Liquid Metal Reactor Design Technology Development ...
539
KR0000195 KAERI/RR-2026/99 M Liquid Metal Reactor Design Technology Development Development of Mechanical Structure Design Technology for LMR A * 7|
Transcript of Liquid Metal Reactor Design Technology Development ...
KR0000195
KAERI/RR-2026/99
M
Liquid Metal ReactorDesign Technology Development
Development of Mechanical StructureDesign Technology for LMR
A*
7|
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S U M M A R Y
I . Project Title
Development of Mechanical Structure Design Technology of KALIMER
II. Objectives and Importance of the Project
The main objectives of the project during the period of '97-'99 project
fiscal years are to develop a conceptual design and computer code systems
for mechanical structure design technology of 150MWe, pool type Liquid
Metal Reactor.
This project is essential since it provides the fundamental skeleton of
reactor system made by systematically implementing the complex interfaces
among core design, fluid system design, instrumentation & control design,
safety analysis and sodium technology.
Reactor structure design development consisting PHTS, containment
system, IHTS, and refueling system needs the design simplicity to meet the
various design requirements developed for the systems, structures and
components (SSC) with effective performance, easiness for inspection and
maintenance, prevention and mitigation of accidents.
Under the sodium operational environments in high temperature of 530°C,
low pressure range of 1 — 10 bars, high temperature structure design against
creep fatigue, ratcheting and thermal striping etc. should be developed for the
thin shell structure to keep sufficiently low thermal stress. On the other hand,
under design basis earthquake of 0.3g ground acceleration, an innovative
seismic design against buckling, seismic sloshing and safe shutdown of reactor
control rods should also be developed to keep the structural integrity for such
thin shell structures, introducing the seismic base isolation design which
remarkably reduces the earthquake loads on whole reactor systems to be more
economic and safer.
In developments of computer code schemes and analysis codes for
designs and analyses of reactor systems, structures, and components, following
four areas are needed;
1) Structural design code scheme for design, links of interfaces and
general arrangements of the 3-dimensional reactor structures
2) Structural analysis code system for the evaluation of structural
integrity of concept design developed
3) High temperature structural analysis codes for the evaluation of
nonlinear behavior of high temperature structures in the creep
fatigue, thermal striping and ratcheting conditions
4) Seismic analysis codes for the core seismic analysis, the
sloshing analysis of reactor vessel, and the buckling analysis of
thin vessels.
HI. Scope and Contents of the Project
1. Conceptual Design of Mechanical System
1) Main Systems, Components, Structures and Piping System of Reactor
System
- Preliminary Conceptual Design of Reactor System
- Structure Design Basis and Design Requirements
- Conceptual Design of Containment Vessel and Dome
- Conceptual Design of IHTS Piping
- Conceptual Design of Reactor Head
- Conceptual Design of Control Rod Drive Mechanism
- Conceptual Design of Refueling System
- Prevention and Minimization of Accidents and Faults Related to
Mechanical System
- Case Study of Reactor Vessel Slenderness and Buckling Analysis
VI
- Conceptual Design of Reactor Support Structure
- Conceptual Design of Support Structures of SG and EM Pump
2) Reactor Internal Structures
- Conceptual Design of Internal Structures
- Conceptual Design of Upper Internal Structure
- Functional Design of Shielding Structures
3) Seismic Isolation System
- Conceptual Design of Reactor Building
- Conceptual Design of Seismic Isolation System
- Conceptual Design of Piping Connection System
4) Preliminary Structure Analysis of Mechanical System
- Structure Analysis of Reactor Vessel
- Response Analysis of Reactor Vessel Sloshing
- Structure Analysis of Reactor Vessel Lower Head
- Preliminary Structure Analysis of IHTS Piping
- Thermal Stress Analysis of Internal Structures
- Structure Analysis of Upper Internal Structures
- Strength Evaluation of Weldments and Creep Fatigue Analysis
- Residual Stress Analysis of Weldments
- Floor Response Spectrum
2. Development of Computer Code Schemes for Mechanical System
1) Structural Design and Analysis Code
- Development of Structural Design Code Scheme
- Development of Structural Analysis Code Scheme
2) Seismic Analysis Code
- Development of Seismic Core Analysis Code
- Seismic Sloshing Analysis Code
- Setup of Small Capacity Structure Test Facility for Verification of
Analysis Results and Codes
- Seismic Isolation Design Guideline
VII
3) High Temperature Structure Analysis Code
- Creep Fatigue and High Temperature Ratcheting Analysis Code
- Setup of Ratcheting Test Facility
4) Code User's Manual
IV. Results of the Project
In this project, fundamentals for conceptual design of mechanical structure
system for LMR were independently established.
- Capability of conceptual design for SSC
- Design integration of interfaces
- Design consistency to keep functions and interfaces by developing
arrangement of reactor system and 3 dimensional concept drawings
- Development and revision of preliminary design requirements and
structural design basis
- Evaluation of structural integrity for SSC following structural design
criteria to check the conceptual design to be proper
- Development of high temperature structure design and analysis
technology and establishment of high temperature structural analysis
codes and scheme
- Development of seismic isolation design concept to reduce seismic
design loads to SSC and establishment of seismic analysis codes and
scheme
V. Proposal for Applications
Design technologies including computer code schemes and analysis codes
developed in this conceptual design for mechanical system for LMR can be
effectively applied for the establishment of concept design and basic design in
the next phases.
- System design to meet design requirements and structural design basis
Vll l
Design data to perform structural and stress analyses for SSC
Interface data for core design, fluid system and I/C, and safety
analysis
Maintenance and inspection design for reactor building and SSC, and
optimization of SSC to achieve economic design
Structural design code : production of 3-dimension mechanical system
drawings using IDEAS computer program.
Structural analysis code : evaluation of structural integrity against
normal and transient operational conditions
High temperature structure analysis code : mitigation of conservatism
in elastic analysis method for high temperature structures
Seismic analysis codes : generation of seismic load for SSC and
evaluation of seismic structural integrity
Small capacity structural test facility : verification of analysis model
and improvement of analysis codes
IX
Table of Contents
Summary i
Table of Contents xi
Chapter 1 Introduction 1
Chapter 2 States of the Arts 3
Section 1 Introduction 3
Section 2 Level of Technologies 10
Chapter 3 Conceptual Design of Mechanical System 17
Section 1 Introduction 17
Section 2 Main Systems, Components, Structures and Piping System
of Reactor System 21
1. Preliminary Conceptual Design of Reactor System 21
2. Structure Design Basis and Design Requirements 32
3. Conceptual Design of Containment Vessel and Dome 48
4. Conceptual Design of IHTS Piping 56
5. Conceptual Design of Reactor Head 64
6. Conceptual Design of Control Rod Drive Mechanism 85
7. Conceptual Design of Refueling System 89
8. Prevention and Minimization of Accident and Faults Related to
Mechanical System 99
9. Case Study of Reactor Vessel Slenderness and Buckling
Analysis 125
10. Conceptual Design of Reactor Support Structure 136
11. Conceptual Design of Support Structures of SG and
EM Pump 157
xi
Section 3 Reactor Internal Structures 160
1. Conceptual Design of Internal Structures 160
2. Conceptual Design of Upper Internal Structure 176
3. Functional Design of Shielding Structures 182
Section 4 Seismic Isolation System 185
1. Conceptual Design of Reactor Building 185
2. Conceptual Design of Seismic Isolation System 191
3. Conceptual Design of Piping Connection System 201
Section 5 Preliminary Structure Analysis of Mechanical System 208
1. Structure Analysis of Reactor Vessel 208
2. Sloshing Analysis of Reactor Vessel 264
3. Structure Analysis of Reactor Vessel Lower Head 271
4. Preliminary Structure Analysis of IHTS Piping 281
5. Thermal Stress Analysis of Internal Structures 288
6. Structure Analysis of Upper Internal Structure 311
7. Strength Evaluation of Weldments and Creep Fatigue Analysis 321
8. Residual Stress Analysis of Weldments 354
9. Floor Response Spectrum 367
Section 6 Conclusion 374
Chapter 4 Development of Computer Code Schemes for Mechanical
System 383
Section 1 Introduction 383
Section 2 Structural Design and Analysis Code 384
1. Development of Structural Design Code Scheme 384
2. Development of Structural Analysis Code Scheme 385
Section 3 Seismic Analysis Code 389
1. Seismic Core Analysis SAC-CORE Code 389
2. Seismic Sloshing Analysis Code 402
3. Setup of Small Structure Test Facility 404
xn
4. Seismic Isolation Design Guideline 415
Section 4 High Temperature Structure Analysis Code 420
1. Creep Fatigue and High Temperature Ratcheting Analysis Code 420
2. Setup of Ratcheting Test Facility 437
Section 5 Code User's Manual 452
1. SAC-CORE Code 452
2. NONSTA Code 464
Section 6 Conclusion 490
Chapter 5 Achievements and Contributions 493
Section 1 Achievements 493
Section 2 Contributions 498
Chapter 6 Proposals for Application 499
Chapter 7 References 501
xni
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Summary v
Table of Contents xi
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3.2.1-9 Concept of Containment Structures
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3.2.1-10 Preliminary Concept Design of KALIMER Reactor System
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NRC4 4 ^ (Regulatory Guides)^ 4 ^ - 4
- 3 4 -
- 1.12, instrumentation for Earthquakes, Revision 1, April 1974.
- 1.59, Design Basis Floods for Nuclear Power Plants, Revision 2, August
1977.
- 1.60, Design Response Spectra for Seismic Design of Nuclear Power
Plants, Revision 1, December 1973.
- 1.61, Damping Values for Seismic Design of Nuclear Power1 Plants,
October 1973.
- 1.76, Design Basis Tornado for Nuclear Power Plants, April 1974.
- 1.92, Combining Modal Responses and Spatial Components in Seismic
Response Analysis, Revision 1, February 1976.
- 1.122, Development of Floor Design Response Spectra for Seismic Design
of Floor-Supported Equipment or Components, Revision 1, February 1978.
(5) *£A
^ ^ f l fl f ^ ^ ANSI 1
do] ^ ^ ^ ^-f n ^ n ^ ^ § } ^ 3 : ^ ^ 5L
^A(envelope)^ 4 ^ 4 - A^7fl^^,
^ ANSI A58.1-1982 - 4 ^ 4 .
Tornado
- 3 5 -
(4)
(5}) ulA><H(Missiles)
NRC 10CFR Part 100^
Sift
- 3 6 -
(4) *W*}^
L ^ 7};
^ ^ 1 * 1 ^ 1 - i ^ l l - ^*H 10CFR100
Appendix A # 1^5} ^ 7fl^ free-field ^1^1°^^ ^ ^ ] ^ ^ ^ :
NRC RG1.6(H
, 0
H ^ § } ^ - ^ ^ e j ^ ^ 2 : # ^ ] tflsflA-] ANSI/ACI 349^]
- 3 7 -
a 3.2.2-2^ 4 4 4 &4- 4 ^ 2 : ~t£ #51^1 ^ 3 H 7]
IS] ^ ^ ^S- i - ^ 3^2*h§- a 3.2.2-3< l
# a 3.2.2-4^ 4ll-f3f 7l7ll-£ ^^7l§Afjl§ol] cfl Sfl ^ ufl «>S] 7J- ?V
4 7]7l
thermal anchor movements^ i ^ - ^ }
(6) 7fl3-&-£l (Material Requirement)
(7})
(4)
(4)
(4) i
(4) -
(4) 03,4- s i i f l t ^ ^ ^ - ^ ^ ^ ^ ^ ° ^ ^ 4 4^H1 4 ^ 7fls.^^4
- 3 8 -
(7) 7}]#.3_£(I & C Requirement)
NRC RG1.12i
^71
| l ^ ] f ] ^ f l j l fl|} ANSI/ANS
2-2-1978^^
(8) ^7Jl^>^ ^(Design Methodology)
o>
(7J-) ASME Code *fl l-§-# Jf^- ^
ASME Code xfl 1^-g- Jff-^ 3Jj7}^ ASME ^ ^ ^ - 7 l Sec. Ill,
Subsection NBU 4 ^ ^ - ^ l ^ l f S t ^ Subsection NF# 4 ^ 4 ^7]-S. 4
IS. i t H ^ l ^ K g - 427 °C
371 °C V]T&)
- 3 9 -
a. NUREG-0800, Section 3.9.3, "ASME Code Class 1, 2, 3
Components, Component Supports."
J l £ ^ - # ( _ $ . i 3 l 4 0 l ^ ^£flo}3]i7ol-^ 427 °C O]AJ-3
371 °C o]Ai-)
a. ASME B&PV Code, Section III, Subsection NH, Class 1 component
in elevated temperature service (1995 Ed. Dec 31, 1995)
b. NUREG-0800, Section 3.9.3
2^-g- J f ^ £ Subsection NC, 4 3f-^ ^-f-^- Subsection ND, 2z$
Subsection NG# 4 ^ 4 - 1 4 ^ 4 W ^ l " 0 ] ovofl^ ^ A]
^ Section III, Code Case N-201-g- 4 4 AAA
(4) 4^1^^] ^ «
7H?} 4^^- i ^
(4)
^ 7^-f T^^1^2:1-Tfl^-(Seismic Isolation System)4
Isolated Structures), TJl-f ^ 7]7l, H E ] J 1
- 4 0 -
(9) ^ l ^ ^ f ^ ^(Testing and Qualification)
Vl
KALIMER
.2.2-4], ^^-§-71 [3.2.2-5], ^
[3.2.2-7], 2%} *AA"%^- ^-^-§-71 [3.2.2-8],
IHTS afl^ ^1f-[3.2.2-9],
[3.2.2-13], Qx}^ 4°]% T&QZ] [3.2.2-14], IHTS
[3.2.2-15] ^o\)
- 4 1 -
3. 3.2.2-1. Safety Classification and Seismic Classification
Safety ASME Code SeismicClass Section/Class Category
or Quality Group
I. REACTOR SYSTEM
Reactor CoreFuel assembliesRadial blanket assembliesRemovable radial shield assembliesControl assemblies
Reactivity Control and Shutdown
III/lIII/lHI/1III/l
Control rod drive assemblies
Reactor Internal StructuresSupport structure includingprimary sodium
Inlet Plenum and Core SupportSupport barrelFixed radiation shieldingReactor vessel liner andseparation platePrimary EM pump dischargemanifolds and sealsIHX seals and supportsCore assembly transfer stationHot pool thermal insulationInstrumentation supportsUpper internal structure
Reactor EnclosureReactor vesselReactor headContainment vessel
Primary Heat TransportPrimary EM pumpsIntermediate heat exchangers(IHX)EM pump coastdown equipment
1
1
111
1
11111
112
111
111/1(1)
QG-A
QG-AQG-AQG-A
QG-A
QG-AQG-AQG-AQG-AQG-A
HI/1III/lIII/l
III/lIII/l
QG-A
1
1
111
1
11111
111
111
- 4 2 -
5- 3.2.2-1 Safety Classification and Seismic Classification
SafetyClass
II. REACTOR PROTECTION SYSTEM
SensorsCableCabinets
112
III. REACTOR REFUELING SYSTEM
Reactor Fuel Handling SystemIn-vessel transfer machine(IVTM)Reactor fuel transfer portadapter and gate valve
Interim Transport System
31
ASME CodeSection/Classor Quality Group
QG-AQG-A
QG-B
QG-CHI/1
SeismicCategory
111
11
Fuel transfer casks 3
IV. AUXILIARY LIQUID METAL SYSTEM
Primary Sodium Processing SubsystemEM pump 3Cold trap module 3Sodium drain tank 3Sodium valves 2Piping 3
HI/3
111/3(1)HI/3HI/3
HI/3HI/3
V. INERT GAS RECEIVING AND PROCESSING SYSTEM
Reactor Helium Distribution SubsystemIsolation valvesPiping
III/lIII/l
- 4 3 -
3.2.2-1 Safety Classification and Seismic Classification
SafetyClass
VI. BUILDINGS AND STRUCTURES
Reactor BuildingHead access area enclosureElectrical and Instrument vaultsPrimary sodium processing and
sodium drain tank vaultsPSDRS inlet and outlet ducts,horizontal plenums, collectorcylinder, and shielding concrete
Seismic isolatorsRadioactive Waste BuildingGround floor and curbs
Mobile Refueling Enclosure
333
3
3
3
ASME CodeSection/Classor Quality Group
QG-CQG-CQG-C
QG-C
QG-C
QG-C
SeismicCategory
111
1
1
1
Wall and roof steel framing 3 QG-C 1
Bridge crane 3 QG-C 1
VI. ELECTRICAL POWER
Class IE dc subsystem 1 QG-C 1Class IE ac subsystem 1 QG-C 1Electromagnetic pump power supply 1 QG-C 1
(1) Portions which form primary boundary
- 4 4 -
I£ 3.2.2-2 Load Combinations for Reinforced Concrete
Seismic Category I Structures
For normal and severe environmental conditions the following load
combinations and allowables are satisfied:
1) U = 1.4D + 1.7L
2) U = 1.4D + 1.7L + 1.9Eo
3) U = 1.4D + 1.7L + 1.9W
If thermal stresses due to To and Ro are present the following combinations
are considered:
4) U = (0.75) (1.4D + 1.7L + 1.7To + 1.7Ro)
5) U = (0.75) (1.4D + 1.7L + 1.9Eo + 1.7To + 1.7Ro)
6) U = (0.75) (1.4D + 1.7L + 1.7W + 1.7To + 1.7Ro)
In addition, the following combinations are also considered:
7) U = 1.2 D + 1.9Eo
8) U - 1.2 D + 1.7W
For extreme environmental, abnormal, abnormal/severe environmental and
abnormal/ extreme environmental conditions, the following load combinations
and allowables are satisfied:
9) U = D + L + To + Ro + Es
10) U = D + L + To + Ro + Wt
11) U = D + L + Ta + Ra + 1.5Pa
12) U = D + L + Ta + Ra + 1.2Pa +1.0(Yr + Yj + Ym) + 1.25Eo I
13) U = D + L + Ta + Ra + Pa + 1.0 (Yr + Yj + Ym) + Es
-45-
£ 3.2.2-3 Load Combinations For Structural Steel
Seismic Category I Structures
For normal and severe environmental conditions, the following load
combinations and allowables are satisfied:
1) S = D + L
2) S = D + L + Eo
3) S = D + L + W
If thermal stresses due to To and Ro are present the following combinations
are also considered:
4) 1.5S = D + L + To + Ro
5) 1.5S = D + L + To + Ro + Eo
6) 1.5S = D + L + To + Ro + W
For extreme environmental, abnormal, abnormal/severe environmental and
abnormal/extreme environmental conditions, the following load combinations
and allowables are satisfied:
7) 1.6S = D + L + To + Ro + Es
8) 1.6S = D + L + To + Ro + Wt
9) 1.6S = D + L + Ta + Ra + Pa
10) 1.6S = D + L + Ta + Ra + Pa + 1.0 (Yr + Yj + Y m ) + Es
11) 1.7S = D + L + Ta + Ra + Pa + 1.0 (Yr + Yj + Y m ) + Es
- 4 6 -
3.2.2-4 Structural Stability
Load Combinations
Minimum of Factors of Safety
Overturning Sliding Flotation
1)
2)
3)
4)
5)
6)
D -
D -
D -
D -
D -
D H
h H + Eo
H H + W
f- H + Es
h H + Wt
H Fl
h F2
1.5
1.5
1.1
1.1
-
-
1.5
1.5
1.1
1.1
-
-
-
-
-
1.5
1.1
Notes: Symbol "H" lateral earth pressure
"Fl" buoyancy force due to maximum ground water level
"F2" buoyancy force due to maximum flood level
S. 3.2.2-5 Minimum Design Loading Combinations for Systems
and Equipment
Condition
Design
Level A
Level B
Level C
Level D
Design Loading Combinations
Design Pressure
PMAX + Dead weight + Thermal(Operating)
(a) PMAX + Dead weight + Thermal(Operating) + OBE + Trans ients(w/ OBE)
(b) PMAX + Dead weight + Thermal(Operating) + Transients(w/o OBE)
PMAX + Dead weight + Thermal(Operating) + Transients + DSL*
(a) PMAX + Dead weight + Thermal(Operating) + SSE + Transients(w/ SSE)
(b) PMAX + Dead weight + Thermal(Operating) + Transients(w/o SSE)
PMAX : Peak pressureDSL* : Dynamic system loading associated with sodium water reactions
- 4 7 -
3.
KALIMER 3 ^ £ lOCFRlOO^ ^ ^ ^ 4 Part50^ GDC16 ^ GDC50
LOCA A>JI ^ o ] ^_g_ ^ 7 4 1 > ^ HH ^ ^
LOCAS} 7EV^. A}JL7\ ^ - ^ * H ?>J1 i f -
Z 3 U
3.2.3-H
[3.2.3-1].
r ^Z] 7}x] 71^-1- ^"^tll[3.2.3-2]
PSDRS 7fl^-[3.2.
# PSDRS ^ 7 1 ^
- 4 8 -
. ii*144 &JL 500 °C,
250KMM 7 1 ^ - f M 4 ^ ^nna\ W - ^4^-§-7]4 ^ - M 4
^7l 7fl >i7fl ^ r ^ l ^ ^ H ^ 3.2.3-24 go) Qz\3.x
M. ^ ^ 7 H H ^^"-§-71 ^ - 4 ^ # € 4 4
ell[3.2.3-5] ^
# € 4 1 - ^ - J I ^ 3.2.3-2011 j i ^ 4 4
ASME Section IIH ufef ^TJlsflo]: ^ j - ^ QT}SL 7} 7}
Subsection NE[3.2.3-7]7> ^-# ^^-§-7]6fl tfl
2]^-^£fe 371 °C4^1 ^
-^-4 H ^[3.2.3-8] PSDRSi
2.25Cr-lMo 7j-6)| tflsfl ASME Subsection NE l ^-g-
3711:* ^^r 5L-&2] ^ 3 , 4 4 - 4 4 4 ^^-g-71 >i7flA] ASME
Subsection NH[3.2.3-8]!- 3-§-«fl°> 3]-7l nfi -«i Subsection NH ] 4^- ^7^]
°fl §1144^- Subsection NB[3.2.3-9]1- ^
500°C, 0.
3.2.3-2 ] 4 4 ^ 1 4 4 ^°1 4 ^ 7.37m, SV^-^Hl-
18.8m, ^ 2.5cm^]4.
4- *
\^z ^^l^rS. 45014 QA*^ 240KPai4
- 4 9 -
7 ^ ^ <g 7\
HVACI-
^ £ # ° J ^ ^ SIS.^ personnel air
IHTS
A}2}-
[3.2.3-13]^
3.2.3-301]
UIS, EM pump
- ^*V I -EE^I l7fl, ^ l ^ ^ ^ ^ ^ l ^ USS
(Ultimate Shutdown System)^- ^ *V ^sflxl 27fl# f-tfl J Z ^ 47fl^l ^ - ^ #
Aj-a-s-jzi. § f « - § ^ ^ ^ ^ J f - ^ f Torispherical ^ - S . o l ^ - ^ ^ ^ c f l Tori-
spherical ^-^-^ ASME Section III, Appendices, Article A-4000[3.2.3-14]<*f].*]
^ 1036.5m3ol
-^r 2.25Cr-lMo7j-AS.
& 3.2.3-34 ^ o ] ^ ^ 14m, £ o ] 8.4m,
KALIMER
- 5 0 -
7}
HAA
3.2.3-4^ 7EVo]
Support ringl- ^
Support ringo]
fe 7A
3.2.3-1 KALIMER
7^ a]
ifl^- ^-3]
^^-§-71
500 °C
250 KPa
737 cm
1880 cm
2.5 cm
2.25Cr-lMo
66.9 m3
450 °C
240 KPa
1400 cm
840 cm
2.5 cm
2.25Cr-lMo
1036.5 mJ
- 5 1 -
3.2.3-1 KALIMER
-52-
Bolts
CV Flange
1880cm
30cm 10cm
ContainmentRing
Reactor Support/Reac to rHeaAichorBoItn2i/
it
Bolt Seal
" Omega Seal
3.2.3-2 3,7]
- 5 3 -
3.2.3-3 3 t f 1/2
- 5 4 -
Insulation
Containment dometemperature ~40C
InsulationPlates (22)
Hot Pool Sodium
-53OC
Containment Boundary(fixed seal)
Containment Ring
Reactor Head
-230 C Normal
PSDSS
Air out temp- 100C
Air In temp ~ 40C
RV Liner Collector cylinder
3.2.3-4
- 5 5 -
4. IHTS fl H
7\. KALIMER ol
(1) IHTS ufl^Tfl
KALIMER[3.2.4-1] *I*1] *)^$] 1 ^ 7 } ] ^ H& 3.2.4-14
$14- ^ 3.2.4-1 A-] 4 TJ-O] IHTS^r IHX # ^ ^ £ 7 f 511
Jl ^ T ^ S - f e 339.7 °C^ IHXS] # . ° J ^ ^ - ^ 4 7 > 171.3
2.571 °g-^.S ^>gs]«H 9X1= JL^ ^<a-^ <
^Js i l^J IHTS4 ^ " ^ ^ ^ 3.2.4-2^1 A 4
KALIMER IHTS n^$] Hfl l [3.2.4-2,3]
3.2.4-3ofl ^ 1 ^ 5 ] ^ X14- ^ 3.2.4-3 ^ 6 1
^ 7fl S] IHXS-^-E] 4 - ^ JL^^-ol -^45.7^1- B3i H> 6flA-l Tee
^ 1 4 4 - ^ ^ 3.2.4-3^A-] Tee ^^•^-•y ^ ^ 5 4
f- 7fl n&^r 14"SCH40^
20"SCH40S] c ) l^^
^ * } ^ ^-S^lr^-ar 5 ,^4 . ^ ^ ^ ^ « m ^ ^ 1 : ^ ^ ° ! 53.34cm,
^ 76.2cmo]4. z | ufl^ ^ o} ^ j ^ ^ . s 3.2.4-1^], nefjL IHTS
4 i ^ ^ ^ - ^ i ? ] 4 ^ a 3.2.4-2i 4 4 4 9XA- IHTS tifl^ TJI^O]
^ =L& 3.2.4-4ofl ZLS]J1 s j ^ £ ^ r n ^ 3.2.4-5^ ^ A] S] O] 014.
(2) <
IHTS tifl^^Sl ^ A ^7]lA^o_S-ir ^*(|, IHX4
4 , fl IHTS ^
i t b 10m ojAj-^. ^ ^
IHX4 SG4 f1^
- 5 6 -
(3)
H ^ 3.2.4-2^
^-#^1 IHX ^ o .
(4) g-§-^
KALIMER IHTS ti^Tili^ ^ ^ - ^ ^ ^^f- ^ ^ ^ ] ^ i 7}^-
Jl, H 5 . - f S l - *]-%-f± ^^}7^o] ^ 4 . n ] ^ ^ PRISM[3.2.4-5]^ IHTS
Gimballed ^ S - f ^ l - fl-g-*V w}^ -fi-^5^ EFR[3.2.4-6]^
- KALIMER IHTS
^ i tfltbSZ-tr
(5)
§T] hanger x]x] ^ i f i ^ S 4-§-*>^4- KALMER51 IHTS
77fl l hanger x]*]^^*] ^ ^
- 5 7 -
(6) 71 Ef JlS|Af*J-
] fflTS
IHTS «M ^ ^ f e i # ¥ ^ 1 tflal^H catch1 ^*1 Aj-Jl a^oJlA^ IHTS
IHTS tiM^life ^^r ^a^lf- ^wM°l ^-^-Slfe v}
- 5 8 -
3.2.4-1 Design features of KALIMER IHTS
IHX
SG
IHTS EMP
Large bored piping
(Hot Leg/Cold Leg)
Small bored piping
(Hot Leg/Cold Leg)
O.D
IHX-IHX distance
NumberO.D
Height
No.O.D
Height
NumberO.D
Thickness
Pipe spec.
Radius of curvatureO.D
Thickness
Pipe spec.
Radius of curvature
Horizontal distance of IHX-SG
Design feature of KALIMER1.2 m
3.74m
4 EA2.8 m
18.8 m
2 EA1.32 m
5.44 m
2 EA50.8 cm
1.506 cm
20SCH40
76.2 cm35.56 cm
1.113 cm
14SCH40
53.34 cm
11.5 m
3.2.4-2 Design parameters of KALIMER IHTS
ParametersDesign pressure
Operating pressure
Faulted pressureDesign
temperatureOperating
temperature
Hot legCold leg
Hot leg
Cold leg
Design features2.5 MPa
0.35 MPa
15.5 MPa530 °C395 °C
511 °C
339 °C
- 5 9 -
CORE mx SG TBN
530°C
386.2°C
529.8°C 511°C 511°C
3SSPC 339.TC 339°C
EMPHeater
3.2.4-1 Normal Operation Condition of KALIMER
Contnmnt Dome(0D=14m)
2.64 m
RxWall(t = 0.9m)
D=35cm
SOSm
II 5m
2.4m
1.87
2.765.02m
IHTS
(OD= 1.32 m)
3.2.4-2 Plan View of KALIMER IHTS
- 6 0 -
Nodal coordinates
IHX: small pipe
: large pipe
IHX
3.2.4-3 Schematic Diagram of KALIMER
IHTS Piping System
Node
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0000
186.7373.5373.5373.5373.50
186.7373.6186.716.716.7186.7186.7-13.3-13.3186.7186.7426.7426.7426.7426.7-249.3-249.30.70.7
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Small pipe (14"SCH40)
:Do: 35.56cm, t=l. 113cm
p=53.34cm
Large pipe (20"SCH40)
:Do: 50.8cm, t=l.506cm
p=76.2cm
- 6 1 -
Co-axial
piping part
3.2.4-4 KALIMER IHTS Piping System
3.2.4-5 Plan View of IHTS
- 6 2 -
EM Pump
3.2.4-6 Intermediate Heat Transport System of KALIMER
- 6 3 -
5.
KALIMER Q } n ] i fl^ ^ [
-^^l ^ < M ^ a ] A S y ^ o H 1^3.2 .5-2]
^7} 3.7% 4 ^ ^ 4 . 71^5] ^^}S^1 *R-2 : ! - £ H ^ 3.2.5-H]A^
30 7 ^ o . S . 127H51 x j ^ i l l - o]^-t><^ ^l^l*l-fe i H H 8 n f . o] 6\]
^ [3.2.5-2]i^^r Z l ^ 3.2.5-2^1^5)-
0>*Vo_S 30cm <£%& T]X]$ 7 ^
.2.5-4].
^ - ^ KALIMER
(1)
-§-71
- IHX (4 7]])
(47fl)
I S (access port : 1)
- UIS (17U)
- IVTM (I7fl)
^ 7U> 71 71
- 6 4 -
RV
S. -
RV ifl S.^r ^ 2 #
^-(gas-tight seal)o]
^ £ 1 ^-^^r seal
membrane seal)0]
^. a 3.2.5-H
7.37mo]c}. KALIMER
n ^ 3.2.5-5^ ^-nf.
7]
^ ^-[3.2.5-2]i
(2)
KALIMER
16mm-?] 227^7}
45cm
85.8^6]]
3.2.5-6oll
(3) SflS.
, EMP,
EMP
^ 3.2.5-4
3.4m^ ^
. ^ y}5f
. 2) *} # ^
^ ^-(welded
- ^ ^ 30cm
3.2.5-1^]
-f-
3.2.5-9
- 6 5 -
ledge ^ °fl * H £ H ledge
3.2.5-8^1 5 ^ 1 S ^ l ^ M O1O.B] zi& 3.2.5-7
IHX riser!- ^-g-^H €^VS.^H 3 3 IHX f } £ ^ f-^*l 3 ofl
- °^7H ^}S«HH<>flfe 4 7 ^ IHX7> ^1^5]^c|l
, IHX Risers ^4^ 0.6m^cf. IHX v}^
A ^ 47l]7f -M 1 sq^ti l ° 1 ^ ^ A J - ^ ^ ^ 3.2.5-8^
, 3.2.5-11^1^ a . ^ ^JJII- ^ o ] xl^l ^ 3 ^ u l ( 5 l ^ l . l75m)i ^
i HAA(Head Access Area)S^l
^(thermal bow)-§- ^4:S}-^?14. ^^>5.?i#- fl HAA^]
^ 38 °CS ^^§VJ1,
ufl ^5L^r 52 °CS. -i
KALIMER^ ^ - f ^^11 ^ ^ 1 ^71171- 65cmS
4.
•& ^ ^ ^ ^ ^ KALIMER ^^fS-SflHS] ^A}^7\%: 5]^ ^ ^ 7fl ^
[3.2.5-1,3]
l, 3fl.EL°ll
- 6 6 -
o}6\)
(1) i^l * 1 ^ ^
o i ^ KALIMER
3.2.5-2
IHX ^ EMP7]- ^-^-slfe- ^ ^ ^ ^ ^ ] Ml^^ \.2mSL
20cm, 25cm, 30cm, 35cm ^ 40cm£1 ^-fofl tfltb
«} $I4[3.2.5-8]. x l ^ l ^ t ^ l ^ E ] - ^ ^ ;g-f [3.2.5-2,6]ofl
(2) ^
-S^H^l^ 7]7]*\ 7] 7]
;«*1#(PRISMS1 4^- : 5271]) ^ ^fl^
7l ^|§f^ ZL& 3.2.5-12^A^ go] IHX, EMP
ANSYS £ 1 ^ DL 3.2.5-125}1 ^ ^ : i ^ « M ^ 1 ^ ^ 1/4^^ S - l ^ ^ ^ 4 - TllS^l^-^A^ 6
, uy, uz, x, y, z)t- fe €
- 6 7 -
4 4 4 r # 20cm
, y)5] 3 4 ^ ^-
(3)
- ^ [3.2.5-7]
i£ 3.2.5-2ofl
H^ 3.2.5-125] s f l ^ l ^ j 5]^i
2]^i#5izi #eflxl Aj-o]] - a 3.2.5-2^^5}- 7EVol ^ J t ^ ; CRD, UIS,
IVTM ^ 7Jl#^-yl ^ ^ 68.611- o} ^
8009.4 (N)5] ^ ^ ^ } ^ o l -g-§1-711
4 ^ ^ i ^ r 3771.54 (N)4 4f^°l 4 ^ 4 ^ , 711 254^1 S ^ 5 ^ s]ol °lo] z> ^ ^ o i l ^ ^-^4711 4714.42
(N)4 4^°1 4-§-44 44-4 4 ^ - e ZL^ 3.2.5-125] 3~4^^^OH1^ %*}
^ i f - f- # 1013.57^.5]
4 ^ i ^ 59161.12(N)4
4 . § f l ^o^ CV7> 4 4 ^ ^ ^ 3.2.5-125] 5 ~ 6 < i ^ l ^ 88.51^-5] CV4
^0} ^^.gj.^cfl o] A1AO>OI 43^^ofl^ 5046.1(N)4
4-
(4)
7] 71
-68-
3.2.5-13^r
3.2.5-14^ CFX S^[3.2.5-
^ ^ 223 °C, *}•$.#•& 230 °C£ M-Ef^^cU o]
PRISM[3.2.5-9]5] ^^^Ef l ^ S ^ H ^1H^ ^ £ 7 ] - 100 °C
} } ^ }^ )} Slfe ^ ^ seal J f £
seal &43. *1*>< ^ ^ ^ 7 B ^ ^ ^ ^ j - J L $14
. KALIMER ^ ^ S . « f l H ^ ^:3£7> 200 °C O]AJ-^_
44 44\+
(5) -g-^sfl^ % - i ^ l ^ ] ^ ^ 4
KALIMER ^ S - S f l n f e ^ - ^ i ^ i ^ ^ £ ] S - S . ASME Section III NB1-
44 ^^1^4- s*> 4
# PRISM[3.2.5-10]
a°HAi ^i-g-^ 4 4 £°1 20cm, 25cm, 30cm, 35cm ^40cmS] ^-fofl cflt}^ -g-e^^-!- ^^^. ^ ^ ^ a 3.2.5-3^ ^ H ^ 4
[3 .2 .5 -8 ]^ ] H l «
-69-
3. 3.2.5-3^^ SLTT 4 4
Sfl
3.2.5-15^^^ go] ^T?\}7\ 30cm
^ 2 ] ^ ^ ] ^ ^ r 0.83mmS 6.35mmiL4
3.2.5-1 KALIMER
^ ^
*r# (EA)
*H
As.
7jo] (shell)
KALIMER J@ *|-3.3I1 H&
16.0 mm22.0 mm
22316SS
^^>S«11 .
45 cm
30 cm304SS
702 cm
5 cm17.6 m316SS
- 7 0 -
i t 3.2.5-2 Weight of Components and Systems for KALIMER Reactor
Structure
^ ^ I - S J Z L + C U I S + C R D )
EMP (1EA)
IHX (1EA)
RVifl ±^
-xl x] tifl Jnlet Plenum
^7\] ( S ) :35.61+(33)
20
25
25
85.8
88.51
165.89
421
426.68
5. 3.2.5-3 Analysis Results of KALIMER Reactor Head
(cm)
20
25
30
35
40
2.73
1.42
0.83
0.53
0.36
rDM1-
6.35
*] (mm)
9.84
5.10
2.99
1.90
1.29
46.08
40.8
28.7
21.3
16.5
38(5.8
. (MPa)
99.95
64.13
44.64
32.88
25.23
-71
Bolts
CV
1687 5cm
ContainmentRing
Flange \Reactor Support/
R e a c t o r H e a Anchor Bolt (12) /
th
30cm 10cm
3.2.5-1 Previous Concept of Reactor Support Structure
- 7 2 -
Insulation Support Ring
\
Containment Boundary(fixed seal)
Reactor Head
-120C Normal
HeInsulationPlates (22)
Hot Pool Sodium
-530C
Ar
RV CVRV Liner
PSDRSAir out temp ~ 100C
Air In temp ~ 40C
Collector cylinder
3.2.5-2 Current Concept of Reactor Support Structure
- 7 3 -
-12)11- Lubrite A[g-li?f SI g
-316SS¥ l 5 C m , i ' 0 l 1855 Cm
-2(1/4)Cr-lMo2.5 Cm, & 01 1880 Cm
3.2.5-3 KALIMER Reactor Structure
- 7 4 -
Support Rin00 767cm
UISOD 140cm
IHX (4)OD 120cm
Thermal LinerOD 687cm
Reactor VesselOD 702cm
Containment VesselOD 737cm
3.2.5-4 Plan View of KALIMER Reactor Head
3.2.5-5 Penetration in KALIMER Reactor Head
- 7 5 -
ROTATING PLUGFLANGE
PINS AK3 SPACERS
3.2.5-6 Construction of Insulation and Shield Plates
- 7 6 -
3.2.5-7 Arrangements of Insulation and Shield Plates
- 7 7 -
3.2.5-8 Components supported by Reactor Head
- 7 8 -
CANOPY SEAL(316CRES
0:25 WALL)
DYNAMIC SEAL(INFLATABLE
ELASTOMERICI
ROTATING PLUGTIE-DOWN BOLTS
BUFFERED STATIC SEAL(4 PLACES)
JACK ATTACHMENTAREA
TIGHT SLIP FIT TO PREVENTTORQUINC BELLOWS
SUPPORT CHOCK SPACE
FIXED CLOSURE FLANGE
12 in.
RING GEAR
TOP SEALRING FLANGE
ROTATING PLUGANTI-ROTATION
TAPERED THRF"" 1—
RP SUPPORTBEARING
PRIMARY SEAL(INFLATABLE
ELASTOMERIC)
MAINTENANCESEAL
ROTATABLEPLUG
3.2.5-9 Alignment of Reactor Head and Rotating Plug during Operation
- 7 9 -
IHX MOON TINGFLANGE
, RE. ACT OHDEC*
1
3.2.5-10 Supporting Concept of IHX
EMP Flange
Reactor Head
Pump penetration : 1.2m O.D
Support cylinder. (I >175m O.D)
Reactor Head
3.2.5-11 Supporting Concept EMP
- 8 0 -
7 ^6 jf +
3;-;-
|:
• i
2
Reactor Head -
AN^ ^ ^ g : ^ . ^ Supporting line
-itIt f iC7f«S : f l^sS-^^ '12 : Rotating plug
^ ^ ^ ^ ^ ^ S ^ - * 5-6-7-8: support ring
Ro]
_xrinc" IMP
type support Xlt-30em) ^ ^ ^
4 5
Fig. 3.2.5-12 Finite Element Model of Reactor Head
- 8 1 -
Containment Dome(Argon gas)
Reactor vesselCenter line
Reactor HeadInsulation
Upper Helium gas region
Insulation plate (22 plates, t=?16mm, gap=22mm)
Lower Helium gas region
Hot pool surface3.435m
3.51m
3.685m
Ar
Reactorvessel
' Thermal lirier
Containmentvessel
3.2.5-13 Configuration of Reactor Structure
- 8 2 -
3.2.5-14 Thermal Analysis Results along RV Axial Direction
Reactor Head - ring type support (t=30cm)
C&VG)
ANSYS 5.5.3APR 11 200011:33:25NODAL SOLUTIONSTEP=1SUB =1TIME=1UZRSYS=0PowerGraphicsEFACET=1AVRES=MatDMX -.01497SMN =-.832E-03^ -.832E-03S I -.740E-03fSB* -.6-37E-03
-.S55E-03-.462E-03-.370E-03-.277E-03-.18SE-Q3-.925E-040
CDmm
CD
3.2.5-15 Vertical Deflection of Reactor Head under Thermal and Dead
Weight Load
- 8 3 -
Z XReactor Head - ring type support (t-30cm)
ANSYS 5.5.3APR 7 200016:55:18ELEMENT SOLUTIONSTEP=1SUB -1TIME=1SINI (NOAVG)PowerGraph icsEFACET-1DMX =.01497SMN -55797
=.287E+0855797.324E+07.642E+07.960E+07.12BE+08.160E+08.191E+08.223E+08.255E+08.287E+Q8
SMX
CDE3E3enCD
3.2.5-16 Distribution of Stress Intensities for Reactor Head
- 8 4 -
6.
3.2.6-14
3.2.6-H7}
ension member)^
(armature)^-
44.
$14.SLB\
(driveline)
44
tube)
44
B4C#
4.
A
- 8 5 -
. A
A
USS(ultimate shutdown system)7>
USS^r ii-a ^
(SASS) 7 l ^ # ^o>4^ 7 ^ ^ - 33*l#*]oM [3.2.6-2],
B4CS- t > l - ^ ^ ^5^ 7flS]
icf[3.2.6-l].
4. f-*11S, ^ 5 ^ # ^ A ^ ^-g-§>^ ^ I f e ^4^°H £\^*\ B4C
. B4C
USS
USS
ULOF(unscrammed unprotected loss-of-flow), ULOHS (unprotected
loss-of-heat sink), BEfe- UTOP(unprotected transient overpower)
- 8 7 -
3. 3.2.6-1 (CRDM)
Housing
Shim motor
Drive shaft
Screw driver
Motor support level
Drive nut
Rod stop screw
Rod stop drive gear
Diameter
30/27 cm
6 cm (1.5/2.5cm)
10 cm
6cm
100cm from bottom
17.08/(12.5/10.5)cm
2.5cm
8. 5cm
Length
400cm
50cm(5.0/2. 0cm)
360cm(-150cm)
150cm
Thickness of 2cm
2.0/10cm
80cm
2.0cm
3.2.6-1
7.
18
(In-Vessel Transfer Machine)^!
(Fuel Transfer Station)* -f-Sfl
-§-71 (Fuel Transfer Cask)ofl ^o ] - ^ ^ A j ^ ^ O ] ^ A | ^ 1 4 . ^ 3.2.7-H>H
*\%*]-£•£:
(1)
3.2.7-2^
- 8 9 -
7} #& #7]
Q4-7], 7}°],
t}7) ^]*>
m 5. ^.o] <^±v] main tube 4 } ^
0.915
1^^1H ^ $14- ^ ^ 3.2.7-3 ^ ^ i ^
^ ^ 3 J ° 1 * A £\ r ^cfl -tl^Al 0.3048
0.9144
(2)
(gate) l i
4 - 5E*> ^
hoists
(3)
2.743 m
. o l .
3 . 2 . 7 - 5 ^ s ] ^ i 4
n ^ 3.2.7-60JI 4 4 4 5 1 4 .
- 9 0 -
#£iHTr ledge seaH
hold-down
tacometer^l 51 sfl ^ r #
^ encorder
(4)
^ 67fl^
cflsfl SB]
t> cover
67fl 51 carousel
(5)
(6)
71
13)
(7)
- 9 1 -
1- f-sfl
3.2.7-8i
Sflo^jg.
Reactor Building
Fuel Handling andStorage Building
at n
3.2.7-1
- 9 2 -
m t n )
Telescopic Tube Length
/ Telescoping coupling
Grapple Assembly
r~ EL. o
EL. 11800
150X150
& 3.2.7-2 Pantograph Type IVTM
- 9 3 -
36 in
Top of core
i
Retracted Position Extended P osition
3.2.7-3 IVTM S]
- 9 4 -
Center of Reactor Qgj$(RC)
. KALIMERCore OuterDia.: 3381 mm
Control Rod Drive
RP Jacking
Mechanism
Plug Drive
Ultimate Shutdown
Assembly (356 O.D)
Center of Rotating PJ gTCF)
2845
Rotating Plug
(2743 dj.a.)
OffsetfromR.C(211)
IVTM
(600 O.D)
FTS (600 O.D)
Support Cylinder
QZ13O.D)
3.2.7-4
- 9 5 -
Center of R.C
2845
Center of RP483 j
< f-915 T T
EL. 900
EL. 300
EL. 0
" EL. -300
280 211
2743
600
1371.5
3.2.7-5
- 9 6 -
RP Support
3.2.7-6 RP seals]
3.2.7-7 RP seals]
- 9 7 -
Rotating Plui
1681.0
1771.0
1846.0
1910.0
Insulation and
Shield Plates
Fuel Transfer
Station
EM Pump
IVTM
IVS
3.2.7-8
8. 7] 7 ^ 2 : # £ A>JL
7}. o f l ^ ^ ^ ^ £ = .
[3.2.8-1]. ^ ^ 1 ^ - ^ S . ^ ^ S ^ l ] ^ i f - ^ ^ z ^ f l S A>-g-§]-7l
(1)
7171S1 ^S] ^-^1 f-afl ^ ^ 1 ^ 1
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4-S-,
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3.2.8-H
4.
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2:4
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$14.
3.2.8-1
Phenix
S P X
Fermi
EBR I I
D F R
P F R
KNK 1
SNR
BN 350
BN 600
Rapsodie
Monju
711
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5
2
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1
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(In-Service Inspection ; ISI)7>
.2.8-5].
^^l^^S-Oi] cfl*> 7\^^7iA\ ^ . ^ ^ ASME B&PV Section XI
Division 3 i 4 4 fl-^€4[3.2.8-6]. Section XRr 7 } ^ ^ ^
^ ^ ^ 71 A\ ^ ^ 7JA|- ^711- 7)^t}5L $14. KALIMER
4 ^ ^ ^ ^ ^ - S . ^ ^ € Tfl-f-4 ^ ^ ^ ASME fl-^#
4- i^r^°J ^^11- ^o1]T= A S M E
31
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(71-) 3 4
oJj^^-^^L^ ^ m JjL -ofl cfl*V 7f^^7jA}^ f ^ o j ASME Sec.
XI, Div. 3£ 7 > ^ 3 4 ^71, 3 4 W «.=., T^AJ-ti *J 7JA)- ^ ^
3.2.8-2) 31 *>^ -£?fl ^ < H $1^4 ASME 7}^-^
KALIMER
ALARA
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B-A
B-B
B-C
B-E
B-F
B-G
B-H
B-J-l
B-J-2
B-K
B-M
B-N
Guard Vessels. i i J ] r
Guard Vessels. JiJLSl^l
?}&] 7 f i l-}] 7)1 7l 7l
t r - - o irj r - * •• ^ r ^n "^
Guard pipe EETT ^ r i S .
Guard pipe JE.^ ^ 3 - S .
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^1-S-^-T"^ 33%
^-g-^-T-5] 33%
^ • g - ^ ^ 100%
d ^ ^
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7 Til 51 33%
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34 71
2,f (7^)
3^} (13\l^]r)
4x} (17\£ V)
34 471
1 - 3
4 - 7
8 - 10
11 - 13
14 - 17
18 - 20
21 - 2324 - 27
28 - 30
31 - 33
34 - 37
38 - 40
*\± 34 #s*
100
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16
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1 - 3
4 - 7
8 - 1011 - 13
14 - 17
18 - 2021 - 23
24 - 27
28 - 3031 - 33
34 - 37
38 - 40
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10016
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3.2.8-1^
A}
-§-7]
RV4
150 °C ~ 200
- 1 0 7 -
oflo] o o 7]-^ ^ f ^ 3}*} 3- -§-7]4 2^-g-7l Afo]o^ 5^^ 7fl ofl
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3.2.8-24
$14.
-71 ofl ^ 4 ^ 4 - ^ °l-g- S^ :^ ^14S SflH°fl $I r ISI
(4) ^
VTM-3
TVofl 1«]- VTM-3^4# " r ^ 4 ^ n r ^ ^ ^ * ^ 4 ? 5 : 4 . ( ^ ^ 3.2.8-2)
- 1 0 8 -
Reactor Vessel
VTM-2, CM, VI
Containment Vessel
VTM-3, ILRT, CM
Primary
VTM-2,
EM Pump
CM
Int. Heat Exchanger
VTM-2, CM
Reactor Internal
VTM-3, CM, VI
Reactor Head
CM
Rx Support Structure
VTM-3
VTM : Visual Testing Method-1,2,3
USV: UnderSodiumViewing
CM : Continuous Monitoring
VI : Volumetric Inspection {UT, ECT)
SI : Surface Inspection {PT, MT)
ILRT : Integral Leak Rate Test
LLRT : Local Leak Rate Test
Containment Dome
ILRT, LLRT
Residual Heat Removal
VTM-3, CM
Primary Cover Gas Sys
Int. Heat Transfer Sys
VTM-2, CM, SI or VI
Isolation Valve
ILRT, Performance test
Intermediate EM Pump
VTM-3, CM
Steam Generator
VI, CM
3.2.8-1 KALIMER
- 1 0 9 -
ISI Access
Port (12)Monitor
Reactor Head
15cm
Reactor Vessel
(SS316) 5cm
EMAT Sensor
Video Camera
Ultrasonic Equipment
A
Video Recorder
Containment Vessel
(2-1/4 Cr-Mo) 2.5 cm
3.2.8-2 -§-71 -§-71^
- 1 1 0 -
RV/CV
tfl^-5] ^ J l 71714
VTM-37]- A ^ i ) ^ ^ ^ } ^ ^ r # ^ ^ tfl
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3.2.8-34
- 1 1 1 -
4- TW 1-Hfl ^ ^ 11 f ^ ^ r IHX
Ultrasonic Equipment Monitor
Manipulator
Ultrasonic Transducer
ISI Port
IVTM
3.2.8-3
-112-
HAAi
^ 71
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bulletin^- ^ ^ A ] ^ O ] § | ] ^ ^
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4 4 10% ^ £ 4 ^ ^ - 1 - fl 7 A)-7R>
(SGACS)4 ^ 7J 4 ° l S ^ ^ ^ 4 ^ ^ TV -7
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Detection)^ ^ ^ -g-%Va-*] (Passive Acoustic Leak Detection)-^ ^ - ^ ^ - § -
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(3)
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71
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$14-
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KALIMER
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(4)
reventive Maintenance : PM)4
ive Maintenance
57^1
^ ^ i ^ ^ ( D i s c r e t i o n a r y PM) H^Jl
(Preventive Diagnostic Maintenance : PDM)S 4 T 1 4 -
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(4)
iJ-'S-i- 3. 3.2.8-44
- 1 1 9 -
(7\)
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KALIMER $] JL^r ^-^ 3LB\f>\5L ASME Section XI Division 3
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- KALIMER5] 7fl^ ^ ^ 1
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124-
9.
} &4[3.2.9-l,3.2.9-2].
Okada f-ojj <q
) - ^ ^ } ^ s ^ ^ 7 } # ^«S^>J1 ASME
Code Section III, Subsection NH[3.2.9-3]°M
7}.
(1)
(3.2.9-1)
• 1 2 5 -
(3.2.9-2)
(3.2.9-3)
^(3.2.9-2), ( 3 . 2 . 9 - 3 ) ^
^ AA
, 0.2% ^l-
flS., ^ 304SS, 316SS
Ramberg-Osgood^ ^ - ^
rjc = Min[\.Q, 1.04tanh(0.98.707£ lcrccre)] (3.2.9-4)
Vs = M«[1.14tanh(rO7£/rc%), tanh(1.6ro.7£ Irscre)} (3.2.9-5)
yft =1.0 + 0.21sech(3.5o-07£/<rJ (3.2.9-6)
ys = M«[1.0 + 0.22sech(1.7ro7E/<J, 1.0 + 13.0sech(6.4r07E / rscrj] (3.2.9-7)
[3.2.9-5]^
(3.2.9-8)
(3.2.9-9)
( 3 . 2 . 9 . 1 0 )
(3.2.9-11)
- 1 2 6 -
[3.2.9-6J. J. Okada
= 0.66^-0.9,1+1.0 (3.2.9-12)
A~~T1 (3.2.9-13)
^ ^ # ^ §tf^fe 0.5< L/R < 5.0 nelJL 50.0 < M < 500.0^4.
(2)
sfl (Eigenvalue Buckling Analysis) yo
VlH-4 til^i^ 2)-i-«l]^ (Nonlinear
Buckling Analysis) yo
Vtt!ol
point)!-
(3.2.9-12)
j 1 (Stress stiffness
matrix), A fe- 2}-
^7}A]
- 1 2 7 -
Snap-through 2 f ^ ^
. KALIMER
(1) KALIMER
3.2.9-1^-
-fe- 316SS
KALIMER ^
a t H^Jl 7]7l
702cm, -Tfl 5cm, 1700cm
(2)
3.2.9-25]-
KALIMER
510°C(950°F)#
ASME Code Section III,
ANSYS version 5.5[3.2.9-7]l-
SHELL63
SHELL43 &.±^
£=160 GPa
Subsection
316SS
^ ^ ^-A]^(Isochronous)
510°C M ^ 3xlO5
3.2.9-3-1:
KALIMER
Qcr = 1200
Qcr = 31829 tons
- 1 2 8 -
: Qcr = 19252 tons (
: Qcr = 2000 tons
5)^71
KALIMER
KALIMER
3.2.9-5^ KALIMER
7}
3.2.9-6^ KALIMER
R/t7\ *}
§ H ^ ^ S ^ « t KALIMER
= 19252 tons°]v\ °}?e D.% 3.2.9-5^1.
- 1 2 9 -
Qbcr.e=20000 tons3\
2000 toS 0cr=12OO tons
3711 ^ ^ - $14- 3.2.9-7^
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III, Division 1-Subsection
Jl $14-
:71
4^-4ASME Code Section
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imperfection^
- 1 3 0 -
l ^ ASME
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(3.2.9-13)
oil tfl fl ^7]1 ^ ^ ^ S ? l A, B^l tflsflAife 3.0, ^ ^ S ^ i C
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KALIMER
KALIMER ^
^ - f 0.9g,
q-. 1 4 4 ^ KALIMER
tons, ^.^.AiA^ ^ - f ° H r 26=171.9
KALIMER
: Load Factor = 1.09 < 1.5 ( £ * I 2 : ^ D)
: Load Factor = 6.98 > 1.5 ( ^ S ^ D)
- 1 3 1 -
KALIMER ^ j ^ 1 ^ ^ f ] f^
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- 1 3 2 -
3.2.9-1 Conceptually Designed KALIMER Reactor
Fixed B.C.
3.2.9-2 Finite Element Analysis Model-1/2
- 1 3 3 -
s.»w
£V)
(1) ASNIE Code Section ill, Subsection NH(2) Material = 316SS(3) Temp = 510°C(4) Service Time = 3x10s hr
0.00 0.25 0.50 0.75 1.00 1.25
Strain (%)
1.50 1.75 2.00
3.2.9-3 Stress-Strain Curve Used in Buckling Analysis
(a) Eigenvalue Analysis (b) Nonlinear Elastic Analysis (c) Nonlinear Elastic-Plastic Analysis
3.2.9-4 Buckling Model of KALIMER Reactor Vessel
- 1 3 4 -
40000
30000
C 20000
10000 -
0 -
Elastic BendingElastic ShearPlasticPlastic and Imperfection
Imperfection Q
Shear Buckling Bending Buckling
L/R
3.2.9-5 Slenderness Effects on Buckling Loads
a " 30000
\ v l \ \ • Thickness = 5.0 Cm
i —— R = 300 Cm— R = 400 Cm— R = SOO Cm—•— R = 600 Cm— R = 700 Cm
Nonlinear Elastic Analysis
Won linear Elastic-Plastic Analysis
O- O - O - 0 - - 0 - 0 - 0 - 0 0
30 AO 50
Displacement (Cm)
60 70 30
3.2.9-6 Plasticity Effects 3.2.9-7 Disp-Force Responses
1 3 5 -
10.
KALIMER[3.2.10-l]S]
o> .s. ^AJ^JL 44^1 ^HU-^Hl ^ ^ 7flM 3J71-1- ^f*l-$i
[3.2.10-3].
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3.2.10-H 3.91
CRDM, IVTM, EM ^ ^ , IHX
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[3.2.10-2]. ^^«J-*j=6.S. 127H5]
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- 1 3 6 -
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370°C A>O]O1]A^ 184.5MPa<y ^
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- 1 4 8 -
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SGACS
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Dump Tank-
Sodium
Catch P a n -
LowerBasemat-
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HAA
PSDRS Stacks
Cask&TransporterPit
EquipVaults
ReactorModule
ReactorSupport
SeismicIsolators
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3.2.10-3
- 1 5 1 -
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3.2.10-5
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- 1 5 3 -
Reactor Head Support Ring
Containment Boundary(fixed seal)
HAA
3.2.10-8
ANSY5 5 . 5 . 1
OCT 31 1999
10:58:10NODAL SOLUTION
STEP=1
SUB =1
TIME=1
SIHT IAVG)
PowerGraphics
AVRES=Mat
DMX =.473E-04
SMH =3 66785
SMX =.127E+08
I1F0RRFORPATHA =.105E+07
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3.2.10-9
- 1 5 4 -
Support Structure - Axisyro case
ABSYS 5.5.1OCT 31 199913:29:39HODAL SOLCTIOHSTEP=1
SUB =1
TME=1SIHT [AVG)PowerGraphics
EFACET=1
AYRES=MatDMX =.001353SHN =.125E+07
SMX =.103E+09A =.6SlEi-07
3.2.10-10
Reactor Support-Head Support ring : Cold deck (t = 30cm)
ANSYS 5.6APR 24 200013:20:26DISPLACEMENTSTEP=1SUB =1TIME=1PowerGraphicsEFACET=1&VRES=MatDMX =.709E-04
DSCA=2809XV =0YV =.866025ZV =.5
*DIST=2.378*XF =2.196*YF =1.799*2F =-.057643Z-BUFFER
3.2.10-11
- 1 5 5 -
Reactor Support-Head Support ring : Cold deck: (t = 30cm)
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ANSYS S.6APR 24 200013:38 :4SELEMENT SOLUTIONSTEP=1SUB =1TIME-1SY (NOAVG)RSYS=1PowerGraphicsEFACET=1DMK - .243E-04SMN =-.866E+07SMX =.B66E+07A =-.770E+07
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hinged support column -rl °11 ^l^l^l Saddle angle plate
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^ £^U1 Hfl ^ ^-711-
3£ E. ^7-1 (support hanger)
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B-B Section View
3.2.11-1
- 1 5 8 -
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A-A Section View
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3.2.11-2
- 1 5 9 -
7}-. Design Description
(1) PURPOSE
The purpose of this document is to provide the design description for
KALIMER (150MWe) reactor internal structures with conceptual
drawings of each internal parts.
(2) SCOPE
The scope of this document includes the description of KALIMER
reactor internal structures except the upper internal structure.
(3) DESIGN DESCRIPTION of KALIMER REACTOR INTERNAL
STRUCTURES
(7» OVERALL DISCRIPTIONS
The KALIMER reactor internal structures are composed of the Core
Support Structure, the Inlet Plenum, the Support Barrel, the RV Liner, the
Baffle Plate, the Separation Plate, the Flow Guide, the EMP Nozzle, the Inlet
Pipe, and the Radiation Shield Structures. Table 3.3.1-1 is the design data of
the KALIMER reactor structures and Fig. 3.3.1-1 shows the elevation of the
reactor internal structures including the containment vessel, reactor vessel,
reactor internal structures, and components. Fig. 3.3.1-2 presents the part
names of the reactor internal structures.
KALIMER reactor internal structures have 3-main functions providing 1)
core support, 2) primary coolant flow path, and 3) component support.
Basically all reactor internal structures are designed to meet these functional
requirements as shown in iso-view drawing of Fig. 3.3.1-3. The design basis
-160-
of KALIMER reactor internal structures is described in next section.
From Fig. 3.3.1-1 and Table 3.3.1-1, KALIMER reactor vessel is 17.0m
height of side cylinder, 7.02m outer diameter, and 0.05m thickness. For the
material data of the reactor internal structures, 304 SS or 316 SS will be
used but these materials are studying to be replaced by 316 LN.
The general seismic design features of KALIMER reactor internal
structures are the horizontally coupled between the fixed structures and the
components at the baffle plate and the separation plate to remove the
disadvantage of a single-stand cantilever structural type as shown in Fig.
3.3.1-2 and Fig. 3.3.1-3.
The annulus type internal structure called as the baffle annulus, which is
composed of the RV liner, the support barrel, the baffle plate, and the
separation plate, is provided to mitigate the large thermal gradients generated
between hot and cold sodium boundaries. The temperature of stagnant sodium
in the baffle annulus is steadily stratified at all operating conditions and will
greatly reduce the thermal stresses of boundary regions of hot and cold
sodium.
Table 3.3.1-2 shows the calculated weights of KALIMER reactor structures
and Table 3.3.1-3 shows the calculated primary sodium volume and weights
contained in reactor vessel.
More detail descriptions of the reactor internal structures for each part are
written in following sections.
(M-) CORE SUPPORT STRUCTURE
The core support structure provides the restraint of the reactor core
assemblies necessary to maintain them in their prescribed geometry during all
modes of reactor operation.
The KLAIMER core support structure is the simple skirt type as shown in
Fig. 3.3.1-2 and Fig. 3.3.1-3. This structure has main function to support the
- 1 6 1 -
core assemblies and the fixed internal structures. This skirt type provides very
simple core support design and fabrication. End parts are welded to the
reactor vessel bottom head and the lower grid plate of the inlet plenum. The
skirt side provides the holes to access for the welding works and to fill the
primary sodium inside the skirt structure.
( 4 ) INLET PLENUM
The inlet plenum is composed of the lower grid plate, the upper grid
plate, the side cylinder, and six (TBD) small diameter structural sleeves. The
upper grid plate is connected to the lower grid plate through the six (TBD)
tie sleeves and the side cylinder that carry the pressure loads tending to
separate the plates. All of the vertical loads from the core assemblies are
carried, through the receptacles to the lower grid plate. The upper grid plate
has a function of accurately positioning the receptacles and also participates in
sealing the annulus around each of the receptacles.
The main functions of the inlet plenum are to receive primary sodium
from 4-inlet pipes and distribute it to the core via the nosepiece receptacles
and structurally to hold the receptacle body supporting the nosepiece of duct
assemblies.
The depth of the inlet plenum is established by the space required for the
inlet pipe nozzles forging welds and the radial flow area necessary to assure
uniform flow distribution to all the core assemblies.
The support structure of the core radiation shields that have functions to
protect the irradiation of the reactor vessel, containment vessel, and to limit
the activation of the impurities in the air flowing the PSDRS is welded to the
outer surface of the lower grid plate of the inlet plenum.
(2}) SUPPORT BARREL
The Support barrel is integrated single cylinder type extending vertically
- 1 6 2 -
upward from its attachment at the upper grid plate of the inlet plenum.
Therefore, no core shroud is provided. At the active core region, support
barrel has a function of core shroud.
The main functions of the support barrel are to provide the support
locations of internal structures such as baffle plate and separation plate and to
guide the flow path of hot sodium coming from core to IHX inlet holes.
Support functions provided by the support barrel are:
- Lateral support of the core former ring
- Lateral and vertical support of the flow guide including EMP nozzle
- Lateral and vertical support of the baffle plate and the separation plate
including the RV liner and the component support structures.
- Support of the IHX shielding materials
(*}) RV LINER
The RV liner is a cylindrical type located 2.5cm inside the reactor vessel
between elevation 210.0cm and 1130.0cm. It is provided with slots at its top
end that under normal operating conditions are always above the hot sodium
level.
The RV liner is designed to protect the reactor vessel from directly
contacting the hot sodium at steady state and transient thermal operating
conditions and form a portion of the pressure boundary between the hot and
the cold sodium regions within the reactor. Therefore, this structure isolates
the reactor vessel from rapid temperature changes in the hot pool sodium that
results from duty cycle events, thus minimizing the thermal loading on vessel,
its attachment to the closure head, and to the containment vessel.
RV liner is one important part consisting of the baffle annulus. The RV
liner provides support for the baffle plate and the separation plate, which
force thermal stratification inside of the baffle annulus and thus minimize heat
transfer between the hot and cold pools.
- 1 6 3 -
(wf) BAFFLE PLATE
The baffle plate is located at the top end of the support barrel and welded
between the RV liner and the support barrel. This has a number of circular
penetrations that allow the IHX and EM pump to pass through while
providing a lateral seismic support for these components. The main function is
to force thermal stratification in the upper volumes of the cold pool and thus
minimize heat transfer between the hot and cold pools.
(A» SEPARATION PLATE
The separation plate is located at the bottom of the RV liner where the
IHX discharge nozzles are attached. The separation plate is welded between
the RV liner and the support barrel to complete the pressure boundary across
the hot and cold pools. This has a number of circular penetrations that allow
the IHX and EM pump to pass through while providing a lateral seismic
support for these components.
( 4 ) FLOW GUIDE
The flow guide is a large diameter cylinder structure, where one end is
fully opened and the other end is covered by the upper plate connected to the
EMP nozzles.
The main function of the flow guide is to direct the cold pool sodium
discharged from the IHX outlet nozzle to the EM pumps with cooling of the
core shield structures installed between the flow guide and the support barrel.
(*r) EMP NOZZLE
There are 4-EMP nozzles corresponding to 4-EM pumps, which has a
function to guide the cold pool sodium to the EM pump intakes after passing
upward from the bottom of the reactor vessel through the annuli between the
- 1 6 4 -
core shield structures. The ends of the EMP nozzles are welded at the
separation plate and the upper plate of the flow guide structure as shown in
Fig. 3.3.1-2 and Fig. 3.3.1-3.
The main function of the EMP nozzle with the flow guide is to enhance
the operation of the PSDRS. These structures assure that sodium drawn by
natural circulation through the EM pumps and into the core will always come
from the lowest elevation and, thus the coolest region within the reactor
vessel.
(*» INLET PIIPE
There are 4-inlet pipes, which are directly connected to the EM pump and
the side cylinder of the inlet plenum. The inlet pipes convey the cold sodium
forced by EM pumps to the inlet plenum.
(?}) CORE FORMER RING
The core restraint ring consists of six core former ring segments and the
core former support ring. The plate segments fit into a rectangular recess in
the inside surface of the ring. When all segments are in place side-by-side,
their inner surface contour matches that of the outer most rows of core
assemblies. The segments are held in the ring by large pins that are welded
to the ring.
The core former ring is supported horizontally and vertically by the
support barrel. Six equally spaced lugs on the outside of the former ring fit
into slots in the top edge of the support barrel. The ring is held in place by
a number of pins installed through the support barrel. Pin motion, after
installation, is prevented by lock welding.
The core former ring fits within the support barrel at its nominal inside
diameter. To provide a close fit of its parts with each other, with the core
assemblies, and the support barrel, the parts of the core restraint hardware
- 1 6 5 -
will be precision machined.
(Ef) RADIATION SHIELD STRUCTURES
The radiation shield structures are provided within the reactor vessel to
limit the activation of secondary sodium flowing through the IHX, to limit the
activation of impurities in the air flowing through the PSDRS, to provide a
radiation environment that accommodates the various neutron flux monitors.
The shielding to provide the irradiation protection for the support barrel of
active core region, if necessary, is required.
Basically the radiation shield structures within the reactor vessel have two
shielding concepts. One is the near-core shielding and the other is the local
shielding.
(4) CONCLUSIONS
This section describes the conceptually designed KALIMER (150MWe)
reactor internal structures. The structural configurations mentioned in this
section are very preliminary, thus required the optimal concept design.
- 1 6 6 -
i t 3.3.1-1. Dimensions of Conceptually Designed KALIMER Reactor
Structures
1.
2.
3.
4.
5.
6.7.
8.
9.
10.
11.
12.
13.
14.
15.
Items
Containment Vessel
Reactor Vessel
RV Liner
Support Barrel
Inlet Plenum
Baffle PlateSeparation Plate
Core Support
Core
Reactor Head
Flow Guide
Inlet Pipe
Core Shield
Former Ring
EMP Nozzle
Outer Dia.
(Cm)
737.0
702.0
687.0
374.0
374.0
687.0687.0
374.0(t)
454.0(b)344.0
737.0
660.0
45.08
248.0
358.0
125.0
Thickness
(Cm)
2.5
5.0
2.5
5.0
15.0
2.510.0
15.0
-
30.0
2.5
2.54
15x3
10.0
2.5
Material
2(l/4)Cr-lMo
316SS
316SS
316SS
304SS
316SS316SS
316SS
-
304SS
304SS
316SS
316SS
316SS
316SS
Remark
(Cm)
Partial-spherical bottom
headGap between RV and CV
= 15.0Gap between RVL and RV
= 2.5Gap between SB and IHX
= 16.925Upper Grid Plate T=10.0
Lower Grid Plate T=15.0Lower Baffle Plate T=2.5
Upper Baffle Plate T=2.5Circular Disk Type
Skirt Type, Height=60
Gap between Core and
SB= 10.0
Circular Disk Type
4 EA
3-Cylinder Type, Gap=3
Height=370
Height=80
* O.D. of IHX (4EA) = 120 cm
* O.D. of EM-Pump (4EA) = 120 cm
* T : Thickness
* t, b : top, bottom
> » On material data, 316SS is studying to be replaced by 316LN.
- 1 6 7 -
3.3.1-2 Weights of KALIMER Reactor Structures
Components
Containment Vessel
Reactor Vessel
Core Support
Inlet Plenum
Support Barrel
RV Liner
Baffle Plate
Separation Plate
Inlet Pipe
Flow Guide
Former Ring
Core Shield Support
Core Shield
EM-Pump Nozzle
Insulation Plates
Weight (tons)
88.51
165.89
10.31
38.72
48.64
39.10
3.02
17.57
19.94
20.20
1.56
0.18
54.00
2.38
85.8
Remarks
Skirt Type
w/o Receptacle
4 EA
4 EA
Plate( 1.6cm) x 22EA
Reactor Head
Rotating Plug
UIS
Total
64.98+15.48
35.61
20.0
731.89
RH + RP Flange
* Used Density = 7800 kg/m3
- 1 6 8 -
S. 3.3.1-3 Calculated Volume
Volume RegionsVolume 1
(RV Bottom Head)Volume 2
(Inlet Plenum)Volume 3
(Outside of Flow Guide)Volume 4
(Inside of Flow Guide)Volume 5
(Core)Volume 6
(Inlet Pipe x 4)Volume 7
(Baffle Zone)Volume 8(IHX x 4)Volume 9
(From Above Core toSB Top )
Volume 10(From SB top to IHX
Cylinder Top)Volume 11
(From IHX CylinderTop to Hot Free
Surface)Volume 12
(From Flow Guide Topto Cold Free Surface)
Volume 13(EM-Pump x 4)
Volume (m^)
34.402
8.230
62.964
58.991
34.000
2.809
95.211
22.727
54.843
38.926
38.814
25.780
19.720
and Weight of Primary Sodium
Weight (tons)
29.76
7.12
54.46
51.03
28.00
2.43
81.14
18.79
45.34
32.18
31.53
22.30
17.06
Remark
Cold
Cold
Cold
ColdHot
Vo*+Vd **x 0.3
Cold
MediumMedium
Vcylinder x 0.8
Hot
Hot
Hot
Cold
ColdVnozzle +Vcylinder
x 0.8
Volume 14(From RV Liner Slot
Top to Hot FreeSurface-Gas)Volume 15(Inert Gas)
Total
17.603
55.036
570.056
-
-
421.14
* Vo : Outside volume of duct assemblies in core region
** Vd : Inside volume of duct assemblies in core region
Hot Sodium Density = 826.77 kg/m3, Medium Sodium Density = 852.25 kg/m3,
Cold Sodium Density = 864.98 kg/m3
- 1 6 9 -
Unit: Cm
165.0
605.0
3.3.1-1 Elevations of Reactor Structures
170-
Internal
Inlet Pipe
Support
Barrel
Separation
Plate
3.3.1-2 Part Names of KALIMER Reactor Internal Structures
- 1 7 1 -
Reactor Head
(RH)
Thermal Insulation
Plate
(TIP)
Baffle Plate
(BP)
Support Barrel
(SB)
Separation Plate
(SP)
Inlet Pipe
(IPP)
Inlet Plenum
(IP)
Reactor Vessel
Liner (RVL)
Reactor Vessel
(RV)
Containment Vessel
(CV)
Upper Internal
Structure (UIS)
Flow Guide
(FG)Radiation Shield
(RS)
Core Support
(CS)
3.3.1-3 KALIMER Reactor Internal Structures
- 1 7 2 -
T-f. Design Requirements
(1) Purpose
The purpose of this document is to provide the preliminary design basis
of KALIMER reactor internal structures.
(2) Scope
The contents of this document include the functional requirements,
structural requirement, and material requirements of KALIMER reactor internal
structures.
(3) Design Requirements of KALIMER Reactor Internal Structures
(71-) Functional Requirements
Provide in-vessel structural support for the core, instrumentation,
Intermediate Heat Exchanger (IHX), EM-pump, in-vessel piping, fuel transfer
equipment, shield material, and in-vessel stored fuel.
- Provide the flow path for primary sodium inside the reactor vessel for both
forced and natural circulation cooling of the core.
- Provide shielding to limit the activation of secondary sodium passing
through the IHX and ambient air passing through the Reactor Vessel
Auxiliary Cooling System (RVACS).
- Limit the irradiation levels within the Head Access Area (HAA) to permit
personnel access during operation.
- Provide the structures to separate hot and cold sodium and minimize the
heat losses between hot and cold plenum.
- Provide the reactor vessel liner to prevent the contact of the hot sodium to
reactor vessel directly.
- Provide the lateral support for the IHX and EM-Pump to reduce the
horizontal seismic responses.
- Provide an Upper Internal Structure (UIS) to support control rod drive
shroud tubes, In-Vessel Transfer Machine (IVTM) guides, and above core
- 1 7 3 -
instrumentation.
Provide the inlet plenum to gather the primary sodium and distribute it to
individual core assemblies appropriately.
Provide the structures or devices to prevent the lift-up of core assemblies
caused by the hydraulic fluid forces.
Provide the core restraints to limit the maximum horizontal core deflection
and acceleration to within the capability of control rod drive and the
structural and functional limits on the core assemblies during duty cycle
events and operational basis and safe shutdown earthquake events.
Limit the maximum relative vertical displacement between core assemblies
and reactor closure head, which hanging the UIS, to minimize unstable
reactivity insertion caused by a change of control rod insertion during design
earthquakes.
Provide for the support and in-vessel storage of (TBD) core fuel
subassemblies during reactor operation at locations accessible to the IVTM
of the reactor refueling system.
A service life of all reactor internal structures shall be 30 years.
*4) Structural Requirements
The reactor internal structures shall be designed to withstand all of
thedesign conditions, which shall cover all service conditions.
Evaluation for structural integrity shall include duty cycle events and design
earthquake events.
The design of the reactor internal structures shall include all fabrication,
handling, transportation, and installation loads.
The loading conditions to be taken into account in designing the reactor
internal structures shall include but not limited to the following : internal
and external pressure, weight of the component and its contents,
superimposed loads from other components, vibration and seismic loads,
174-
reactions at supports, temperature effects, irradiation effects, and the effects
of the sodium environment. Design basis pressure and temperature for the
system is shown in Table 3.3.1-1. These conditions shall be used in
conjunction with the plant duty cycle (Appendix A) to establish the thermal
and mechanical loading conditions for the reactor internal structures.
For the seismic events, the reactor internal structures shall be capable of
withstanding the effects of the Operating Basis Earthquake (OBE) without
loss of capability to remain functional and to withstand the effects of the
Safe Shutdown Earthquake (SSE) without loss of capability to perform their
safety functions.
As a general seismic design basis, the designer shall follow the design
guidelines for seismic isolation
For the design criteria, design and construction of core support structures
and designated reactor internal structures shall conform to the ASME B&PV
Code, Section III, Subsection NG.
For elevated temperature service exceed those to which Tables of ASME
B&PV Code, Section III apply, special rules such as ASME Code Case
N-201-4 may be used.
The reactor internal structures shall be designed as Seismic Category I
structure.
Material Requirements
The effects of environmental conditions such as neutron radiation exposure,
temperature variations, and sodium shall be included in determining the
allowable value of material properties used in the design of system
components.
Material surface in contact with the liquid sodium coolant shall be austenitic
stainless steel unless other material must be used for strength or wear
resistance.
- 1 7 5 -
- Appropriate heat treatments and processes shall be utilized during fabrication
to minimize sensitization of stainless steel components.
(5) Conclusions
This section will provide the requirements for conceptual design and
analysis of KALIMER Reactor Internal Structures.
2.
Internal Structure, UIS)£)
10m
fe
- 1 7 6 -
£L7fl
IDEAS
±S£ 3.7)7} ^ 5 ] # 150MWe
^^^l^rfe- S 3.3.2-H
150MWe
Til ^ ^47 } M-^ife 2^
KALIMER 'S-^-tfl^-^S-i-fil ^ ^ € ¥ 3^ ^ l sjrfl 140cm
£r Inconel
Inconel
ife 95cm7>
- 1 7 7 -
KALIMER
= HOcm
= 2.5cm
= 500cm
= 74cm
= 5.0cm
= 468cm
= HOcm
= 2.5cm
= 92cm
= 10cm
= 10cm
7 ^ o ] ^ io.6m7|-
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= 20.3cm
= 0.635cm
= 515cm
= 11.43cm
1 7 8 -
= 0.305cm
= 454cm
= 13.46cm
= 0.254cm
= 165.7cm
= 12.73cm
= 0.267cm
= 969cm
- 13.46cm
= 0.254cm
= 165.7cm
IDEAS
t ^ sf^^- ^r^JEl- n ^ 3.3.2-14 n ^ 3.3.2-2^
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- 1 7 9 -
S. 3.3.2-1 Dimension of PRISM and KALIMER Upper Internal Structures
Cylinder Outside
Diameter
Thickness of
Cylinder
Distance between
Upper Core and
1) Shroud Tube*
2) UIS
Total Length
PRISM 150
(1986)
132cm/
132cm
2.54cm
5 cm
91.44cm
11.25 m
PRISM 150
(1989)
142cm / 74cm
2.54cm/5.08cm
5 cm
91.44cm
11.76 m
-Upper :
6.02m
-Inter : 4.80m
-Lower :
0.94m
PRISM 300
213cm/ 152cm
2.54cm/5.08cm
-
-
12.85m
-Upper :5.59m
-Inter :6.30m
-Lower :0.66m
KALIMER
(1997)
140cm/140cm
2.5cm
5cm
90cm
10.60m
KALIMER
(1999)
140cm/74cm
2.5cm/5.0cm
5 cm
95cm
10.60m
-Upper :5.00m
-Inter :4.68m
-Lower :0.92m
: In operating condition
3. 3.3.2-2
(0.
(0
*l (m<)
1.15
0.2913
0
152
0
032
1
1697
+ 0.0177)
0408
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6518
9.
2
1.
(1.183
0.
(0.249
13
: (tons)
136
.32
321
+ 0.138)
318
+ 0.069)
.097
- 1 8 0 -
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ij
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^ ^ - Fit table, s f l < £ 5 - ^ Table, ^ 7 ^ ^
- 1 8 2 -
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KALIMERi tfl^ of til xM^7]&£.3,*\ 3.4-^^7.} 2:A}(Fast
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4-
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Grid & = 0.039 DPA < QAA^ = 4.1 DPA
- 1 8 3 -
3.3.3-1 Iso-View of Core Radiation Shield Structure
3.3.3-2 Dimension of Core Radiation Shield Structure
- 1 8 4 -
7>.
^^[3.4.1-3].
^ f^f-S} 7l7l«H^] ^2:6fl tfl Sfl
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71
6m
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l - i ^ ^^1 ^ } ^ til^-ol 20% ^ E f ^-^-si-51^-.
- 1 8 6 -
S. 3.4.1-1 KALIMER i i i
Part Name
RV Support Wall
SG Support/Protection Wall
Working Floor(HAA)RV Support Floor
SG Bottom FloorSodium Tank Room FloorVertical Inner WallStacks (4)Center RoofUpper Part
Middle Part Walls
Lower Part WallsBasemat (Upper/Lower)
Isolators SystemTotal (Except Isolators)
Weight
(x 1,000 Ton)2.336
0.35/ 2.3
2.2161.70
1.111.551.01
0.290.962.72
8.08
19.067.3/ 7.3
1.951.23
Wall or Floor
Thickness (m)1.5
1.0/0.7
0.70.7- 1.0
0.7
0.50.70.1
0.50.5
0.5 0.9
0.7 0.91.5/ 1.5
(Number : 182)
Key Dimension [Section
Area (m2) and/or Height(m)lID/OD=9.0/12.0, H=19.3
12.0 x 7.0 /13.4 x7.7,H=25.0
37.20 x 19.122.65 x 19.122.65 x 7.00
22.65 x 7.0, H=5.8H=13.3
2.2 x 2.2, H=36
39.0 x 20.9H=6.50
H=19.0
H=30.8
52.0 x39.0
Seismic Isolation Bearing
3.4.1-1 KALIMER
- 1 8 7 -
Unit: m
A A
39
A
R t t ^ -
3.4.1-2 KALIMER
400 cm
63 cm,
120 en
_ 9 5 c m ^ _, 210 cm _
3.4.1-3
- 1 8 8 -
3.4.1-4 3L7] KALIMER IDEAS
3.4.1-5 KALIMER IDEAS
- 1 8 9 -
1 r
i
r - r
1
-\
m m m m
i
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|
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"1
i : :|
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|
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3.4.1-6 7fl KALIMER IDEAS
- 1 9 0 -
2.
2007]]
514.
KALIMER
^ ^ 1 ^ ^ 1 9 9 4 ^ ^ 1 9 9 9 ^ 4 4
^°} 9X°-V][3.4.2-1,2,3], £ * ! €
e-^ *11^# ^ r s 3 ^ 4 514P.4.2-4].
^ KALIMER € ^ > 5 . ^ # ^ ^ 1 ^ 1 ^
|sfl -f^d KALIMER ^ 4
: ANSYS
1- 4 ^ - ^ S . KALIMER
4-
^o] 26kgf/cm2 (370 psi), ^ ^^1^4^(fh)7> 0.5 Hz,
^ 21 Hz, ^ ^ ^ ^ ^ T f l i r 300% £1Jt-(]Efe 538 mrn^]
- 1 9 1 -
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1 9 3 -
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3.4.2-4O1] 4 E } \ + tif4 ^-o] ANSYS
4 A^^] ^ 4 4 ^ 3 2 0 ^ ^ 4 ^ 4 ^ ^ ^ 4 ^ ^ 3,166 KN/m,
5584,824 KN/m^-S. 4^4[3.4.2-2].
2400 kg/m3, i 4 ^ y l ^ 0.2, ^^Tfl^fe- 21.5 GPaS.
4 ^4 441: 44
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^ T f l
ol
- 1 9 6 -
i t 3.4.2-1 Specification and Design Targets for Lead Laminated
Rubber Bearings
Prototype LRB 1/8 Scale LLRB
Design Vertical Load (Ton)
Effective OD(cm) / ID(cm)
Rubber Thick.(mm)Layers
Steel Thick.(mm) x Layers
Primary Shape Factor(D/4tr)
Secondary Shape Factor(D/ntr)
Vertical Stiffhess(kgf/cm)
Horizontal Stiffness (kgf/cm)
Damping Coefficient(%)
Max. Shear Strain(%)
294
120/4
278(9.629)
3.2 x 28
31.25
4.31
51.6xlO5
2,846 (5,692)**
12
300
4.6
15/(2.7,3.7,4.8)*
34.8(1.229)
1.8 x 28
31.25
4.31
6.4xlO5
356 (711.4)**
12
300
* Inner Diameter of Lead Rubber Bearing and Diameter of Lead Plug
** Horizontal Stifmess at Isolation Frequency of 0.5 Hz (0.7Hz)
3. 3.4.2-2 KALIMER
AREA
NODE
ELEMENT
Number
1-120
121-134
135-170
1-3058
4001- 4238
1-104
105-399
400-3439
3901-3916
4001-4221
4301-5082
Description7-^.g- S^T^-VS D.I A,\1 e o \1 —i ZK. o
SG £LM
7d-i: ^ ^ ^
QA^ £ # %BL «J.S.i (STIF4)
^ ^ 7 l 2 : ^ S . (SHELL63)
QAS- ?i-i- (SHELL63)
%7\S. ? ^ t ^f^^^ (MASS21)•s}^-7} 2 n f l ^ %^ «1J3L4: (STF4)
^[^)sfl<H^(COMBIN14)
- 1 9 7 -
3.4.2-3 KALIMER
MODE
1
2
3
FREQUENCY
0.480
0.510
0.528
EFFECTIVE
MASS (X)
0.341E+07
0.620E+07
0.485E+08
EFFECTIVE
MASS (Y)
0.121E+08
0.439E+08
0.209E+07
EFFECTIVE
MASS (Z)
Small
Small
Small
^ 3.4.2-1
1 16 J i t 2 i i16
3.4.2-3
- 1 9 8 -
3.4.2-4
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31
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tflt!:
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0.9m ^ 5 . £lH^ HflU 5)uH ^ ^ t -
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=1711
4.52
L
12
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[3.4.3-4]. tijl^^^- J7OJ-O] 13071
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44.9 MPa
A
- 2 0 3 -
S. 3.4.3-1
1
2
3
4
5
6
7
8
9
10
11
12
13
14
15
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300
# £
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320
Aj-.Q.
AV 0
^ • &
(kg/
cm2)
7
5
5
5
130
160
7
7
3
3
20
7
10
15
8
8
°3 ^ 7~1 •§-
R/B 21 «-
R/B 21 r
R/B M/B
R/B M/B
R/B T/B
R/B T/B
R/B ^l-f
R/B T/B
R/B M/B
R/B 21 n1
R/B T/B
R/B M/B
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R/B M/B
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21 *
(inch)
18
2
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3.4.3-2
Design Variables
(Support Location)
Frequency LimitStress Limit
DV1 (m)DV2 (m)
DV3 (m)DV4 (m)
DV5 (m)Freql (Hz)
(MPa)
Lower Bound12
2
16
54
Upper Bound216
15
24
146
154(480 °C)
Initial Values1
2
2
16
5
3.4.3-1 KALIMER
Isolated Part
OD = 45.7cmThick = 4.52cm
(SCH160)
3.4.3-2 ^
- 2 0 5 -
3.4.3-3
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Service level A,
Service level C, D<>11 ^ § > ^
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S. 3.5.1-1 SS316#, 2.25Cr-lMo7Di-,
(a) SS3167J-
Temp
CO
-17.837.7893.33148.9204.4260
315.6371.1426.7482.2537.8593.3648.9704.4760
815.6
Thermal
Expansion
(m/m/°C)1.4753E-051.5270E-051.5749E-051.6190E-051.6595E-051.6968E-051.7308E-051.7619E-051.7902E-051.8159E-051.8393E-051.8604E-051.8795E-051.8968E-051.9125E-051.9268E-05
Density
(kg/m3)
7861.12
778077577735
Thermal
Conductivity
k(J/sec.m.°C)12.6999713.6557314.5956815.5196216.4273317.3186418.1933419.0512219.8921120.7157821.5220622.3107423.0816223.834524.5691925.28549
Poissons
Ratio,
0.27
0.304
Youngs
Modulus
(GPa)
163
156.65
Specific Heat
c(J/Kg.°C)
448.8464472.3338492.4997509.7058524.3136536.6844547.1799556.1616563.9909571.0294577.6385584.1798591.0148598.505
607.0118616.8969
(b) 2.25Cr-lMo#
Temp
CC)
21.1137.7893.33148.9204.4260
315.6371.1426.7482.2537.8593.3648.9
Thermal
Expansion
(m/m/°C)1.1610E-051.1700E-051.2060E-051.2420E-051.2726E-051.3014E-051.3284E-051.3500E-051.3716E-051.3914E-051.4076E-051.4220E-051.4346E-05
Density
(kg/m3)
Thermal
Conductivity
k(J/sec.m.°C)36.1847336.350936.870237.2233237.2233237.0363836.5170835.831634.9591834.1075333.0689432.0303431.15792
Poissons
Ratio,
0.265
0.304
Youngs
Modulus
(GPa)
156.65
Specific Heat
c(J/Kg.°C)
704.4760
815.6
0.0000E+000.0000E+000.0000E+00
29.766227.0035326.48423 0
- 2 4 1 -
(c) -T2T
Temp
(°C)
-17.837.7893.33148.9204.4260
315.6371.1426.7482.2537.8593.3648.9704.4760
815.6
Thermal
Expansion
(m/m/°C)
Density
(kg/m3)
954.13941.394928.658915.923903.187890.452877.716864.981852.245839.509826.774814.038801.303788.567775.832763.096
Thermal Conductivity
k(J/sec.m.°C)
94.0138290.7992287.6570284.5872481.5898778.6649175.8123673.0322270.3245
67.6891865.1262862.6357860.2177
57.8720355.5987753.39792
Specific Heat
c (J/Kg.TC)
1447.446
1415.71386.8081360.7711337.5891317.2621299.7891285.1711273.4071264.4991258.4451255.2451254.9011257.4111262.7761270.995
S. 3.5.1-2 (PSDRS
RV ^?fl
2.5cm
5cm
10cm
15cm
(MPa)
104.7
117.2
134.1
147.6
(MPa)
129.7
146.3
169.9
187.3
• § - 3 # : E
(MPa)
127.4
135.1
164.0
183.7
^ 7 f ^ ( % )
(2.5cm
7^-f^ o]5L)
0
6
29
44
- 2 4 2 -
g. 3.5.1-3 PSDRS)
RV ^
2.5cm
5cm
10cm
15cm
^ «
(MPa)
128.0
143.7
162.1
175.2
(MPa)
161.4
180.4
208.4
229.0
^ «(MPa)
157.3
165.7
201.2
224.6
(2.5cm
0
5
28
43
3. 3.5.1-4
Casel
Case 2
Case 3
Case 4
^ J - t -S-^ ay(MPa)
152
152.2
82.6
86.8
-152
-152.1
-73
-77.5
-136
-135.6
-95.4
-94.5
134
134.4
95.7
94.8
48.5
48.5
143
128
-58.1
-58.1
-144
-128
• ^ ^ J - * -S-^ az(MPa)
^^ -e^^109
109.3
36.3
41.9
24.5
24.5
-24
-22.3
-112
-111.8
-81.5
-72.7
-30
-30
37.7
37.4
(MPa)
173
173
176
162
- 2 4 3 -
S. 3.5.1-5 KALIMER £.7] 7]
ComponentsContainment Vessel
Reactor VesselCore SupportInlet Plenum
Support BarrelRV Liner
Baffle PlateSeparation Plate
Inlet PipeFlow GuideFormer Ring
Core Shield SupportCore Shield
EM-Pump NozzleInsulation Plates
Reactor HeadRotating Plug
UISSodium
Core
Weight (tons)88.51165.8910.3138.7248.6439.103.0217.5719.9420.201.560.1854.002.3885.8
64.98+15.4835.6120.0421175
Remarks
Skirt Typew/o Receptacle
4 EA
4 EAPlated.6cm) x 22EA
RH + RP Flange
3.5.1-6 316SS#^ , Smt(MPa) (Subsection NH)
(°C)426.7
454.4
482.2
510.0
537.8
565.6
593.3
621.1
648.9
676.7
704.4
732.2
760.0
787.8
lh
109.6
108.3J
107.6
106.9
106.2
104.1
102.0
101.4
100.7
97.9
95.2
88.3
77.9
66.9
lOh
109.6
108.3
107.6
106.9
106.2
104.1
102.0
101.4
100.7
97.9
88.3
71.0
56.5
44.1
30h
109.6
108.3
107.6
106.9
106.2
104.1
102.0
101.4
100.7
93.1
75.2
59.3
46.2
35.2
lOOh
109.6
108.3
107.6
106.9
106.2
104.1
102.0
101.4
97.9
79.3
62.7
48.3
37.2
28.3
300h
109.6
108.3
107.6
106.9
106.2
104.1
102.0
101.4
85.5
67.6
51.7
40.7
31.0
23.4
lOOOh
109.6
108.3
107.6
106.9
106.2
104.1
102.0
97.9
73.1
57.2
44.1
34.5
26.2
20.0
3000h
109.6
108.3
107.6
106.9
106.2
104.1
102.0
89.6
64.8
50.3
38.6
29.0
21.4
15.2
lOOOOh
109.6
108.3
107.6
106.9
106.2
104.1
95.8
75.2
57.2
43.4
32.4
23.4
17.2
11.7
30000h
109.6
108.3
107.6
106.9
106.2
102.7
79.3
61.4
47.6
37.2
26.9
19.3
13.8
9.7
lxlO5h
109.6
108.3
107.6
106.9
106.2
86.2
65.5
49.6
37.9
29.0
21.4
14.5
10.3
6.9
3xl05h
109.6
108.3
107.6
106.9
96.5
73.8
53.8
40.7
31.0
22.8
17.2
12.4
8.36.2
815.6] 53.8| 33.8 26.9 22. l| 17.9| 14.5 11.0| 8.3| 6.2 4.5 3.4
- 2 4 4 -
0 (-8.0)
30.0(-7.7)
285(-5.6)
500(-3.8)
1200(2.2)
1290(2.9)
1681(6.3)
1771(7.0)
1846(7.7)
1910(8.0)
Unit : Cm
165C-6.6)
605(-2.8)
1234(2.5)
1700(6.4)
1885(6.4)
3.5.1-1
- 2 4 5 -
Insulation Support Ring
Containment dometemperature ~40C
\
Reactor Head
-230 C Normal
HeInsulationPlates (22)
Hot Pool Sodium
-530C
Ar
RV Liner
Containment Boundary(fixed seal)
RV CV
PSDRSAir out temp- 100C
Air In temp - 40C
Collector cylinder
3.5.1-2
-246-
250cm ArGas
RVACS Ai r9 0 ° C
3.5.1-3
- 2 4 7 -
3.5.1-4
Thermal analysis of SB, Liner, RV, CV, SP, EP
iiNSi'S 5.5.1MAR 13 199913:12:18NODAL SOLUTION
SUB =1 :TIME=1TEMP " (iVG)RSYS-01
Powe rGraph i osEFACET-1AVRES=Mat :'SMM =91 442SMK =403.388
-2S2.076=316.736
3.5.1-5
- 2 4 8 -
3.5.1-6
3.5.1-7
- 2 4 9 -
3.5.1-8
1.40E+008
1.20E+008
^ 1.00E+008
£• 8.00E+007cB£ 6.00E+007
K 4.00E+007
2.00E+007
O.OOE+000_1_
Inner (Uniform)Outer (Uniform)Inner (Variable)Outer (Variable)
_i L.
4 6
Distance
10 12
3.5.1-9
- 2 5 0 -
3.5.1-10
3.5.1-11
- 2 5 1 -
RV upper
•
part
•I
thermal stress
i\B 4>y-0.8m
-•> Sm
1
ANSYS 5.6APR 15 200011:25:05NODAL SOLUTIONSTEP=1SUB =1TIME-1SINT (AVG)PowerGraphicsEFACET=1AVRES=MatDMX =.037102SMN =342058SMX =.173E+09_ _ 342058
.195E+08
.387E+08
.579E+08
.771E+08
.962E+08
.115E+09
.135E+09
.154E+09
.173E+09
cm
ED
3.5.1-12 FEM
RV upper part thermal stres s
ANSYSAPR 1511:28:NODALSTEP=1SUB =1TIME=1SYRSYS=O
5.62000
23SOLUTION
(AVG)
PowerGraphicsEFACETAVRES=DMX =.SMN =-SMX =.A
= 1Mat037102.152E+09152E+09.135E+09
=.135E+D9
3.5.1-13 -§- £3. (Case 1)
-252-
RV upper part thermal stress
ANSYS 5.6APR 15 200011:29:42NODAL SOLUTIONSTEP=1SUB =1TIME=1SZ (AVG)RS2S=0PowerGraphicsEFACET=1AVRES=MatDMK =.037102SMN =-.112E+09SMX =.109E+09A =-.99SE+08
=.370E+03
3.5.1-14 (Case 1)
AKSVS 5.6APR 15 200015:07:51 ' . '•"'.*:. MODAL SOLUTION•'.
S T E P - I ' V : :•.• •'•:
S U B = 1 • . - • • • •
TIME=1 •: SIIJT ; (AVG).:
Power-Graph i c s : .E F A C E T = 1 • • • • • • ,. . • -
AVRES=Mat . •• .DMK = .03235 . ,SMW; =10699.0SfK =.162E+09,—-, 1069901 ' .181E+08'
.361E+0B, .54QE+08;•.72DE+08.900E+08.1OSE+09..126E+09.144E+09
U^-J .162E+09
RV upper part thermal stres
3.5.1-15 (Case 4)
-25 3 -
o
5 0 0
4 5 0
4 0 0
3 5 0
3 0 0
2 5 0
-X RV 2|° j (COMMIX)
- 0 RV Ml ni (COMMIX)
10
^eh si-el-
1 5 20
3.5.1-16 (COMMIX
500.00
450.00
400.00
OLh1 350.000|J
300.00
250.00
1
VInnerOuter
J0.00 5.00 10.00 15.00 20.00
3.5.1-17
- 2 5 4 -
RV with Ellipsoidal shaped bottom head
3.5.1-18
5F5JBoSo
0.00 20.00
3.5.1-19 1-51-g-71
-255-
3.5.1-20
1.80E+08
1.60E+08
1.40E+08
„ 1 .20E+08CO
£f 1.00E+08
^ 8.00E+07n5T
6.00E+07
4.00E+07
2.00E+07
O.OOE+00
0.00
-SINT-in
-SINT-out
5.00 10.00 15.00 20.00
zz.e] 3.5.1-21
- 2 5 6 -
a.
1.50E+08
1 .OOE+08
5.OOE+07
0. OOE+00
O.(J-5.OOE+07
-1. OOE+08
-1.50E+08
10.00 15.00 20.
•SY-in
•SY-out
DO
3.5.1-22
(Pa)
fir
KhofJ
1
1
5
0
- 5
- 1
.50E+08
.OOE+08
.OOE+07
. OOE+00
(
.OOE+07
.OOE+08
.50E+08
15.00
•SZ-in
- SZ-out
20.00
3.5.1-23
-257-
8.00E+06
6.00E+06
4.00E+06
'ab 2.00E+06srolojO O.OOE+OO
jo o.q
5° -2.00E+06
-4.00E+06
-6.00E+06
-8.00E+06
10.00 15.00 20.
-SX-in
• SX-out
3.5.1-24
Chimney(4 Places)
24m
Head and Support Ring(OD7.97m)
3.5.1-25 KALIMER PSDRS
-258 -
600 Thot. p|. ex
1000.0E+00 2.0E+04 4.0E+04 6.0E+04 8.0E+04 1.0E+05 1.2E+05
Time [sec]
3.5.1-26 PSDRS
600
500
3.4 3.6 3.8
3.5.1-27 PSDRS
700
600
5 0°400
300
200
CV max
RV max
Core out
_J 1 I I I U_J 1 i L_
20 40 60 80 100
3.5.1-28 PSDRS -ft3.7}- 75%
0
CV max
RV max
Core out
1 0 0
3.5.1-29 PSDRS7} 12^71 25%
- 2 6 0 -
120.0
(0CL
?5T
1 " " " I ' " " " I ' ' " " " I1.0 10.0 100.0 1000.0 10000.0100000. 100000
0 0.0
454.4C482.2C510.0C537.8C
•-565.6C+-593.3C
621.1C«*_648.9C•_676.7C._704.4C.—732.2C
760.0C. 787.8C
;; 815.6C
3.5.1-30 316SS t, Subsection NH)
8008509009501000105011001150120012501300135014001450
OJ» 10 © ~ - 10"
MINIMUM TIME TO RUPTURE, HR10
3.5.1-31 316SS -§-^ (Subsection NH)
- 2 6 1 -
MATERIAL - 316 SS
TEMPERATURE - 1200 F
0.2 0.4 0.6 0.8 1.0 1.2 1 4 1.6 1.8 2.0 2.2
3.5.1-32
- 2 6 2 -
s HOT TEC
= = C 5 1 HOUR
MATERIAL -316SSTEMPERATURE - 1300 F
1.0 1.2 1
STRAIN. %
4 1.6 1.8 2.0 2.2
3.5.1-33 316SS#^ 704 "
- 2 6 3 -
2.
KALIMER %7\S-%-7] ^ ^Jf^2:l-^ 7 2 4 4 ^ ^7}i 5 ^ 4 4
ASCE 4-86[3.5.2-l]
o]4 . ANSYS 5-S.ZL^[3.5.2-2]^
5flA^ ^S^o1 E - f E *(H ^ ^ } * ^ ^ t >
[3.5.2-3].
S-^^- ANSYS S-S-ZL^^r ^-^ ^ ^ ^ ^ lfloflA-1
^ IHX ^ EMP ^S- i - i - i^-§|-fe KALIMER
OJ ANSYSt-
r 444 r ^ ^ 4^ 4^1- 1- lS. 4 r 344
FLUID80 - M71 ^*V i i i ^ *irj\$-R z=0 J±4 *>2fl°fl # ^ f l ^ i ^^7\^S-~ z=0
- 2 6 4 -
IHX B-^17]--B- fe 4 4 4 IHX
7]
2.23m, 0.7m<?]
3.5.2-H el
0.58 0.52 HzS- ^ ^
3.5.2-H]
4-
-§-4
443.5.2-3i
4= S3s
9m
IHX ^ EMP
3.5.2-2oll
- 2 6 5 -
ing)
ofl^
IHX
7]- 0.4
3.5.2-4,541
EMP
O . ^ o] nfl
^ 0.3
3.5.2-1
1
2
3
l 1] ^ Ai sJ rJ ^H] *T g tlL-l i:
(d/D=O.O)
0.576
1.058
1.309
1.00
0.29
0.15
0
1
1
(d/D=0.25)
*4=(H 2 )
.525
.024
.298
* ^ *
0.79
1.00
0.34
- 2 6 6 -
3. 3.5.2-2
l
2
MODE
1
2
3
4
1
2
3
4
FREQUENCY
0.304730
0.506135
0.536354
0.632131
0.306638
0.502118
0.545851
0.629007
PARTIC. FACTOR
3.2816
1.9758
1.8644
1.5820
3.2612
1.9916
1.8320
1.5898
EFFECTIVE MASS
5702.42
23.0506
33.1172
4.81433
5616.16
13.0160
18.9814
6.73957
Frequency vs D/d ratios
3 4
D/d ratio
3.5.2-1
- 2 6 7 -
3.5.2-2
3.5.2-3
- 2 6 8 -
3.5.2-4 H tfltt •a
- 2 6 9 -
3.5.2-5
- 2 7 0 -
3.
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4 ^-g-^ol 7-1S]
10.6cm
°)\ <ii&.*$^°) ^ ^ ^ ^ r °av ^ & 4 . ^ - § - ^ i tfl^ ASME B&PV Code,
Section III, Subsection NB[8]^ Q$] ^\^^k^ 3SmA£ 333MPa<ycll
- 2 7 6 -
S. 3.5.3-1
(cm)
0.74
1.9
136.1
1.9
1.11
(MPa)
331
527
3130
72.5
210
(MPa)
-187
846
-287
171
-2350
2550
32
72
-128
98
Sx(MPa)
-121
149
-321
387
-2860
3060
-1
35
-15
91
Sy(MPa)-185
245
-268
320
-1760
1800
-1
45
-49
115
3.5.3-2
^£€
#^
(cm)
10.6
10.6
10.7
10.6
10.6
(MPa)
201
207
216
196
201
(MPa)
-201
196
-204
197
-197
198
-196
195
-199
198
Sx(MPa)
-196
195
-179
177
-201
199
-196
195
-196
194
Sy(MPa)
-199
199
-204
203
-197
196
-196
195
-198
197
- 2 7 7 -
2l3(cnO
737(3.1)
702(3.(687(2,!
0 (-8.0)
30.0(-7.7) •
285(-5.6)
500(-3.8)
1200(2.2)-
1290(2.9)
1681(6.3) •
1771(7.0)
1846(7.7)
1910(8.0)
U n i t : Cm
•165(-6.6)
. 605(-2.8)
• 1234(2.5)
3.5.3-1
- 2 7 8 -
L
ANSIS 5.5.1HAS IS 1SSJli.ii :'•(•PLOT .VO. I
SUS =1
£»« -,5C7-!W
be-ccon. h^^tt Cparcu^S
3.5.3-2
AJT5VS S.
tuyr so.N'ODAL S•J
SO3 - 1
any. =.551i!*C?
3.5.3-3
- 2 7 9 -
ANSVS i . 5 .1MAE i J "i3t>t>! 7 : 0 2 ; 4 2PLOT NO- I
CT3 - :
22 i
SV iwtto.- head rplac ehapei
3.5.3-4
i .rays 5 .5 .1HAR 13 155S
S72P-1SU3 -1
EKX =.3C19C3Slfl; -,333EiC'P,5X5: - . ?25E^CS
H - .556E.ee
3.5.3-5
- 2 8 0 -
RV fccttcxn h t a d I £ l l i i
3.5.3-6
STO 5 . 5 . 1H.\z 15 135317=03:3«
SU3 - 1
SINT (AVGI
BKX =SKN -
tins -
4.
fe KALIMERS]
^-[3.5.4-1 ~3]t- ^ § H ^.a . 7)7] *\ 3.7]
KALIMER ^
Sfl IHX-SG5]
7l7]
afl^S
Chaboche
IHX
A}
cfl
- 2 8 1 -
^[3.5.4-4,5]
^r 10002,
KALIMER IHTS fl£ fl^^l fll fl4 ^
KALIMER IHTS «fl#
-id
7\. KALIMER
(1) 7]7l ^
3.2.4-3^ ^ 7 f l ^ IHTS
^
(2)
(71-) Sfl^j .2..gig
ZL^ 3.2.4-34 IHTS
SG 4 ° 1 ^ f ^a^e l l - 8m, 12m, 16m ^ 11.5mS.
-fe- ^3.2.4-24
tifl^^.^w-Ei Tee
20"SCH40^
7] ^*fl hanger 4 4 ^ S # ^ r ^3. ^^}%v}. KALMER IHTS ufl
^ l ^ r 77fl51 hanger 4
fe 316 ^
- 2 8 2 -
£ 30451
ABAQUS[3.5.4-6] 3.5.4-H]
PIPE31
^yM(co-axial piping)
IHTS ^*b ANSYS sfl^S-l^r H& 3.5.4-2^
^ 4 ^ ^ ANSYS[3.5.4-7] sfl^H^fe ^
(3)
^ ^ 3.5.4-34
8m, 12m, 16m, 1
Mises -g-sj ^ slcfl
6.89 MPaS. DFBR2J- MDP^]
DFBRKALIMER4
Von Mises ^?l°]
^7] - s] ^ t f . Mises -g-
Tee ^ ^ - ^ f ^ l ^ SG ^
29mm«1 ^ ^ . ^
14
(4)
KALIMER IHTS
LBB[3.5.4-8] ^ ^
- 2 8 3 -
BDS[3.5.4-10] ^ 3.^^
tflSfl^
RC-3600[3.5.4-13]
ASME Section III NH-3600[3.5.4-9]2f
RCC-MR RB-3600[3.5.4-ll] *]%<>] *1H £] <H 9X
ASME Code Case N-253-6[3.5.4-12]4 RCC-MR
- ^ 014. z
Tr KALIMER IHTS -# ^ Sfl
KALIMER IHTS
4s} . IHTS
j£ 3.5.4-1 Case study results by inelastic study
\
Mises
(MPa)
Max Disp
(mm)
DFBR
26.7
25.6
MDP
51.0
7.28
KALIMER
Case
I*
73.5
18.7
Case
II*
50.0
22.8
Case
III*
23.7
25.3
Case
IV**
21.4
19.1
Casey***
22.2
40.0
Caseyj****
8.69
29
IHX-SG 8m, ** : 12m, *** : 16m, **** : 11.5m
- 2 8 4 -
S. 3.5.4-2 The evaluation results of KALIMER IHTS piping
per design codes
events M3£ or
equation
ASME NH-3200
ASME CC
N-253
BDS
RCC-MR
RC-3600
Design Condition
Level A,B
Level DDesign Condition
Level A,B
Design Condition
Level A,B
Design Condition
Level A,B
Eqs. (1), (2)
Eqs. (3),(4),(5)
Eq.(12)Eq. (8)
Eqs. (9),(10),(ll)
Eqs. (5.2.1), (5.2.2)
Eqs. (5.2.3),(5.2.4)
RC 3651.1.1
RC 3651.2
Yes
Yes
YesYes
Yes
Yes
Yes
Yes
Yes
l*r «
2*} H M
2x> BM
3.5.4-1 ABAQUS model for inelastic analysis
- 2 8 5 -
3.5.4-2 ANSYS model for elastic analysis
T(°C)'
530
365
50 1000 t(sec)
3.5.4-3 Thermal transients
- 2 8 6 -
SECTION POINT 1HISES VALUE
•4.28E-O1•1.09EKW•1.74E>00*2.40E>0O•3.06E-00•3.71E>00•4.37E-0O»5.O3E»OO•5.69EMW
•7.00E»00-*8 .69E«»
3.5.4-4 Distribution of Von Mises stress
Ul
XMIN .OOQE+00XMAX 1 . 0 0 0 E + 0 0
IBM -2.930E+D1
JTMAX 3.877E-01
D
SPLACEMCi
NI
-
1
0 .
- 5 .
- 1 0 .
- I S .
-20 .
-25 .
- 3 Q .
— 1
-
-
-
\\
/
/
i
/
/
/
i
/ -
/ _
-
-
i
. 0 .2 .4 .6
DISTANCE
1 .0
3.5.4-5 Distribution of displacement, ul for Tee-SG span
-287 -
5.
7}.
(l) >H ^
<sUfl ^ifloflx-] 711^:^*1 ^ a f l ^ S . * ? ! KALIMER
530°C5L
nf l^ i [3.5.5-2]
KALIMER €^fS-^-
^ ^ SX i 71 (Seismic isolation
design)[3.5.5-3]7l- ^ -
KALIMER
ASME 2 E f
427°C(800°F )°l5-]-<y 7 ] ^ ^ ^ ^ - i ^ ^ l ^ ASME Code Section III,
Subsection NG7> Aj-g-sH^ a ^ ] ^ ^ J l ^ i ^ i i ^^fl>Hfe ^ 3 . 1 ^
H S 7-11 A] Z\JL 01^ ASME Code Case N-201-4[3.5.5-4]£|
^ 014. ^ iLJLA^jA^ KALIMER
Level
- 2 8 8 -
(2) KALIMER
! ^ 3.% 3.3.1-35]
43^1^11-(Core Support), -fi-^^(Inlet Plenum),
iflJf^]^]^-(Support Barrel), #*}£,-%• 7] eHL1(RV Liner),
Plate), £ ^(Separation Plate), n e | a l -fi-^^tfll^Flow Guide) S
KALIMER ^ l ^ l - S ^ J f ^ a l - ^ ZL^ 3.3.1-2^
^:7] (Primary Intermediate Heat Exchanger)^ 27fl5]
(Electro Magnetic Pump)S.
» 7-1
KALIMER
- 2 8 9 -
3, KALIMER ^ ^ } S
fuel) J M
=L7fl
316
(3)
3.5.5-1^ -^-^
^ ANSYS 5.5
SOILD701: 4-g-^jL ^ - § - ^ ^ ^ ^ 1 ^ SOLID45 i i f
7H*>
1/4 -H-^riLi « f l ^ £ l 1 M-E}M- Sl^ ^51^2} ^ e l ^ i ^ 2}-Z]- I7fl
5] 7 l.2m
- 2 9 0 -
51 fe PSDRS^r
PSDRSS -^-£51^ cfl -(Convection),
(Conduction),
n ^ 3.5.5-2^ <!-&--§• ^-§-*ll^SH*l COMMIX 2
KALIMER
temperature)#
3 .
- 2 9 1 -
3 . 5 . 5 - 3 ^ 1 * } 3 | | * i ] * *}•%•*}*} ^^r
n 4.
3.5.5-5^-
3.5.5-10^ o] s . tfl
3.5.5-74
7]7]
3.5.5-8^
3.5.5-9
24
7]7l -g-^o] 3.5.5-10^
- 2 9 2 -
3.5.5-1^ 4 ^S^-^ofl tfl^H ASME ^ . S H ^ i *H S}^ -g-sj
(4) ASME
^ ASME Code Section III, Division 1 NG
^ 427°C (800°F) o]
ASME Code Section II, Part D<*fl*| ^ l ^
11^^ tfl^ Section III^ i ^ ^ l ^ l
ASME ^^Sl i^-1 §«] ^ i XI4- 4 5 M Section II, Part
A ^ Subsection NG l tfl -o^ ASME Code Case N-201-4S] Part A ^fe
Part B£ ^ ^ / ^ ^ s l fl-^1:^- ^-g-^ ^ S i £ ^ §>i Si4-
ASME Code Case N-201-4^ Part AS]- Part B£ T 1 - ^ ^ ^ Sl-^1^
Subsection NG j ^^^d °]Ao1- ^ ^ ^ £ ° l l ^-§-"§: ^ - 2 - 5 . Subsection
NG1- ^^*>7]i4 ^A*F ^ ^ l - ^ i i l^rS]^ S14- Part A ^ 3 ^ 4
Stress-ruptureJl f l- ^ ^ 7>^^r ^^]^] £ ^ 4 * 1 Subsection NG# ^ - ^ ^
^o]^]n> Appendix XLX$\ Time-at-temperature limits^ tfl^ Tf- go] s^ - j i
fl £-ofl 3 ^ 3 } Stress-ruptured ^ -§1 JlBl^t 7A% -S-
11 Part B ^ 3 . ^ 4 Stress-rupture JL3)-# ^ ^*1 3 ^
Subsection NGi cH«} fl-^-t^ ^ ^ i ^ t ^ 3 H 4- Part A
- 2 9 3 -
$] Appendix XIX5] Time-at-temperature limits^1 tfl tb
£ Part A cfl Aloj] p ^ B # 4 - § - ^ ^ $14-
£ ^ H H ^ 3 ^ 4 Stress-rupture i 4 # : M ^ Part
3-§-§}-JIT-} *>4. sfl^oil 7 l s ^ -i3]*r-§-(Design Acceptability)
Code NG(<>1S> NG)4 Code Case N-201-4(^l •&]- N-201)7V ^ s .
NGofl^fe ^ # € -§-^^°l ASME Section II, Part D, Subpart
2A, 2B
•§•
Table
Flow
ASME Code Case N-2015]
^(Appendix Y)^.S.
11^^r NG-3000i
4-
4-
ufl ^-
Sit]-.
27H
^r 13
Appendix
fl-^ (Appendix Y)-^
-294-
(7ft
Pi)A
NG-3220.1)i ^Tjsfl^ ^7\^o\°\ %t\. 6\ ± ^ 5
t - § - § 5 ^ ^ ^ Table NG-3217-1 <>1 ^ ^ 5 ] o j o jo .^
o | ^ Tableo]]
Level
(Operating Basis Earthquake)^] tfl ^ ^ -^ -g -^ [3.5.5-6]^
Check 1 :
P* * SM (3.5.5-1)
KALIMER^) ^ ^ i ^ ^ ^ l 30\d4
AI (3.5.5.1)^
-!: 5L?f- ^ V ^ ^ H ^ ^^^1^11- -
^ ^ ^ - ^ ( ^ ^ ^ f ^ 4)2]
(3.5.5-1)2]
Check 2 :
^ + n ^ S C T (3.5.5-2)
- 2 9 5 -
(3.5.5-3)
A1 (3.5.5-3)o]H
£=1.57}- 4-§~44-
3. 3.5.5-35] ^ £
Check 3 :
P^+PJK. <S* ' " i — ui (3.5.5-4)
^ (3.5.5-4)oflAi
K,=(K+l)/2 (3.5.5-5)
SJ5] Check 2 11 *\ *}•%••$
Check l^x\£\- 4 t ? } ^ £ KALIMER } ^ ^ ^ ^ 4 l ^ f ]
^cfl rf^5j5--^£ r=455°C4 r=500°Ci cH*V - g - ^ 7 0 V £ ^ ^ ] 5,fe ASME
Code Case N-201-45] Table 5 . 3 B A S ^ f B| z ^ z | 5(=140MPa, 5,=124MPa^ 1
a 3.5.5-3i
(3.5.5-4)^ t
Check
(M-)
- 2 9 6 -
, 2)
, 3) =L$-v\S,5%7}, 4) 5)-
, 5) ^ - 8 - ^ , 6) Isochronous -§-^-^^#
71
Check 1 :
ffSi.0% (3.5.5-6)
3.5.5-15] ^ ^ # ^ 1 cfl«]: §H
(3.5.5-6)2}
Check 2 :
Membranes,,, <\.0%^Bendingsb < 2.Wo^LocalsL < 5.0% (3.5.5-7,8,9)
No. A-l, A-2, A-3)
-297-
Test No. A-l
* ss, (3.5.5-10)
x^+zy/O^^r^e*)™^ (3.5.5-11,12)
°14- ^ (3.5.5-10)^1 Syt
^ ^ • ^ r : ^ ^ %%# 27fl4
i 5^120MPa(455°C), AA^$\ ^ - f 5V=118MPa(500°C)o)
104*1 # : 4 21^ ^ ^ 5 - £ £ l - 4-§-*}^ l ^ t b 1.255,4 ^
^^ l^ i 4 ^ ^ ^ 4-§"tl-4. ^ - ^ ^ ^ ^ ^ f i Sa = Min[1.255f , Sy ] =
Min[1.25xl42MPa, 120MPa] = 120MPao]ol ?*?]$-$] ^ ^ ^ l f e Sa =
Min[1.255, , Sy ] = Min[1.25xl35MPa, 118MPa] =
(3.5.5-10)4
^ (3.5.5-12)011
-T1 (Maximum range of secondary stress intensity)
^^J-Efl ^ £ S ? H cfl*}^ TJIA]-^ ^ ^ ^ - g 3 ( a 3.5.5-1)^-
o)*}%.&<>) §^^ -^°flAi t ! ^ S 7 } Startup*}^ Hotstandby^4°$
4 c ]^-§-^ A o^Sl-^ 7}^*}3L oil- 2]cfl o lx l -g-^ 7 ^^^ o^^ ^ ^
a 3.5.5-3^ *1 (3.5.5-10)^ tfl
4 14%
Test No. A-2
^ + 1- 1 (3.5.5-13)
ASME Code Case N-201-4^ Table Y-1323^1
^ s ? i ^-f^l rflsH 1 (3.5.5-13)4
°1^1 ^flS Type 316 SS4 ^- f
- 2 9 8 -
544°C(1011°F)S
£ ^ A } ^ ^ 500°C# ^ ^ * V 4 . ^ M " ^ (3.5.5-13)^
Test No. A-H^ 4.$$. SJSy=l.03\- £ £ S ^ A ^ i ^ £ ^ 4 ^ 3.
3.5.5-34 <H
Test No. A-3
(3.5.5-14)
^•=2.628x105hr l ^ 4 . zie]5l ^fe ^ " # ^ £ 3"/^ 1.5Sy| - ^ cfl*H ASME
Code Case N-201-4^ Fig. 5.55.-?-El
T=500°Cl- J l ^ § | - ^ 1.5Sy|n =180MPa(26.1ksi)ol4.
N-201-4 Fig. 5.5^ Stress-to-rupture x}£.°\] tfl«r ^ ^ ^ ^ - ^ ^ i
ufl ^-g-Al^V^. 1 ^ ^ } ^ 4.61xl05hrS 4^-M-1^ ^ (3.5.5-14)1
(4)
fe- oflH] ^ ^ 1 ^ KALIMER
ASME Code Case N-201-H
ASME J l - ^ 2 : ! - - i ^ lSH^A^ fl-^«>fe 4 ^ « 1 1 ^ ^ i ^ 1 ^ Level A/B
Service Loadings^
- 2 9 9 -
3.5.5-1 Calculated Thermal Stress Intensity and Strain
Me
mb
ra
neBe
ndi
ngTotal
e
(%)
With Thermal Barrier,
(MPa)No. 1
21.3
55.7
66.4
0.059
No. 2
49.3
144.5
152.7
0.147
No. 3
51.4
109.8
113.3
0.143
No. 4
91.4
127.9
130.6
0.146
No. 5
26.3
125.5
127.4
0.167
W/O Thermal Barrier,
(MPa)No. 1
48.6
106.4
105.0
0.092
No. 2
54.2
165.4
173.2
0.166
No. 3
58.0
125.2
129.2
0.162
No. 4
118.6
151.6
151.6
0.166
No. 5
26.6
135.1
137.1
0.178
i t 3.5.5-2 Service Limit Check for Load-Controlled Quantities
With
Thermal
Barrier
W/O
Thermal
Barrier
Check
PartNo. 1No. 2No. 3No. 4No. 5No. 1No. 2No. 3No. 4No. 5
Check 1
(Pm Smt)
Pm21.349.351.491.426.348.654.258.0118.626.6
Smt108108106108106108108106108106
Check 2
(Pm+Pb KSm)
Pm+Pb30.180.263.5122.138.457.485.170.1149.538.7
KSm159159159159159159159159159159
Check 3
(Pm+Pb/Kt St)
Pm+Pb/Kt28.474.061.1116.136.055.778.967.7143.336.3
St140140124140124140140124140124
* Pm : Primary membrane stress due to thermal load of steady state condition
* Pb : Primary bending stress due to OBE load
- 3 0 0 -
5L 3.5.5-3 Service Limit Check for Deformation-Controlled Quantities
WithThermalBarrier
W/OThermalBarrier
CheckPart
No.lNo. 2No. 3No. 4No. 5
No. 1No. 2No. 3No. 4No. 5
Check 1(X+Y<Sa/Sy)
X+Y
0.23 + 0.29 = 0.520.62 + 0.79 = 1.410.51+0.50 = 1.010.97 + 0.30 = 1.270.30 + 0.84=1.14
0.47 + 0.48 = 0.950.65 + 0.93 = 1.580.57 + 0.57 = 1.141.19 + 0.28 = 1.470.31+0.92 = 1.23
S./S.1111111111
IHX Hole
Thermal
Barrier
turns' 11
J|1
EMP Hole
Reactor Vessel
3.5.5-1 Finite Element Model
- 3 0 1 -
500°C (Gas Region)
4
II 480°C
440°C
C I 380°C
3.5.5-2 Thermal Boundary Conditions
- 3 0 2 -
ANSYS 5.5.1APR .3 199910:13:11NODAL SOLUTIONSTEP=1- '.:S U B = 1 \";- '•;'••
T I M E - 1 ..:•'.T E M P "-••••.• ( A V G )
RSY.S=0 \.'-•'•' - ' ':;P.owerGraphics ,E F A C E T = 1 "•:.•":' '.' -AVRES=Mat,"-, "".• ^SMN =38Q.087SMK ,=519.998I——, 380.087:fed -395; 6-333
411.1:79426.724.442.27457.815 •,473.361
.'••4:8 8; 907r— , ' 504.452 :•.:L— J 519.998
3.5.5-3 Calculated Temp. Distributions
3.5.5-4 Calculated Temp. Distribution at SP
- 3 0 3 -
No.3
No.5
No.4
3.5.5-5 Section Numbers for Service Limit Check
202372: :;.805E+07.159EH-08:.237E+08.316E+08.394E+08.473E+08.551E+08.630E+08.708E+08
3.5.5-6 Stress Intensity Contour around Section No.l
- 3 0 4 -
3.5.5-7 Stress Intensity Contour around Section No.2
923417.142E+08.274E+08.407E+08.539E+08.672E+08.804E+D8.937E+08.107E+09.120E+09
3.5.5-8 Stress Intensity Contour around Section No.3
- 3 0 5 -
.227E+07'.204E+Q8..3.86E+08V568E+08.750E+08.S31E+08.lllE+09:.129E+0S.148E+09.166E+09
3.5.5-9 Stress Intensity Contour around Section No.4
9234.1T•
.-3.76E+08,
.166E+09
3.5.5-10 Stress Intensity Contour around Section No.5
- 3 0 6 -
( l )
KALIMER ^ j - 5 L § } ^ 2 : i - ^ ^ 2 ^ * 1 ^ 1 - ^S.«>7l 3R> ^ °] 4 .
^ ^ ^ f e - ANSYS ^
(2) 7-3,^^
Sfl^oi] 4-g-^ t f l ^ 3 H ^ ASNSYS
fe- ANSYSoiH ^l^^l-fe SOLID
3.5.5-11^8: 4 § fl^i ^ \ ^
^ ] ^ g ^ 1 4 ^7j ]2 :^^- M-E}^} ^O]T^ z i ^ 3.5.5-12
Bulk
(3) Sfl^^il-
3.5.5-13^8: f
Smax = 336 MPa > 3Sm = 327 MPa (800°F)
(4)
o]
- 3 0 7 -
Vertically Constrained Nodes
P, = 1720 kPa
Reactor
Vessel
RV Bottom Head Core Support Structure
3.5.5-11 1/4-Model of RI Lower Part and Applied Dead Weight
- 3 0 8 -
Assumed Bulk Temperatures
I ^ H j 300°C
350"C
386°C
450°C
3.5.5-13 Applied Bulk Temperatures for Normal Operation
- 3 0 9 -
AWSYS5/5.3KOV 3 199910:15:33NODAL SOLUTIONSTEP=1 .: -/"SUB =1 :,-.:. .'.".TIME=1SIWT.,-;.-; (AVG)PowerGraph ic sEFACET=1AVRES=MatDMX =.026903SMN =.206E+07SMX =.336E+09
.206E+07
.392E+08
.763E+08
.U3E+09. . vl50E+09;.188E+09
3.5.5-14 Stress Intensity Contour for Dead Weight and Temperature
Conditions of Normal Operation
- 3 1 0 -
6.
KALIMER
7>
ANSYS ^ 2 : ^ s £ a ^ [ 3 . 5 . 6 - l ] l S ^ ^ 7fl
0.3g ^ 5 J ^ 0.2g
191
/«=— o V—^T^ ' ^ ^moment of inertia, m=mass per unit length.Z7r v / m
o] o.74m, vfl^o
^ a 3.5.6-14
^ A A 50%4 28% ^ ^-
l)
- 3 1 1
ANSYS
shell 63 1 4 : 5 } mass21 ]4 | ^
3.5.6-HI SL f-
i 3.5.6-25}
2) ^
[3.5.6-3,4]. ^ -^- i f l^ -^^ i i - i cfl^ ^-^ l -^ t 7fl<LH^ -fi- 171-
3.5.6-3^
5m ^<ifl 3m# i f ^ f l ^M $ITT ^ ^ -S ^ f- JL^§}^ tfl/fi]^. i f o f l
^Sfl #311 ^ 2 : # ^ ^ £ ^ r 100% o]Ao>
3) 7fltiol-
ANSYS
7\)
• 3 1 2 -
3.5.6-31 A-] 3 1 ^ ^-7}-^^7Jl^r(Hydrodynamic Mass Coefficient)
4 tl]
4.07HzS,
10% ^ 5 .
^ S 3.5.6-4i M-B}>S4. a 3.5.6-41
|- 4.04Hz7|- E)o]
I 014
f^ J I - * - ^ 1 ^ ^ ^ s. 3.5.6-51 ^ . ^
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195.13 x 109 N/m2
7965 Kg/m'0.3
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850 Kg/mJ
0.95 x 10-3 m2/sec
- 3 1 6 -
3. 3.5.6-3
UIS 4J?le| i f ^ ? i l 2 ! l ( m / m )
1.40/ 6.87
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0.74/ 3.74
1.40/ 3.74
Hydrodynamic Mass
Coefficient (Cm)
1.09
1.03
1.08
1.33
M= r. *(0.74)2 =365Kg/m, M2 =
Cm =(l+((d/D)2)/(l-(d/Df)
Added Mass/Unit Length
(Kg/m)Outside Sodium
1.09M2
1.03M1
1.08M1
1.33M2
4 /4*(1.40)2 =
Inside Sodium
1.0M2
1.0M1
1.0M1
1.0M2
= 1308.5Kg/m,
3. 3.5.6-4
MODE
1
2
5
(3D -fMli
FREQUENC
Y4.07108
21.6836
62.8089
l ± *]••§-)
EFF. MASS
6974.32
4510.91
364.526
3. 3 ] f;
FREQUEN
CY4.40655
24.0790
69.6307
EFF. MASS
5889.21
3628.60
330.787
%t7iFREQUEN
CY4.03972
21.4656
61.3738
EFF. MASS
7791.97
3979.69
374.020
3.5.6-5
MODE
1
2
5
(3D -n-^ l J l iFREQUENCY
3.76699
19.3206
55.9472
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8404.75
5894.82
401.543
FREQUENCY
3.74194
19.2028
55.2605
EFF. MASS
8849.7
6075.3
511.737
- 3 1 7 -
S. 3.5.6-6 JL-f
X-direction Y-direction Z-directionMODE
1
2345678
FREQU
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3.939.29
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PARTI.
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22.9015.5464.96-7.403.47
-18.96-0.80
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524.68241.72
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73.065.475.51
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-37.08-11.91105.32
EFF.
MASS0.95
0.811.554.55
70.321374.77141.85
11093.10
3.5.6-1
RH5YS 5 .5 .1HW. 20 200019:39:58
1
1I
.VISITS 5.5 .1
- .CSSSS
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3.5.6-2
- 3 1 8 -
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7.
Many components and subcomponents in liquid metal fast breeder reactor
(LMFBR) primary and secondary systems are exposed to sodium from more
than one source, and it is common to find the impinging fluids at
significantly different temperatures. When this occurs, portions of the surfaces
of such components and subcomponents are subjected to fluctuations between
the hot and cold sodium which are the coolants of LMFBR. This exposure of
a surface to alternating hot and cold fluid temperatures during steady state
reactor operation has been termed thermal striping. The thermal striping
phenomenon, which occurs due to an imperfect mixing of sodium streams
with different temperatures is one of the most significant problems in
LMFBR.
Thermal stresses arising from thermal striping can initiate surface cracks
by high cycle fatigue. These types of thermal fluctuations induced the cracks
in reality such as the crack in the expansion tank of Phenix secondary loops,
the crack at the tee-junction of Superphenix and the crack at the cold trap
system of BN-600[3.5.7-l]. Through-the-wall failures of mixing tees have been
reported several times in the test loop and FBR plant, which demonstrates this
mechanism for component failure.
In this section, an efficient numerical method based on the Green's
function concept and Duhamels integral theorem was utilized to calculate
thermal strains and the SIFs(stress intensity factors) to evaluate fatigue damage
and crack propagation under thermal striping loads for the tee-junction of the
secondary piping system. Compared with the standard finite element method,
the present method was confirmed to be effective from the viewpoint of
computational aspect without sacrificing the solution accuracy.
- 3 2 1 -
(1) Description of Benchmark Problem
The present benchmark problem is based on an industrial problem which
has occurred in the secondary circuit of the French liquid metal reactor,
Phenix. It deals with the thermal striping phenomenon. Phenix is a 250 MWe
prototype fast breeder reactor with three secondary loops operating since 1974.
Problems on pipes induced by thermal striping phenomenon have effectively
been observed during the course of inspection, after 90,000 hours of
operation. This technical problem deals with the mixing of two flows with
different temperatures in the secondary circuit of the Phenix during normal
operations. The sodium in a branch line flows into the main pipe of the
secondary circuit as illustrated in Fig. 3.5.7-1. A small bored pipe, connected
with a tee junction to the main pipe discharges sodium at 430C into the main
pipe. Two convergent flows with temperature differences of 90C are mixed
in the tee junction area.
There is a circumferential weld at 160 mm downstream from the
horizontal axis of the tee-junction. The circumferential weld on the main pipe
is as-welded condition at both inner and outer surfaces. The internal pressure
is 2.2 bar for the main pipe and 2.9 bar for the small bored pipe. The
thermal striping damage is to be evaluated after 90,000 hours of operation.
No creep was taken into account due to the low temperature level. Only
steady state operating conditions need to be considered because the operating
transients induce no significant stresses in the area of interest and
corresponding fatigue damage is negligible. The materials of the base metal
for both pipes are AISI304 stainless steel, grade Z5 CN18.10, while the weld
material of the main pipe is 16Cr-8Ni-2Mo and the circumferential welding
was carried out by a plasma welding.
This benchmark problem brings opportunities to compare results of
numerical analysis and observations on a practical problem, not idealized but
industrial, involving a lot of parameters and different aspects of phenomenon
- 3 2 2 -
on thermohydraulic, thermomechanical and fracture behaviors. All numerical
evaluations should be as close as possible to reality without including any
margin.
(2) Thermomechanical Analysis
(7J-) Green's function approach
In the present study, Green's function approach for the crack propagation
problem of a pipe under random type thermal load was proposed, which can
dramatically reduce the amount of calculation in the elastic regime. In
addition, the proposed approach was also applied to the fatigue analysis of a
pipe.
The Green's function is defined as the response of a system to a standard
step or impulse input. The Green's function contains all essential information
of the system when it is properly defined. Based on the Green's function
concept and the Duhamel theorem when it is properly defined, the change of
thermal stresses at time t due to a small change of the boundary temperature
at time can be expressed as follows
(3.5.7-1)
where the stress Green's function, G-» (' ~r) can be determined from the step
change of the boundary temperature. The Green's function needs to be
computed only once for a set of boundary condition under unit step loading.
Equation (3.5.7-1) can be written as
°r*=1™ZAer/''O (3.5.7-2)
From equation (3.5.7--1) and (3.5.7—2)
- 3 2 3 -
' . . = l™2X(r - r ) ^Ar (3.5.7-3)
Equation (3.5.7-3) can be expressed as
"••('>= K( / - r )^ r f r (3.5.7-4)
Equation (3.5.7-4) can be separated as follows
where td is decay time for the Green's function. The decay time is determined
from the response of the system for unit step input.
Since the Green"s function G",ST^ is constant for r-ld, equation (3.5.7-5)
can be reduced as
o- (0= lt G*. ('- T)^dr+ G., (',){©(» -',)-0(0)} p 5 7_6^
Equation (3.5.7-6) shows that the integration over the time range td only
is necessary no matter how long the elapsed time may be for the calculation
of the parameters such as stresses, strains or the SIFs. Then equation
(3.5.7-6) can be expressed as follows with the time range, td divided into n
steps for numerical integration.
a, W = S G: {l ' T< ){®(r<} " ® ( r - 5} + G.t (t,, ){©(/ - td ) - 0(0)} ^ 5 ? _ 7 ^
where r = r., + A r .
Similarly, c«, under a unit step change of boundary temperature can be used
to determine the SIF[3.5.7-2].the Green's function for the SIF,
•324-
(3.5.7-8)
The Green's function method (GFM) for the SIF enables these fracture
parameters to be calculated very efficiently using a simple integration scheme
under thermal loads. The validity of GFM for the SIF of the present
geometrical model is shown in Fig. 3.5.7-2 under triangular thermal loads for
a temperature difference of T=45C from the average temperature of 384.6C
with 0.033 Hz (1 period = 30 sec). The SIFs by GFM showed good
agreement with those by standard FEM as shown in Fig. 3.5.7-2.
(1-4) Description of the model
For thermomechanical analysis, an axisymmetric model with 1540
isoparametric quadratic elements for the heat affected zone of the welded joint
were used as shown in Fig. 3.5.7-3. The model has 14 elements along the
thickness (7mm) direction. The axial displacements were constrained at the
bottom line of the model.
In the present analysis, the ABAQUS version 5.7[3.5.7-3] was used for
heat transfer, thermal stress and fracture mechanics analyses. In addition, some
programming was carried out for stress and fracture analyses using Green's
function method, and for damage evaluation per design code. In this study,
the procedure specified in the ASME section III subsection NH was used for
fatigue damage evaluation.
Loading conditions
- Thermohydraulic(TH) loading
The thermohydraulic behavior of the turbulent flow under thermal striping
phenomenon should be evaluated by using numerical analysis to predict the
thermomechanical and fracture assessment of the tee-junction. An important
- 3 2 5 -
part of this benchmark problem is to evaluate the T/H behavior of the
striping phenomenon described previously. In the present analysis, the random
type fluid temperature history predicted by UK AEA[3.5.7-4] as shown in Fig.
3.5.7-4 was used. The temperature history was computed for 32.5 seconds at
the location of 80 mm downstream from the centerline of the small pipe,
which is the random type as shown in Fig. 3.5.7-4. It was assumed that the
temperature at the inner surface of the pipe was the same as that of the
sodium fluid and the temperature history of the inner surface was the same.
- Mechanical loading
The reaction forces and moments at the location of A and B in Fig.
3.5.7-1 due to the weight and thermal expansion of pipes during nominal
steady state are given in Table 3.5.7- 1.
The residual stresses in a welded joint may have an influence on the
behavior of the crack initiation and propagation because it may change the
levels of mean stresses. However, the residual stresses in a welded joint are
mostly relaxed due to high operating temperatures or by post weld heat
treatment. Therefore, the effects of residual stresses were not considered here.
(sf) Stress Analysis
The thermal stresses were calculated using Green's function approach. The
history of stress intensity is shown in Fig. 3.5.7-5 and every three output
points was plotted. The maximum value of it at welded location of C in Fig.
3.5.7-3 was 173.3 MPa. The stress components at the welded joint under the
random type thermal loads calculated by GFM are shown in Figs. 6 & 7.
The maximum values of stress components were rr = 42.67 MPa, = 186.67
MPa, zz = 211.05 MPa, and zr = 57.05 MPa.
It is interesting to note that the magnitude of the shear strain (zr) level at
the welded joint is as high as that of radial strain (rr) as shown in Fig.
- 3 2 6 -
3.5.7-8 due to the geometric discontinuity while the other strain components
(zz,, ) are relatively small. The variations of the equivalent strain range (eq)
for random type loads is shown in Fig. 3.5.7-9, which shows that the
maximum value of eq at the welded joint is 0.00183. The sampling time of
the T/H data is 0.1 second.
The calculated stress results due to the reaction forces and moments at the
welded joint of the inner surface were very small. The hoop stress due to the
internal pressure was computed to be 7.863 MPa, the axial stress due to
bending at the outermost location of the pipe was 1.838 MPa and the shear
stress due to torsion of the pipe was 0.39 MPa. These stationary stresses
would act as mean stresses in fatigue and crack propagation analysis.
However, the contribution of these stresses under the stationary load to
striping damage was evaluated to be very small. The magnitude of the
equivalent plastic strain was about two orders lower than the elastic total
stain.
(v\) Results of Fatigue Damage Evaluation
The fatigue damage evaluation was performed according to ASME code
subsection NH[3.5.7-5]. The evaluation results of fatigue damage at the
welded joint showed that the number of allowable cycles in design fatigue
curve was 65,000 for the total strain range of 3.77% and the number of
applied repetition of the cycle was 1.08107. Therefore, the calculated usage
factor for this case was 166.15 during 90,000 hours of operation. It was
shown that initial fatigue failure occurred at t = 541.67 (hours) at the same
location.
(2) Fracture Mechanics Assessment
(7J-) Description of the criteria
The propagation law with the effective SIF parameter for AISI304 stainless
- 3 2 7 -
steel was employed as follows ;
JL = C(AKe/ry (3.5.7-9)
where c = 7.5xi(r13, « = 4.
Keff is effective SIF range described in reference [3.5.7-6], and the unit of
the SIF is MPa(m)0.5.
(MO Evaluation of Crack Propagation
The crack propagation analysis using GFM requires determination of the
SIF range, K for the incremental crack lengths. Then, the fatigue lifetime can
be easily determined by integrating the crack propagation formula. To
determine the fatigue crack lifetime, it is necessary to express K as a function
of the crack length a in the crack propagation law of equation (3.5.7-9). The
variations of K for each stage of the incremental crack length were calculated
using the Green's function for the corresponding crack length. The initial
crack length was 0.5 mm. The variation of the SIF is shown in Fig. 3.5.7-10.
The polynomial expression of K for the random type load is
AK = 7 .45- 9724.97a + 7.97x 10'a2 - 3.32x10'a1 +7.36x10"a'
-8.11xlO'V+3.46xlO'V. (MPaJm) (3.5.7-10)
The estimated lifetime up to a=5 mm under the random type thermal load
was 42,689.9 hours.
As for the crack propagation for a>5.0 mm which is over 70% of the
thickness, the validity of Paris law is uncertain because plastic deformation
occurs throughout the remaining ligament.
The instability analysis would show if the crack will propagate through the
thickness or not. In the present analysis, the tearing modulus based on
J-integral was employed to evaluate the crack instability. The calculated
tearing modulus under this thermohydraulic load at welded joint was 0.58
- 3 2 8 -
while the tearing modulus for this material at 427 C based on the
multiple-specimen JR-curve procedure was 612[3.5.7-7]. Therefore, the crack
will be arrested between 5 and 7mm along the thickness direction.
(t}) Reduction of striping damage
The prevention of failure due to striping damage is important in a piping
system of this type where mixing of the two fluids with different
temperatures occurs. Fig. 3.5.7-11 shows the observation results for Phenix
after the operation of 90,000 hours, which shows that the crack was initiated
and propagated in two directions along the welded joint. It was observed that
two cracks were propagated along the radial direction as shown in the left
hand side of Fig. 3.5.7-11. Three kinds of approaches can be proposed to
avoid the striping damage in the welded joint of the main pipe with a
tee-junction;
- Extension of a small pipe into the main pipe
As shown in Fig. 3.5.7-12, the striping damage at the welded joint can be
reduced by shifting the mixing zone from the welded zone by extending the
branch line into the main pipe.
- Change of fluid velocities
The two fluid velocities of vl and v2 in Fig. 3.5.7-12 can be changed to
move the mixing zone from the welded joint. However, this requires overall
thermohydraulic analysis as well as thermomechanical analysis in detail.
- Change of welded location
The welded location can be shifted to the downstream of the main pipe so
that mixing may occur apart from the welded zone.
It can be shown that the third method of shifting welded joint is relatively
simple but Phenix chose the first method to reduce the striping damage. The
reduction of the thermal load at the welded joint due to fluid mixing was
confirmed by measuring the surface temperatures near the welded zone after
- 3 2 9 -
modification of the branch line carried out for Phenix. It was found that the
geometrical bead shape has a very strong influence on the integrity of the
welded joint because it induces a sensitive strength reduction factor due to the
geometrical discontinuity.
As conclusions, the evaluation of the thermomechanical fatigue and fracture
behavior on the tee-junction of a Phenix secondary circuit having a welded
joint at the downstream of its main pipe was carried out using Green's
function method as well as standard FEM.
The evaluation by Green's function method showed that the fatigue failure
under the random type load occurred as early as 541.67 hours of operation at
the circumferential welded joint of the inner surface.
The crack propagation analyses showed that crack would be propagated
over 5mm during 90,000 hours of operation. The crack would be initiated and
propagated up to 5 mm through the thickness direction for 42,698.9 hours.
The instability analysis with tearing modulus showed that the crack would be
arrested at the location between 5 and 7 mm along the thickness direction.
An efficient numerical approach using Green's function concept was mainly
employed for this random type thermal load case. The approach enabled the
calculation of fatigue usage and the crack propagation lifetime by simple
numerical integration.
From the viewpoint of industry, it is important to note that striping
damage can be reduced by shifting the welded joint or moving the mixing
zone from the critical locations with discontinuities in geometry or material.
- 3 3 0 -
i t 3.5.7-1. Forces and moments in the pipe
Location
A
B
Weight
Mx = -4.3 106 N.mmFy = -91 N
My = 2.1 106 N.mmFz = 165 N
Mz = 5.3 105 N.mmMx = 4.3 106 N.mm
Fy = 91 N
My = -2.1 106 N.mmFz = -165 N
Mz = -4.6 105 N.mm
Weight + Expansion
Mx = -1.1 106 N.mmFy = 2,500 N
My = -2.1 106 N.mmFz = 910 N
Mz = 8.7 105 N.mmMx = 1.1 106 N.mm
Fy = -2,500 N
My = 2.9 106 N.mmFz = -910 N
Mz = -2.8 106 N.mm
Small PipeTh = 430'CDi=68mm, t=2.5tnmQ=7 kg/s, p=2.9bar
Main PipeTc = 340'CDi^94mm, t=7mmQ=800 kg/s, p=2.2bar
3.5.7-1 Geometrical configuration of Phenix secondary piping
- 3 3 1 -
Temp(cC)
384.6
AT = ± 45 °C
(a) input thermal load
4x10'
3x10'
2x10*
1110°
1x10*
2x10*
3x10'
p
30
\
\
\
25 40
t
——
i ,
\
45
(sec)
- Green's Fn MethodStandard FEM
/
/
50 55 60
(b) Variation of stress intensity factors
for triangular thermal load of 0.033 Hz
3.5.7-2 Validation the Green's function method in fracture evaluation
- 3 3 2 -
3.5.7-3 Axisymmetric FE model of the main pipe near welded joint
-40
10 20
t (sec)
30
3.5.7-4 History of thermohydraulic data computed by UK AEA
- 3 3 3 -
2.0x10*r
3.5.7-5 Variation of Mises stress
6.0x10 "
4.0x10 "
0.
-4.0x10 -
-8.0x1030
3.5.7-6 Variation of radial and shear stress components at welded point
- 3 3 4 -
2.0x10
1.0x10
inin
-1.0x10
-2.0x10
3.5.7-7 Variation of hoop and axial stress components
1.50x10'
1.00x10
5.00x10"1 "
(O
to
0.00
-5.00x10'* "
-1.00x10'
3.5.7-8 Variation of welded strain components
- 3 3 5 -
0.0020 r
0.0015 -
0.0010
0.0005 -
0.0000 -
— As
t (sec)
3.5.7-9 Variation of equivalent strain range
•
4 . 0 -
3 . 5 -
3 . 0 -
2 . 5 -
ii
\
1
i
i
\
\
AK for random data
f
y•-••-w—•""""•
/
/
' 1
\\
\
\
h\\
0.000 0.001 0.002 0.003 0.004 0.005 0.006 0.007
a(m)
3.5.7-10 Stress intensity factor range as a function of crack length
- 3 3 6 -
small pipe axis
,«] 00 mm
3.5.7-11 Actual observation of the damaged pipe of Phenix
weld
V2Main pipeRi=247mm
3.5.7-12 Reduction of striping damage at welded zone by extending
small pipe into main pipe
- 3 3 7 -
4-
-tf.
t j-^ji ASME Subsection
KALIMER
(1)
^ - g - ^ KALIMER[3.5.7-8]^ ^
530 °C ^ i ^ j :n£-o]ji ^ A ] OIA^L ^ ^ . ^ ^£^>7> 146 °C
S. 1967\i ASME B&PV Code, Section III, Code Case
I975\i Code Case 1592, 1977^d Code Case N-47^
t}o^ 19951^ Subsection NH[3.5.7-9]S.
Code Case N-47^-E^ 5L-& 7 } i
$14-
- 3 3 8 -
Superphenix[3.5.7-10]^ 7 f l ^
1 9 7 0 ^ ^ 1 ^ nl^-S] Code Case N-47^- A f - g - ^ ^ ^ l T%X\S>\
1967^ ? i ^ t b ^ ^ S RAPSODIE^ ^ ^ ^ ^ #
7 l l^# ^ ^ § H Code Case N-47S ^-g-o] Jf^|flrfj7
RCC-MR[3.5.7-12]
71]^1-^tj-. RCC-MR 3 E r ^ ^ S RAPSODIE^ Phenix^l
S Superphenix^l ^ ^ ^ ^ - ^ ^ ^ -
^ S . JOYO^l ^^Alo]]^- ASME Secion III^j- Code Case 1331
3L ^ ^ ^ € ^ S MONJU# 7fl\| ^ ^ 1 ^ : xtfli£
fe^l Code Case 1331^ fM^Til ^ l ^^ l 145} -i
ufl^o] 3fi£*> ji^A^ ^ o f l x^J^ ^ ^ £]o] oil- #0^
1978Hi all:S:'s^l^l^]<y PDS£(- -§-7l Aj Tjl l ^ °] VDS# 7fl1i:§l-^ 1984\1
H l | o j BDS[3.5.7-13]S. 1>^ i^ l ^4 . BDS
FFTF5]- CRBRP5] ^ - f^ l 4^«H^ | ^ ^ l 4 ^ - ^^l7>
ASME SiEL#
- 3 3 9 -
ASME
Severud[3.5.7-14]3 ^ ^ ^q-® N-47-29(1989\£^-)^r ^ ^ - i i - ^ °}7A
•§• 1995^ Subsection N H S
7}
(2) 3 ^ 3 X ] S
(7}-) ASME Subsection NH 2 H S ] yov^
Subsection N H ^ Section III, Subsection NB<^
Subsection N H i
3.5.7-13^1
AA3.5.7-13^
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Freq.
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0.69
0.69
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9.8
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0.21
0.190
0.183
0.225
0.225
0.188
0.192
0.179
i t 3.5.9-2 Enveloped Response Spectrum at Reactor Support for Fixed and
Isolated Cases (Verti.)
Fixed-Base Building
Freq.
(Hz)
0.2
0.54
1.0
2.1
3.5
5.4
7.0
7.5
10.2
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Response
Spectrum(g)
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0.26
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0.72
0.68
0.73
0.75
0.8
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(Hz)
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13.8
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22.5
23.7
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0.5
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0.45
0.42
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0.75
0.75
0.85
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1.29
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12.9
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17.3
22.5
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26.5
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0.65
0.62
0.56
- 3 7 0 -
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Freq.
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1.68
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Freq.
(Hz)
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0.49
0.59
0.7
0.82
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1.38
1.7
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Spectrum(g)
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0.45
0.70
0.70
0.46
0.46
0.3
0.3
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(Hz)
2.6
3.2
3.7
7.6
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0.2
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0.27
0.27
0.195
0.186
0.182
i t 3.5.9-4 Enveloped Response Spectrum at Reactor Building Top for Fixed
and Isolated Cases (Verti.)
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Freq.
(Hz)
0.2
0.54
1.0
2.1
3.5
5.4
7.0
7.5
10.2
Accel.
Response
Spectrum(g)
0.1
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0.26
0.50
0.71
0.73
0.85
0.9
1.15
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(Hz)
11.9
13.8
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22.5
23.7
26.5
33.0
100
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Spectrum(g)
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3.4
3.5
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0.75
0.68
0.565
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Freq.
(Hz)
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0.54
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5.4
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Spectrum(g)
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0.26
0.52
0.80
0.90
0.95
1.1
2.0
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(Hz)
11.9
12.9
15.6
17.3
22.5
23.7
26.5
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100
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Spectrum(g)
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5.9
2.5
1.75
1.15
1.15
1.15
0.98
0.85
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T-Internal Solver
-PostMechanism Design
. Review of Results
. Interference & MaiProperties
Simulation
-FEM Meshing. 2D, 3D, Beam Elements
-Loading & Boundary. Pressure & Forces. Displacements
i-Solver. External Solver(ANSYS, ABAQUS)
. Internal Solver-Results. Natural Frequency. Stress & Displacement
Analyses
4.2.1-1
- 3 8 6 -
ASME B&P Section III, NB, NG, NH,ASME Code Case N-201-4
4.2.2-1 H ^ NSSS
- 3 8 7 -
(Substructures)
STATIC/SOLSPECTR/SOL
( S M E J -No
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4.2.2-2 ANSYS1- °]
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Load Case1234
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Conditions (0.3g)Freq. Remarks
8.1 Hz Non-Iso, RI Freq.4.3 Hz Non-Iso,Core Freq.4.3 Hz Iso., Core Freq.0.7 Hz Isolation Freq.
i t 4.3.1-2 Comparison of Maximum Disp. Responses at Top Nodes
Row 1 Row 4 Row 5 Row 10 Row 15 Row 16 Row 19
ExperimentCASTEM2000CORE-SEIS
FINASFINDSSAFA
SALCONSAC-CORE
9.0-
12.28.06.66.510.59.2
8.47.68.36.55.86.18.18.0
15.219.414.413.212.812.514.612.3
12.614.614.312.411.312.311.113.9
17.412.814.812.413.913.513.611.7
9.56.28.26.56.45.711.38.1
8.6-
10.78.75.86.6-
9.2
- 3 9 4 -
Analysis Part
|
Input Data
- Seismic Model
- Gap Conditions
- Input Motion
1SAC-C(Nonlin
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r
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V
ation of Floor
nse Spectrum)
w
w
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Graphic Part
SAC-POST
- Seismic Model Plot
- Mode Shape Plot
- Mode Shape Animati
SAC-MODAL(Modal Analysis)
w
an
SAC-PLOT- Response Plot
- Check ZPA
4.3.1-1 Contents of SAC-CORE Code
- 3 9 5 -
START
Systenupg
•System Matrix Generation
1t t
Core Elements[M]c.[C]c,[K]c
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g
Fluid Effects
i 1
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in Matrixrade
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4.3.1-2 Analysis procedures of SAC-CORE Code
- 3 9 6 -
ACLP
Core Shroud
Core SupportPlate
4.3.1-3 Clustering of Sub-Assemblies
Former Ring
480.0
Upper Shielding
380.0
Upper Gas Plenum
230.0
Core
130.0
Lower Shielding
30.0Nose Piece
0.0 Cm
tCluster 1
(26 Assemblies)
t tCluster 2 Cluster 3
(51 Assemblies) (26 Assemblies)
4.3.1-4 Core Seismic Analysis Model
- 3 9 7 -
I . , . , , . . , ,
4.3.1-5 Relative Disp. Time History Responses at Node 22
- 3 9 8 -
4e+5
0.0
4.3.1-6 Impact Time History Responses at Gap 1
- 3 9 9 -
2.0
1.5
3 1.0too
Q] 0.5
0.0
-0.5
19 Single Row Model(RAPSODIE Mockup)
W////////A
Nodal PointsGaps at TopGaps at Pad
Fuel Assemblyi i i i i i i i i i i i i i i i i i i
0 1 2 3 4 5 6 7 8 9 1011121314151617181920
Row Numbers
4.3.1-7 Core Seismic Analysis Model of RAPSODIE
-400-
30
.§ 20
a>o
a.«5
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10
0
-10
-20
Range
Positive Direction ExperimentExperimentExperimentSAC-CORESAC-CORE
Negative Direction
i i i i
6 8 10 12 14 16 18 20
Locations (Top Nodes)
4.3.1-8 Maximum Disp. Response at Top Nodes (in Air)
- 4 0 1 -
2.
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BUILD MODEL(PREP7)
Define Element Types
Define Material Properties
Define Real Constants
Create Model Geometry
Generate finite element mesh
iMODAL ANALYSIS(SOLUTION)
Set Analysis Type: Modal
Define Boundary Conditions
SPECTRUM ANALYSIS(SOLUTION)
Obtain Modal Solution
Set Analysis Type: Spectrum
Specify Load Step
TDefine Spectral Values and
Frequencies
RESULT SUMMARY(POST1)
Resume Full Database andDisplay Mode Shapes
Other Postprocessing
TRANSIENT ANALYSIS(SOLUTION)
Set Analysis Type: Transient
Set Time and Substep Option
Define Boundary Conditions
Define Load Step
RESULT SUMMARY(POST26)
Time-History Postprocessing
3.4.2-1
- 4 0 3 -
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BASE PLATE II
- Material : SS41
- Dimension : 2000xl800xl25t
- Anchor Hole : 20 Points
- Taping Hole : 20 Points
( 4 ) GUIDE BASE PLATE
- Material : SS41
- Dimension : 1800xl300x80t
- Taping Hole : 80 Points
ACTUATING BASE PLATE
Material : SS41
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- 4 0 8 -
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M-. INSTRON SCHENCK TESTING SYSTEMS
(1) HYDRAULIC ACTUATOR ASSEMBLY 1 SYSTEM
- Hydropuls Actuator (PL25N /I)
Load : 25 fcN(3}Srir) / 20 k N ( ^ } ^ ) , Stroke : 250 mm
- Set of ball joints (PK25L /I)
- Sevoblock (SBL63/63N /I)
- Servo Valves (SV63 /I) 63 lpm
- Damping Throttle (SB-DD /I)
- 4 0 9 -
- Dampling Throttle Adaptor (SB-DP /I)
- Flushing Block (SB-SB /I)
- Loop compensation system (8800-264 /I)
- Load Cell (PM25K /I)
10kN-4000kN (1. step increments) 2500-7000Hz (without any additional mass)
- Adaptor plate actuator piston (PZ263A /I)
- Bearing-Oil Pump Unit (LPL /I)
- Set of hose lines (SS16/20A6 /I)
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(2) HYDRAULIC POWER SUPPLY
- Hydraulic power pack
(3) DIGITAL CONTROL ELECTRONICS
- Modular Multi-Axis digital control console
(5) TEST S/W
- RS CONSOLE
- Supplied on CD-ROM
- RS PLUS 32
- Supplied on CD-ROM
- Export Packing & Handing Charges
- Inland Freight & Forwarding Charges
KALIMER
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4.3.3-1
4.3.3-2
- 4 1 4 -
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7\. 7fliL
7fl1£^<y ^ s f l ^ S . KALIMER(Korea
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SCOPE
APPLICABILITY
- afl 3 ^ MAIN DEFINITIONS
- 4 4*} DESIGN REQUIREMENTS AND ANALYSIS METHODS FOR
SEISMICALLY ISOLATED SYSTEM (SIS)
- afl 5 # DESIGN REQUIREMENTS AND ANALYSIS METHODS FOR
ISOLATED STRUCTURES, SYSTEMS AND COMPONENTS
- afl 6 # DESIGN REQUIREMENTS AND EVALUATION METHODS FOR
SEISMIC ISOLATOR
- all 7 # DESIGN AND PERFORMANCE REQUIREMENTS FOR SEISMIC
ISOLATION SYSTEM
- all 8^> DESIGN REQUIRMENTS AND ANALYSIS METHODS FOR
INTERFACE SYSTEM
- all 9 # QUALIFICATION OF SEISMIC ISOLATOR, ISOLATION SYSTEM
AND ISOLATED STRUCTUES
- 4 1 5 -
- all 10^- ACCEPTANCE TESTING OF SEISMIC ISOLATORS
- all 1 1 ^ SEISMIC ISOLATION RELIABILITY
- 4 12# SEISMIC SAFETY AND MONITORING SYSTEM
- 4 13# REFERENCE DOCUMENTS
4.
JL 5 a ^ 1 2 ^ - ^
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Isolated System)^ tfl ^ ^ ^ ^ . ^ s f Sfl^iJ-^^ if^ ^ &£-^ A
Seismic Isolation Frequency
Horizontal Displacements
4.3 Seismic Capacity
4 .4^ Upper and Lower Basemat
4 . 5 ^ Soil-Structure Interaction
4.6^! Ultimate Restraint Systems
4 .7^ Seismic Analysis
71711-
Number of Earthquakes for Design
Minimum Number of OBEs
Analysis of Secondary Components
Floor Response Spectra
Static Analysis
-416-
Sloshing
1 4 7 ^
6.1^. General Descriptions
6.2^1 Design Procedures of Seismic Isolator
6.3 Design Vertical Loads and Capacity
6.4^ Design Displacement and Capacity
6.5 Horizontal and Vertical Stiffnesses
6.6^1 Damping
6.7^ Stability
6 .8^ Ultimate Behavior
6.9^ Limits on Scattering of Characteristics
6.10^ Environmental Effects
6.11 Creep Effects
6.12^ Design Life
6.13^ Design Tolerances
6.14^ Material Properties
1 7 ^ - ^ ^ ^ 1 A (Seismic Isolation System)^ tfl
7 . 1 ^ General Descriptions
7.2^ Design Vertical Loads
7 . 3 ^ Design Displacements
7.4^ Seismic Isolator Arrangement
7 .5^ Self-Centering Capability
7.6^ Uplift and Rocking Effects
7 .7^ Additional Isolation Devices
1 8 %•& ^^-t i l^^l ^ l ^ l f - ^
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- 8 . 1 ^ General Descriptions
- 8.2 Design Gaps for Safety-Related Components and Systems
- 8.3 Design Gaps for Non-Safety-Related Components and Systems
- 8.4^ Interface Piping Systems
4 9
9 . 1 ^ Qualification Methods
9.2^ Seismic Isolators
9.3 Seismic Isolation System
9.4^ Seismically Isolated System
10
10.1^. General Descriptions
10.2^ Acceptance Tests
10.3 Identification of Seismic Isolators
10.4^ Documentation
11 ^-&
11.1^ Quality Assurance Program
11.2^ Evaluation of Phenomena Affecting the Reliability of Seismic
Isolators
11.3^ Life-Time of Seismic Isolators
11.4^ In-Service Inspection
12 # £
- 4 1 8 -
12.1 Seismic Safety System
12.2^ Monitoring System
13 # £ -
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Newton methodl: o] -g-0^^^ ^ ^ i ^ ^ * J 1 ^ - -fr
^ %^JL^*1 [4.4.1-40]oil
(1)
(External state variable) £} wc
^ ^(Internal state variable)S.
- 4 2 8 -
ife- 4 i ^ ^ ^ ^ ^ 1 3 7 | f M-BJ-tfl plastic multiplier^
-i- 4Ef\S4.(4.4.1-1)^)- ^ o ] Hookes Law^l
(4.4.1-2)4 (4.4.1-3
f=(-)iEf(cr,X,R,T)o|rf.
JF < 0 elastic region
= F(CT, X, /?, 7") [F > 0 plastic region
(4.4.1-1)
(4.4.1-2)
(4.4.1-3)
^sfl ^ ^ . t b plastic multiplier i
consistent conditional ^IS}^ ^ ^ ^ 4 -
JTJ. ^ o ] ^ - ^ ^Efl^ a^^-o .S .^1 Work hardening
Strain hardening^ nf5} 4^7fl
27fl o]
- 4 2 9 -
(2)
5 - ^ forward
gradient, backward gradient, central difference u j " ^ -§"ol %14- °1
y y= f(t,y), "At ' = ytieat (4.4.1-4)
(4.4.1-4)^ ^ £ )
yl+eA, = y1 + f(t+eAt,y,+M,)At (4.4.1-5)
^ 97]- 0^1 ig forward gradient method, 87> 1 ^ ] ^ backward
gradient method, 87} 1/2^1 ^ central difference method7J- S]^T>11, 9 1 - 0<e<i
>. 7 | . ^ ^ ^ _ <^ti} ^ ^ - ^ ^ ( G e n e r a l Midpoint Rule; o]§]. GMR)
ov
f (cre,Xe,Re,Te,X.)At (4.4.1-6)
AX = XeAt = g(oe,Xe,Re;T9,i)At (4.4.1-7)
AR = R9At = h(ce,Xe,Re,Te,A.)At (4.4.1-8)
^(4.4.1-6) ~ (4.4.1-8)^1 2 ^ ^ ; - f ^ ^ . 5 . 1 *J-§>JL g<q ^ l l - i "
(4.4.1-9)
X9=X,+0AXt=Xt+eg(oe,Xe,Re;T6,l)At (4.4.1-10)
= RI+9h(CTe,Xe,Re,T9ll)At (4.4.1-11)
= F(a9,Xe,Re) (4.4.1-12)
^"Efl ^ ^ ( o e , X 9 , R 9 , T 6 ^ ) ^ ^ ^
- 4 3 0 -
-idNewton method
-3M4- ^ U"4 Plastic multiplier^
(4.4.1-13)
System^ (stiffness matrix)^
(4.4.1-11) (4.4.1-12)
d(Ao) = dai+,
d<*,+, + 9XdX,, ,+-
3 R .dX At (4.4.1-14)
d(AX) = dXi+1 =
d(AR) = dRi+1 =
, 1+1 ax i+1 i+1 aR i+i '+ di JT (4.4.1-15)
dh_
do : ., +ax
dX At
,*"'••+ ax i+l
(4.4.1-16)
(4.4.1-17)
df'\ _ df' fop
(4.4.1-18)
(4.4.1-14) ~ ^} ( 4 . 4 . 1 - 1 7 ) ^ ^ dXj+I>dRi+1)dl
dai+1=Hdei+1 (4.4.1-19)
27fl
- 4 3 1 -
(4.4.1-14)
dy" = At ap3y~
(dy)+E'd8
7 ] ^ dy- = (dcr,+, dXi+1 dRitJ 0)T dy = (doi+1 dXi+1 dRi+1 dl ) 1
P = ( f g h F )7
*\ (4.4.1-20)
E* =
Diagonal *J-<5l 0<?]
(4.4.1-20)
(4.4.1-21)
H* = H x
(dy)= I*-At ^ E*dE = H'de
da=HQdE,
,dR=HRde,
271]
(4.4.1-22)
. o]
NONSTA-EP
4.4.1-8^
- 4 3 2 -
ABAQUS/STANDARD
Initial stressInitial state variable
strain incrementtemperature increment
time increment
USERINIT
USER
.—-—'
FUNC
I — •
r
MEM_MAPStore the information into
common block
INITIALInitialize state variables
CORRECTORintegrate constitutive
equation
CONSISTENTCalculate Tangent Modulus
UPDATEUpdate State Variables
USERDERV
<C^TTime Control ? J ^ >
No•
Return to ABAQUS
-Yes>KTIME
time control w.r.t localtruncation error
4.4.1-1 NONSTA-VP 3.B.&1 Jif-J
- 4 3 3 -
Stress a22 (MPa)
u
r-fc
s o
33
3 «•
Stress a (MPa)
_4i.
•
r|r
Pressure (MPa)K)
o
ofit
S 2 ;
FT-".21E*01
.•J1E.
. 15E-
. 7 7 E -
. '.'HE*
01
02
)2
02
02
6.9OE.
.29C-
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.50E.
.B2E-O:
4.4.1-5
:• * i *
B
(b)
Banff*1 «*_s>
ti] B]-AJ §1] ^
p
1.1 • • •- r
44.1-6
f l iSbS •//.
|ffl--: j^:
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0 0
"
02
02
02
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<. i
(a)
4.4.1-7
(b)
- 4 3 5 -
1Consistent Tangent
Modulus
i
Con.trc; Tine Incrensnt
IConsistent Tangent
Modulus
<
Return to ABAQUS
4.4.1-8 NONSTA-EP £
- 4 3 6 -
2.
^ 1-10 7 l ^ , ^ ^ ^ - £ f e 500-550
^ x f ^ # < y ^ £ 51*1-71- 4 150 °C
30 °C ^
^(progress ive inelastic deformation)o]
[4.4.2-1,2].
(constitutive equation)
(dimensional
instability)-^ ^>7lAl^ ^ S l ^ - H S n] [4.4.2-6], ^^-^[4.4 .2-7] ,
[4.4.2-8] ^ ^
0) 1
i 44
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4.4.2-1^
(2) 'g 4^1^ l
actuatorl-
(4)
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(5)
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600
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^
rolling & pitching
- 4 4 2 -
^(Thermocouples : T/C)4 ^ - ^ l - *}•-§-
28
600 °C?H, ^ ^ i ^ V f e 1 °C
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fe 10 mm,
4-Strain gage*
work coil §
3cm
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sloti:
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4.4.2-8^
A]
- 4 4 4 -
Temp.
V
Temp. Front
V
t CyclicMoving
V
Accumulation of circumferential plastic strain
4.4.2-1 Concept of Thermal Ratchet Phenomenon
- 4 4 5 -
4.4.2-2 Concept of Thermal Ratchet Test
4.4.2-3 Concept of Moving Temperature Distribution
- 4 4 6 -
19 •18
10-^
11—5
12
14
15
•21
16 -17
c:i
Ah
22
/n\
23
24
4.4.2-4 Elevation System of Test Specimen
4.4.2-5 Auxiliary Device for Ratchet Test under Primary and
Secondary Loads
- 4 4 7 -
70mm
10mm 150mm 10mm
Tab M6
© .0...
0
7mm
30mm
8mm
480mm
4.4.2-6 Configuration of Laser Displacement Sensor
- 4 4 8 -
0H!- PncBEEalSteppiriK WbtorDiftibal tfO *i- E A/P Doardj
' U n i t Caba
Printsr,J
oL Unit Digibi VO UuiW Analog Input
(a)
(b)
4.4.2-7 Data Acquisition and Control System
- 4 4 9 -
:3™2 O600
H=500mm
M I : 3mm
316SS
ovality7j- 3mm
: 300mm
4.4.2-8 Configuration of Structural Test Specimen
- 4 5 0 -
(a)
(b)
4.4.2-9 Thermal Ratchet Test Facility
- 4 5 1 -
1. ii^^l?I*fl^-§- SAC-CORE(Version 1.0)
7]-. SAC-CORE S E ^ ]
SAC-CORE 2 E 5 ] # # 2 ] SI ^ £ H f 4.3.1-14 ^ 4 - j i f
SAC-CORE 3 H ^ r
SAC-MODAL,
s}7] ^ SAC-FRS,
4 1 - n s f l s g ^-^§|-7l ^ t b SAC-PLOT,
SAC-MODAL^|
} SAC-POST £
SAC-CORE^ SAC-MODAL^ FORTRAN
J SAC-PLOT^ SAC-POSTfe- Microsoft-C
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71 f-
(1)
)• (4.5.1-1)
[C] ne|ji [K]fe i i^sHl
- 4 5 2 -
# AA
Load pads*]]
Runge-Kutta ^ ^ ^ ^ < t J l ^ # ^
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\ (4.5.1-4)
(4.5.1-1)4) (n x n) ^ t £ ^-§"
(2n x 2n) * 3 1 ^
(4.5.1-5)
^ , = ^ + ^ . ^ = ^ + ^ 6 . xabs=xr+xb (4.5.1-6,7,8)
Runge-Kutta 1
. SAC-CORE
^(condensation
technique)^
(4.5.1-9)
- 4 5 3 -
(4.5.1-10)
1 q (4.5.1-10)^ ^ (4.5.1-9)^1
I -O- cA Ji. s=. ol
-c] RC (4.5.1-11)
(4.5.1-1 Uc
(4.5.1-12)
SAC-COREofl^
, Gap S - l ^ r ^*> Gap
(2)
SAC-CORE SJE.oi
22 ^>^ ^ ^ l i tfl^-Uri, UXJ, Uyj, Urj]
1/30 A
0 C
1/6
0 E
0 - ,
0 0
0 0
)(r,0) -F(r,f
1/600
1/300
0 0
0A(rJ)
p = Density
m = Added Mass per Unit Length
ein = Prestrain
(4.5.1-13)
(4.5.1-14)
- 4 5 4 -
13/35 + 7/10^+1/3^+6/5(/7Z)2
9/70 + 3/10jzS+i/6jZ*2-6/5(r/L)2
(11/210 + 11/120^+1/24(0
(13/ 420 + 3 / 40^ +1 / 24JZJ2
(1 /105 +1 / 60{?i +1 / 120(Z*2 +
( l /140 + l/60(Z* + l / 1 2 0 ^ 2 +
2+(l/10-l/2^)(WL)2)L
-(l/10-l/2^)(r/Z,)2)Z,
+ 1/ 2 .
)L2
r = 11— = Radius of Gyration\J A
^ = Y1E1 I GAsL2
E =Youngs Modulus
L = Element Length
I = Moment of Inertia
G = Shear Modulus
As = A/Fs
A = Cross-Section Area
Fs = Shear Deflection Constant
AE
T0
0
\2E1
0
F0
6EI
0
12EI
6EI
El (4 + </>)
0
6EI
L2 (I + f)
EIQ-f)
L
0
0
12£7
6£7
0
12^7
6EI
0
0
6EI
(4.5.1-15)
- 4 5 5 -
q (4.6.1-14)4 q (4.6.1-15)1- °l-g-sH
{3 ^
q (4.5.1-17)^1^
(4.5.1-16)
(4.5.1-17)
(3) Gap
Load
SAC-CORE
ei*V Gap
(4.5.1-18)4 q
q Gap
10
0
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0
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1
0
0
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0
0
0000
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0
0
0
0
0
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0
0
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0
0
0
0
0
0
0
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0
0
0
0
0
0
0
0
0
0
Gap ^ . i *
(4.5.1-18)
(4.6.1-19)
Gap
C =K.(\-s2)Ts
(4.5.1-20)
- 4 5 6 -
Kx, s, nejJL Ts±= AA Gap 7<H§,
4 - ^ ^ l ^ ^ S . #(Steel)3 ^ - f ^ T f l ^ f e - 0.557}
SAC-CORE 2H<Mfe- Gap 2 . 1 ^ ^
4-
0 0 0 0 0 0
0 0 0 0 0 0
0 0 KXi 0 0 0
0 0 0 0 0 0
0 0 0 0 0 0
0 0 0 0 0 K «J
(4.5.1-21)
(4)
SAC-CORE 3 £ « l | ^ r
mxi
0
0
0
0
0
0
myi
0
0
0
0
00
m - i
0
0
0
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0
0
0
0
0
0
0
myj
0
00000
m(4.5.1-22)
SAC-CORE 2 £ 1
SAC-CORE 2H-g-
, Gap AS.,
Batch
, Gap Master
- 4 5 7 -
(1)
[ NOTE, TNE, TNN, TNM ]
NOTE = user defined note
TNE = total number of elements
TNN = total number of nodes
TNM = total number of material
[ NOTE, MID, EX, El, A, AS, DENS, MU, Fl, F2, Dl, D2 ]
NOTE = user defined note
MID = material ID
EX = Youngs modulus (N/m2)
El = moment of inertia (m)
A = cross sectional area (m)
AS = shear area (m)
DENS = material density (kg/m3)
MU =
Fl
F2
Dl
D2
GAP 7%-
[ NOTE,
Poisson ratio
1st
2nd
1st
2nd
^ <s
natural
natural
modal
modal
TNG ]
frequency (Hz)
frequency (Hz)
damping ratio
damping ratio
NOTE = user defined note
TNG = total number of gap elements
- 4 5 8 -
(4) GAP i i
[ NOTE, GID, KGX, KGY, KGRI, KGRJ, GS ]
NOTE = user defined note
GID = gap ID
KGX = gap stiffness X axis (N/m)
KGY = gap stiffness Y axis (N/m)
KGRI = rotational gap stiffness at I node (N/rad)
KGRJ = rotational gap stiffness at J node (N/rad)
GS = gap size (m)
* TNG # 0 °] ^ - f ^ °J^
(5) GAP
[ NOTE, GID, DGX, DGY, DGRJ, DGRJ ]
NOTE = used defined note
GID = gap ID
DGX = gap damping X axis (TV. sec/m)
DGY = gap damping Y axis (N. sec/m)
DGRI = rotational damping at I node (N. sec/rad)
DGRJ = rotational damping at J node (N. sec/rad)
* TNG % o ?! ^-fofl^ <y^
(6) H
[ NOTE, NN, X, Y ]
- 4 5 9 -
NOTE = user defined note
NN = node number
X = x - local coordinate (m)
Y = y - local coordinate (m)
(7)
[ NOTE, ET, EN, NI, NJ, MN, GN ]
NOTE = user defined note
ET = element type ( ET=1 for beam, ET=2 for gap )
EN = element number
NI = I - node number
NJ = J node number
MN = material number
GN = gap number ( GN=gap ID for ET=2, GN=0 for ET#2 )
(8) ^ 7 } ^ ^ 7^ og^
[ NOTE, TNM ]
NOTE = user defined note
TNM = total number of added mass
(9) ^ 7 > ^ ^ < ^
[ NOTE, NN, AMX, AMY, AMR ]
NOTE = user defined note
NN = node number for the added mass
AMX = added mass X axis (kg)
AMY = added mass Y axis (kg)
-460-
AMR = rotary inertia (kg. m2)
* TNM # 0 91
(10) ^A^d^r ^
[ NOTE, TBC ]
NOTE = user defined note
TBC = total number of boundary nodes
[ NOTE, NN, XDOF, YDOF, RDOF ]
NOTE = user defined note
NN = node number
XDOF = X DOF ( XDOF=0 for fix, XDOF=1 for free )
YDOF = Y DOF ( YDOF=0 for fix, YDOF=1 for free )
RDOF = Rotation DOF ( RDOF=0 for fix, RDOF=1 for free )
(12)
[ NOTE, G, FC ]
NOTE = user defined note
G = gravity (m/s2)
FC = force control factor
- 4 6 1 -
(13) sfl-&
[ NOTE, TI, NTS, STS ]
NOTE = user defined note
TI = time interval {second)
NTS = number of time step
STS = sub-time step
TI/STS
(14) 7}^£-g -^ 3 ^ ^ 7 I ^ °d^
[ NOTE, NARF ]
NOTE = user defined note
NARF = number of acceleration response files
(15) 7H f5L-g-# QQ*M ° J ^
[ NOTE, ARFN, MNN1,MNN2,MNN3,MNN4 ]
NOTE = user defined note
ARFN = acceleration response file name
MNN1 ~ MNN4 = master node number ( MNN#=0 for no-print )
* NARF + 0 9\ ^^-^l1?} °g^
(16) ^ ^ ^ g - ^ - Sj-^
[ NOTE, NDRF ]
- 4 6 2 -
NOTE = user defined note
NDRF = number of displacement response files
(17) ^ ^ - g - ^ 3 ^ ^ o ^
[ NOTE, DRFN, MNN1,MNN2,MNN3,MNN4 ]
NOTE = user defined note
DRPN = displacement response file name
MNN1 ~ MNN4 = master node number ( MNN#=0 for no-print )
* NDRF # 0 <
(is) ^ n ^ ^
[ NOTE, IRFN ]
NOTE = user defined note
IRFN = impact response file name
(19) GAP A i 2 ] MASTER NODE
[ NOTE, GID, MM, MNJ, GL, IRP ]
NOTE = user defined note
GID = gap ID
MNI = master node I
MNJ - master node J
GL = gap location ( GL=0 for inner gap, GL=1 for left end gap, GL=2
for right end gap)
IRP = impact load print option ( IRP=0 for no-print, IRP=1 for print )
- 4 6 3 -
GL Option :
&fe Gap io] G a p _Q
GL=2<?1 ^-ffe i f a ^ ^ o ] 7>^l^<y Gap
* Master node r $*$$. #*H ^ °1H M ^z|- ^^s-ofl ufl
SAC-CORE(Version 1.0) 2 £ r t ^ ^ l ^ l ^^l%fl^-g-
SAC-MODAL, SAC-FRS, SAC-POST n e ] j l SAC-PLOT
SAC-CORE(Version 1.0) 2 £ ^ 1 Upgradel- ^
^]*> SAC-PRE 7fl - 25)
2. J 1 ^ ^ 2 : ^Tf l^-g- NONSTA 3
KALIMER ^^T-S^r 530°C^ Jl
NONSTA-VP ±£.Ii$^r 71]^[4.6.2-1]^}^
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N0NSTA-VP5} NONSTA-EP^l
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NONSTA-VP
(1) NONSTA-VP ^
NONSTA-VP^- ABAQUS-t
ABAQUS[4.6.2-5]
(7}-)
NONSTA-VP ^ ^ Z i e f l ^ J l f - i l - 3L5] 4.5.2-H
USERINIT, USERFUNC, USERDERV
Chaboche model ^ ^ - f <g £ ^JL7> O3o]5-S <=»! xifl q
- 4 6 5 -
USERINIT03, USERFUNC03, USERDERV03
t*{7]x\ Chaboche viscoplastic modeler
4- Chaboche viscoplastic models §-^[4.6.2-6]^
^ 304 316 ^ l ^ l
© USERINIT
71
Subroutine*
*
userfuncO3(srate,tvrate, svrate,
stress,tv,sv,
stran,dstran,dtime,temp,dtemp,
ntens,ntv,nsv,nprop)
implicit real*8(a-h,o-z)
dimension
dimension
dimension
dimension
props(nprop)sratefntens),tvrate(ntens,ntv),
Stress(ntens) , stran (ntens) , dstran
tv(ntens, ntv),sv(nsv)
props,
svrate(ntv)
(ntens)
Cflfl-
stress : -§-^ ^ ^ r s 4 ^ 4 ^ tiT] H
tv : &H4 AJ-Efl^^(Tensorial state variable)-^ 4 ^ 4 ^ HH 1
sv : ^2}-4" ^Bfl ^1 -(Scalar state variable)!? 4 4 ^ H^
n L e n s . v | ^ I i*. i —j -^3-/1 ~^\"i _ (2> —i o T _ —"i f
ndi : ^ 4 -g-^4 T1 (-§-^4 ^-f 11 , 22 , 334 ^ # 44)
nshr : ^ 4 -g-^4 (-§-^^ ^-f 12 , 23 , 134 A^% 44 )
ntv : ^14 4-T- ^n^^l ^
nsv : ili-51- ifl - ^ ^ 4 41
- 4 6 6 -
itvar : $\X] #EJ] ^ O | £ $ ^(dimension)t- ^#3)-fe ufli
(0: stress dimension, 1: strain dimension, 2: other dimension)
param : *fl£
nparam : ^
ntens, ndi, nshrfe
^ i ^-S. 4-§-s)fe i t A i i tfl§}^ °1 € * r i : ^ ^ ^ [4.6.2-6]
3. 4.5.2-
ntv, nsv, itvar, tv, sv, stress, nparam, param °1
Chaboche
Chaboche models] ^ - f ^ 7fl5] ^ ^ ^^ (n tv : l ) 4 f 7 ^ i
1 ^ ^ 107fl
(nparma:10) ^S. ^^^ param^1 tf^^&ty-. Chaboche model ^ ^:
USERINIT^ S. 4.6.2-24 7^x\.
(E) USERFUNC
USERFUNC^ ^ ] ^ - ^ ^ tfla- ^ ^ 5 ]
- 4 6 7 -
Subroutine**
*
implicit
dimension
dimension
dimension
dimension
userfuncO3(srate,tvrate, svrate,
stress,tv,sv,
stran,dstran,dtime,temp,dtemp,props,
ntens,ntv,nsv,nprop)
real*8(a-h,o-z)
props(nprop)
srate(ntens),tvrate(ntens, ntv) , svrate(ntv)
Stress(ntens ) , stran (ntens) , dstran (ntens)
tv(ntens, ntv) , sv (nsv)
srate : M 3 g ^
tvrate
svrate
stress
tv : ^
sv : *
stran :
dstran
dtime
temp :
dtemp
props
ntens :
ntv :
nsv : ^
nprop : 4S.
- 4 6 8 -
g ^ ^ srate, tvrate, svrate o)\^
^ 3.7\7\ ntens*ntv <(\ 2?\Q a f l ^ ^ j i tvrate(
fe 3.7171- nsv^l tifliolji sv( i WM ife ^
tvrate^ svratei
Chaboche
3 s - an = —
(4.5.2-5)^
*P=P" (4.5.2-1)
J(s-a)-K-c
K / (4.5.2-2)
2J(s-a) (4.5.2-3)
- a ) ^ s - a ^ Mises-^Sl ^ - ^
-a) = A||(SU -SK8u -°u) (4.5.2-4)
J(s-o)j (4.5.2-5)
(4.5.2-6) ofl ^
£ A1 (4.5.2-7) 0]] ^
K = b(Q-K)p (4.5.2-7)
316 i ^ l ^ I ^ i
^ q (4.5.2-7)44 3.7]$.
EflS. 3. 4.5.2-3 1 ^ el 4 ^ 4 . Chaboche modeler ^ ^ ^ USERFUNC
4.5.2-44 ^ 4 .
- 4 6 9 -
USERDERV
USERDERV^ Newton method £] ^j-Stil^V * S l ^ r ^^"^V^l -^ § H -g-
Subroutine***
implicit
dimension
dimension
dimension
dimension
userfuncO3(srate,tvrate,svrate
stress,tv,sv,
stran,dstran,dtime,temp,dtemp
ntens,ntv,nsv,nprop)
real*8 (a-h,o-z)
props(nprop)srate(ntens),tvrate(ntens,ntv),
Stress(ntens) , stran (ntens) , dstran
tv(ntens, ntv) , sv(nsv)
props,
svrate(ntv)
(ntens)
^ ^ # X, r i^e} ^ ^ 1 - R,
DstrDst : % , , -g-^ ^ S . # -§-^Ai^ nl^*V
DstrDtv : %x, ^ ^ ^
DstrDsv : % R , -g-^
DstrDe : % , -g-^
DstrDtp : %r , -g-^
DtvrDst : 5^ao, € ^
DtvrDtv : % , € ^
DtvrDsv : % , ^^^-Efl^^ ^ E f
DtvrDe : a % , , W
- 4 7 0 -
Dtvrdtp :
DsvrDst :
DsvrDtv :
DsvrDsv: 5 % R ,
DsvrDe :
DsvrDtp :
3.717}
7] 7} ntens*ntv*ntens
Chaboche
< 11- s.^[ DtvrDst^ ^ - f tvfe
st^ 37l7> ntens*] Hfl^oj^S DtvrDstfe 3.
( 00] 5}
JCs-CO-K-CTj
K
5K
m/J(s-a)-K-gy
K
dnk 1 (3
2) -g-
dai
(4.5.2-8)
(4.5.2-9)
(4.5.2-10)
(4.5.2-11)
(4.5.2-12)
- 4 7 1 -
dai v Jdaj (4.5.2-14)
da, , .p dp-^- = (-)tiknk— (4.5.2-15)
&7=ATE ' J (4.5.2-16)
da, 1^T = (-)^EiJ«; (4.5.2-17)
4] (4.5.2-17)5] j
3)
; + 3 % p (4.5.2-18)
(4.5.2-19)
ddl _(2 ~)dp_ = _Cn i-Ya1j— (4.5.2-20)
9KK ) a ^ (4.5.2-21)
= b ( Q K ) ^ (4.5.2-22)
dk ,' dr>
_ = _ b p + b ( Q _ K ) _ (4.5.2-23)
Chaboche 3.^-k °im-et USERDERV^r 3. 4.5.2-5^
NONSTA-VP!-
i ^1 ^ ^ * > Chaboche
- 4 7 2 -
*material,name=316ss
*depvar
10,
*user material, constants=4
3, 0.5, 0.001, 0*user subroutines, input=nonsta_vp.f
*material,name=316ss
°1 17]] o] j i ^ ^ - ^ ^-g-o] l fl <y ^ ^ - ^ depvarl- 10 ^
^ H > ^ 1 o . ^ EiUi ^ « - 4 ^ ^ e f ^ ^ ^ 7 f l ^ ^ . 7^7\ n t v ,
depvar^- 6 x ntv + nsv g.t\-
*user material,constants=4
3, 0.5, 0.0Q1, 0
Chaboche model^
midpoint coefficient: ) # ^) nl
^ (fully implicit integration)°] 5] 31, 0°l
explicit integration) 61 14-
: Newton ^ ^ ' r ^ «t7ll(RTOL)# 51
?~x < RTOL
trucation error7]-
- 4 7 3 -
''user subroutines, input=nonsta vp.f
NONSTA-VP 3.B.
UTILITY SUBROUTINES
- Sinv : -§-^ ^-§-^1 first invariant^ second invariant 1r
- KMULVV : « ] E ^ tfj E ^ ifl
- KMULVT : «
- KMULTV : i
- KMULTT : 3
- KDIADIC : ^B\( xl )Sf ^t]( yj ) # o l ^ ] . ^ ( XI yj
- ESTIFF : ^ # 4
- KTIME : ^]^}^^:4r
^. NONSTA-EP S ^
N0NSTA-EP4 ABAQUS1-
ABAQUS[4.6.2-5]
(1)
i£^<4 Plastic multiplier^ ^ S . 4 4 ^ 1 ^ 4-§-
- 4 7 4 -
USERINIT, USERFUNC
Chaboche[4.6.2-7]
-s}4. Nonlinear kinematic hardening f h ± ^ n ^ ^ - c
[4.6.2-3]i ^ s . ^ ^Bfl* Aj-§-§}$34. °1 S . 1 ^ 304 * 316 ^
(7]-) USERINIT
(4) USERFUNC
F = j(s-X)-R-p3 (4.5.2-24)
J(s-x)-^-(slj-xli)(siJ-xu) (4.5.2-25)
2J(s-a)J (4.5.2-26)
(4.5.2-27)oll <5^H ^ ^ ^ 4 -
<J = E(8-8p) (4.5.2-27)
] ^ ^ (4.5.2-28)4 ^ (4.5.2-29)4
- 4 7 5 -
(4.5.2-28)
(4.5.2-29)
(2) NONSTA-EPf- ABAQUS4
4 &TT
4.6.2-241
Chaboche
^material,name=316ss
*depvar
10,
* u s e r m a t e r i a l , c o n s t a n t s = 7
1 4 4 . d 9 , 3 . d - l , 7 0 . d 6 , 1 .3d3 , 6 7 . 5 d 6 , 12, 3 0 . d 6
* u s e r s u b r o u t i n e s , i n p u t = n o n s t a e p . f
ntv,
^^1 I7flolji i
depvarfe- 6*ntv+nsv
4^87fl
^ depvarl- 10
- 4 7 6 -
: nonsta_ep^ < ^
Q
NONSTA-EP i
^ i - f - common blocks]
^ ^ ) o j r i g i d rotation^ 5L
Plastic multiplier!-
Plastic multiplier^
-Mem_map
-Rigid :
-Predictor :
-Corrector:
-Continuum
-Consistent
-Update : ^
-Reform :
-Rtsafe : Newton method#
-Newt : Newton method^
-Fdjac: ^ H l S *] -*S l(Jacobian matrix)^:
-Lnsrch : - ^ ^ ^ ^ ( L i n e search technique)^- ^r
-Lubksb : * S 1 ^ ^ ^ ^ ( B a c k substitution)^:
-Ludcmp : LU decomposition^:
-Estiff : ^ ^ 7 j - ^ * S t 4 ^
-Sinv : -§-^ A^^:^l First invariant^ Second invariant^
-Ktime : Time step^-
^r-=r
4.6.2-63]- i 4.6.2-7oll
- 4 7 7 -
USERINIT3}- USERFUNC ^ H
4.5.2-8^1
S. 4.5.2-1 ntens, ndi, nshr
Element type
Beam element
Plane stress element
Plane strain element
Axisymmetric element
3-D element
ntens
1
2
3
3
3
ndi
1
1
1
1
3
nshr
0
3
4
4
6
4.5.2-2 Chaboche model USERINIT
1
c
Subroutine userinitO3(stress,tv,sv,ntens,ndi,nshr,ntv,nsv,itvar,
* param,nparam)
implicit real*8 (a-h,o-z)
parameter (np = 50,nv=10)
dimension stress(ntens),tv(ntens,ntv),sv(nsv)
dimension param(np)
dimension itvar(nv)
number of tensorial components
ntv = 1
number of scalar components
nsv = 1
type of tensorial components
do 1 i=l,l
itvar(i) = 1
Initial value of state variables
do 10 i=l,ntens
- 4 7 8 -
stress(i) = O.dO
10 continue
do 20 j=l,ntv
do 20 i=l,ntens
tv(ij) = O.dO
20 continue
do 30 i=l,nsv
sv(i) = O.dO
30 continue
c number of parameters
nparam = 1 0
c Value of parameter value
param(l)= 196000
param(2)= 0.3
param(3)= l.d-5
param(4)= 151
param(5)= 24
param(6)= 82
param(7)= 162400
param(8)= 2800
param(9)= 60
param(10)= 8
return
end
S. 4.5.2-3 Chaboche 3.^2$
7}5L
E
K
n
196GPa
0.3
151 MPa
24
WlJL
Youngs modulus
Poissons ratio
CTE
y
c
b
Q
82
162400
2800
8
60
Hi JL
-479-
S. 4.5.2-4 Chaboche model^ °J ^ *t USERFUNC
subroutine userfuncO3(srate,tvrate,svrate,
* stress,tv,sv,stran,dstran,dtime,temp,dtemp,props,
* ntens,ntv,nsv,nprop)
c tv : tensorial variable tvrate : rate of tv
c sv : scalar variable svrate : rate of sv
implicit real*8(a-h,o-z)
dimension props(nprop), tv(ntens,ntv),sv(nsv)
dimension srate(ntens),tvrate(ntens,ntv),svrate(ntv)
dimension stress(ntens),stran(ntens),dstran(ntens)
dimension eerate(ntens),devstr(ntens),devmat(ntens,ntens)
dimension dummy(ntens),dmat(ntens,ntens),direct(ntens)
c material parameter
young = props(l)
enu = props(2)
gamma = props(3)
eK = props(4)
en = props(5)
yield = props(6)
C = props(7)
ro = props(8)
Q = props(9)
b = props(lO)
shydro = (stress(l)+stress(2)+stress(3))/3.dO
xhydro = (tv(l,l) + tv(2,l) + tv(3,l))/3.dO
do 10 i=l,3
10 devstr(i) - ( stress(i) - shydro ) - ( tv(i,l)-xhydro )
do 11 j=4,ntens
11 devstr(j) = stress(j) - tv(j,l)
call kmulvv(devstr,devstr,smises,ntens)
smises = dsqrt(1.5dO*smises)
perate = ( dmaxl(smises-sv(l)-yield,O.dO)/eK )**en
if (smises.ne.O.dO) then
do 12 i = l,ntens
12 direct(i) = 1.5d0*devstr(i)/smises
-480-
else
do 13 i = l,ntens
13 direct(i) - O.dO
endif
c define stress rate
do 30 k=l,ntens
30 eerate(k) = dstran(k)/dtime-perate*direct(k)
do 31 k=l,3
31 eerate(k) = eerate(k) - gamma* dtemp/dtime
call estiff(dmat,young,enu,ntens,3)
call kmultv(dmat,eerate,srate,ntens,ntens)
c define the rate of tensorial components
do 40 i=l,ntens
40 tvrate(U) = ( 2.dO/3.dO*C*direct(i) - ro*tv(i,l) )*perate
c define the rate of scalar components
svrate(l) = b*( Q sv(l) )*perate
return
end
S. 4.5.2-5 Chaboche models <Q ^ t t USERDERV
subroutine userdervO3(DstrDst,DstrDtv,DstrDsv,DstrDe,DstrDtp,
* DtvrDst,DtvrDtv,DtvrDsv,DtvrDe,Dtvrdtp,
* DsvrDst,DsvrDtv,DsvrDsv,DsvrDe,Dsvrdtp,
* stress,tv,sv,
* stran,dstran,dtime,temp,dtemp,props,
* ntens,ntv,nsv,nprop)
implicit real*8(a-h,o-z)
dimension DstrDst(ntens,ntens),DstrDtv(ntens,ntens,ntv),
* DstrDsv(ntens,nsv),DstrDe(ntens,ntens),DstrDtp(ntens),
* DtvrDst(ntens,ntv,ntens),DtvrDtv(ntens,ntv,ntens,ntv),
* DtvrDsv(ntens,ntv,nsv),DtvrDe(ntens,ntv,ntens),
* Dtvrdtp(ntens,ntv),
- 4 8 1 -
* DsvrDst(nsv,ntens),DsvrDtv(nsv,ntens,ntv),
* DsvrDsv(nsv,nsv),DsvrDe(nsv,ntens),DsvrDtp(nsv)
dimension stran(ntens),dstran(ntens),props(nprop)
dimension stress(ntens),tv(ntens,ntv),sv(nsv)
dimension thrate(ntens)
dimension dummy(ntens),dmat(ntens,ntens)
dimension amat(ntens,ntens),devstr(ntens)
dimension bmat(ntens,ntens),cmat(ntens,ntens)
dimension direct(ntens),xvec(ntens),gamma(ntens,ntens)
young = props(l)
enu = props(2)
alpa = props(3)
eK = props(4)
en = props(5)
yield = props(6)
C = props(7)
ro = props(8)
Q = props(9)
b = props(lO)
shydro = (stress(l)+stress(2)+stress(3))/3.dO
xhydro = (tv(l,l) + tv(2,l) + tv(3,l))/3.dO
do 10 i=l,3
10 devstr(i) = ( stress(i) - shydro ) - ( tv(i,l) - xhydro )
do 11 j=4,ntens
11 devstr(j) = stress(j) - tv(j,l)
call kmulvv(devstr,devstr,smises,ntens)
smises = dsqrt(1.5dO*smises)
perate = ( dmaxl(smises-sv(l)-yield,O.dO)/eK )**en
call zero 1 d(direct,ntens)
if (smises.ne.O.dO) then
do 12 i = l,ntens
12 direct(i) = 1.5dO*devstr(i)/smises
endif
beta = (en/eK)*( dmaxl(smises-sv(l)-yield,O.dO)/eK )**(en-l.dO)
call ddsdds(amat,ntens)
call kdi adi c(direct, direct,bmat,ntens)
- 4 8 2 -
call zero2d(gamma,ntens,ntens)
if(smises.ne.O.dO) then
do 13 i = l,ntens
do 13 j = l,ntens
13 gamma(ij) = ( 1.5dO*amat(i,j) - bmat(ij) )/smises
endif
c
c define jacobians of stress rate
c
do 20 i=l,ntens
do 20 j=l,ntens
cmat(i,j) = -l.dO*( perate*gamma(i,j) + beta*bmat(i,j) )
20 continue
call estiff(dmat,young,enu,ntens,3)
call kmultt(dmat,cmat,dstrdst,ntens,ntens,ntens)
do 2.1 i=l,ntens
do 21 j=l,ntens
21 dstrdtv(i,j,l) = -l.dO*dstrdst(i,j)
call kmultv(dmat,direct,dstrdsv,ntens,ntens)
do 22 i=l,ntens
22 dstrdsv(i,l) = beta*dstrdsv(i,l)
c
c define jacobians of tensorial component rate
c
do 30 i=l,ntens
30 xvec(i) = 2.dO/3.dO*C*direct(i) - ro*tv(i,l)
call kdiadic(xvec,direct,amat,ntens)
do 31 i=l,ntens
do 31 j=l,ntens
31 dtvrdst(Uj) = beta*amat(ij)+2.dO/3.dO!|tC*perate*gamma(i,j)
do 32 i=l,ntens
do 32 j=l,ntens
32 dtvrdtv(i,lj,l) = -l.dO*dtvrdst(i,l,j)
do 33 i=l,ntens
33 dtvrdtv(i,l,i,l) = dtvrdtv(i,l,i,l)-ro*perate
do 34 i=l,ntens
- 4 8 3 -
34
c
c
c
40
41
100
110
120
140
dtvrdsv(i,l,l)= -l.dO*xvec(i)*beta
define the jacobian of the scalar component rate
do 40 j=l,ntens
dsvrdst(lj) = b*(Q-sv(l))*beta*direct(j)
do 41 j=l,ntens
dsvrdtv(lj,l) = -l.dO*dsvrdst(l,j)
dsvrdsv(l,l) - b*perate + b*( Q - sv(l) )*beta
dsvrdsv(l,l) = (-l.d0)*dsvrdsv(l,l)
do 100 i = l,ntens
do 100 j = l,ntens
DstrDe(ij) = dmat(ij)/dtime
continue
do 110 i=l,ntens
thrate(i) = O.dO
do 120 i=l,3
thrate(i) = -l.d0*alpa
call kmultv(dmat,thrate,dummy,ntens,ntens)
do 140 i=l,ntens
dstrdtp(i) = dummy(i)/dtime
return
end
4.5.2-6 1*H1 tfl-g-
IA(1)
IA(2)
IA(3)
IA(4)
IA(5)
IA(6)
IA(7)
<r*l A^ ^ (NDI)
# # ^ £ *r (NSHR)t H ^ I 3.7} (NTENS)
^\^- ^ ^ r <r (NSTATV)
4S. -#<*r "T- (NPROP)
.S-dt 41 (NEL)^ ^ ^ ^ S (NPT)
^ ^
IA(8)
IA(9)
IA(10)
IA(ll)IA(12)IA(13)IA(14
Layer «iJi (LAYER)^ E J J ^ « i ^ (KSPT)
i ^ j =r (KSTEP)
^ ^ r ^ (KINC)
€^l A ^ ^r (NTV)i ^ 5 } ^ ^ 41 (NSV)
^ ^ ^[^r *r (NY)
- 4 8 4 -
S. 4.5.2-7 A Pfla.e| Map
N(l)
N(2)
N(3)
N(4)
N(5)
N(6)
N(7)
N(8)
E ^ iflJ=L ^ ^
N(9)
N(10)
N(l l )N(12)
N(21)
N(22)
N(23)
N(24)
^ £ ^^>
EjUi tfl^- ^ ^
Plastic multiplier
i t 4.5.2-8 Nonlinear kinematic hardening models]
subroutine userinit(ntv,nsv,theta)
implicit real*8 (a-h,o-z)*********************************************************
userinit interface card
ntv : number of tensorial variable
nsv : number of scalar variable
theta : midpoint coefficientI t * * * * * :
ntv = 1
nsv = 1
theta = l.dO
return
end
subroutine userfunc(srate,tvrate,svrate,yield,
* stress,tv,sv,eqperate,
- 4 8 5 -
* stran,dstran,dtime,props,
* ntens,ntv,nsv,nprop)
implicit real*8(a-h,o-z)
dimension props(nprop)
dimension srate(ntens),tvrate(ntens,ntv),svrate(ntv)
dimension stress(ntens),stran(ntens),dstran(ntens)
dimension tv(ntens,ntv),sv(nsv)
c
c userfunc interface card
c
c tv : tensorial variable tvrate : rate of tv
c sv : scalar variable svrate : rate of svf~\ T^ ^r ^^ "J *p * f *J* *^ *p *p *f» *j* »J» *|> ^^ *p |* *|* »^ "^ ' j * ^p *p 3|C JJs Jp ?|t *J» J s *^Z Jp *p 3|t 3JQ 'fi ?JN J t JJ» ?p *J* J(* * C JJC J|t Jp J]t Jp j p ?js Jjt JJ ?p J[t JJS J^% *^ T ^
dimension eerate(ntens),perate(ntens),dmat(ntens,ntens)
dimension dummy(ntens)
c < define plastic strain rate (flow rule)>
young = props(l)
enu = props(2)
do 10 i=l,ntens
10 dummy(i) = stress(i)-tv(i, 1)
call sinv(sinvl,seff,dummy,ntens)
yield = seff - sv(l) - props(3)
do 15 i=l,3
15 stress(i) = stress(i) -tv(i,l) - sinvl
eqperate = dabs(eqperate)
if (seff.eq.O.dO) then
do 16 i=l,ntens
16 perate(i) = O.dO
else
do 20 i=l,ntens
perate(i) = 1.5 *(stress(i)-rv(i,l))/seff eqperate
20 continue
end if
- 4 8 6 -
c < define stress rate>
call estiff(dmat,young,enu,ntens,3)
do 30 k=l,ntens
30 eerate(k) = dstran(k)/dtime - perate(k)
call kmultv(dmat,eerate,srate,ntens,ntens)
c < define back stress rate>
do 40 k=l,ntens
tvrate(k,l)= 2.dO/3.dO*props(4)*props(5)*perate(k)
* - props(4)*tv(k,l)*eqperate
40 continue
c < define drag stress rate>
svrate(l) = props(6)*(props(7)-sv(l))*eqperate
return
end
- 4 8 7 -
ABAQUS/STANDARD
Initial stressInitial state variable
strain incrementtemperature increment
time increment
USERINIT
MEMJ/1APStore the information into
common block
INITIALInitialize state variables
USERFUNC
CORRECTORintegrate constitutive
equation USER
iCONSISTENT
Calculate Tangent Modulus
,-—-—
DERV
UPDATEUpdate State Variables
I,<^~Time Control ? J ^ >
NoT
Return to ABAQUS
- Y e s *KTIME
time control w.r.t localtruncation error
4.5.2-1 NONSTA-VP
- 4 8 8 -
Elastic-PlasticTransition
State Variable Update[Inplicit Method)
Return to ftBAQUS
State Variable update[Explicit Method!
ICons'stent Tangent
Modulus
1
Control Time Increment
Co^sister.t TangentModulus
4
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[3.2.2-1] KALIMER Design Concept Report, KAERI/TR-888/97, 1997.
[3.2.2-2] SA120-SB-01/1998, Rev.O, Safety Related Design Basis Events for
KALIMER, 1998.
[3.2.2-3] -fr-g-, ^ 3 3 , °l*Rh ^ f l ^ S KALIMER1- ^ <& ^ ^ 3 ]^ l ^ ^ i (Revision A), KAERI/TR-1544/2000, 2000.
[3.2.2-4] Design Requirements for KALIMER Reactor Vessel,
KALIMER/MS111-DR-01, Rev. A, 1999.
[3.2.2-5] Design Requirements for KALIMER Containment Vessel,
KALIMER/MS412-DR-01, Rev. A, 1998.
[3.2.2-6] Design Requirements for KALIMER Upper Internal Structures,
KALIMER/MS429-DR-01, Rev. A, 1998.
[3.2.2-7] Design Requirements for KALIMER Reactor Head,
KALIMER/MS413-DR-01, Rev. A, 1999.
[3.2.2-8] Design Requirements for KALIMER Secondary EM Pump Vessel,
KALIMER/MS435-DR-01, Rev. A, 1998.
[3.2.2-9] Design Requirements for KALIMER IHTS Piping System,
KALIMER/MS414-DR-01, Rev. A, 1998.
[3.2.2-10] Design Requirements for KALIMER Reactor Support Structure,
KALIMER/MS416-DR-01, Rev. A, 1998.
[3.2.2-11] Design Requirements for KALIMER Steam Generator Support
Structure, KALIMER/MS417-DR-01, Rev. A, 1999.
[3.2.2-12] Design Requirements for KALIMER Reactor Internal Structure,
KALIMER/MS420-DR-01, Rev. A, 1998.
[3.2.2-13] Design Requirements for KALIMER Secondary EM Pump Support
Structure, KALIMER/MS418-DR-01, Rev. A, 1999.
[3.2.2-14] Design Requirements for KALIMER Control Rod Drive Mechanism,
KALIMER/MS431-DR-01, Rev. A, 1999.
- 5 0 1 -
[3.2.2-15] Design Requirements for KALIMER IHTS Piping Support Structure,
KALIMER/MS419-DR-01, Rev. A, 1999.
[3.2.3-1] KALIMER Design Concept Report, KAERI/TR-888/97, 1997.
[3.2.3-2] Design Requirements for KALIMER Containment Vessel,
KALIMER/MS412-DR-01, 1998.
[3.2.3-3] $•&$ ^ , PSDRSS] ^^A]}7] ^ $q, 98
[3.2.3-4] Q*}3, ^ ^^ -§ -7 ] X[o] 7}^ S f l ^ , IOC-MS-011-1999.
[3.2.3-5] KALIMER $\x}3. ^ l ^ l - 7 ] ^ ^ , KALIMER/MS416-WR-01,
1998.
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[3.2.3-10] ASME B&PV Code, Section III, Subsection NH, ASME, New
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[3.2.3-14] Design Criteria and Equations for Torishperical and Ellisoidal heads,
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- 5 0 2 -
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[3.2.4-3] o]^c^ ; 7 j f ^ , -fi-^-, " ^ ^ ] ^ - ^ 5 - KALIMERS] f ^ ^ t
« f l ^ ii^l ^ *fl^", 99 ^ ^ ^ « ] - 5 ] ^ ^ « ] - ^ ^ s ] , 1999.
[3.2.4-4] IHTS v$Q3L7] ^ Hfl?r>£*l &.&-2Z}, OME-3-2, 1999.
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01/1998 Rev.A, 1998.
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^Hl*1]^", t i - ^ ^ ^ s ] 99 ^ ^ I ^ ^ t f l ^ l , 1999.
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- 5 0 3 -
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- 5 2 0 -
IMS
KAERI/RR-2026/99
(KALIMER
2000\fl
520 p. s. s. 5U-8-C O ), 7] A4
O ), 313Hi( ),
7fl
BIBLIOGRAPHIC INFORMATION SHEET
Performing Org.
Report No.
Sponsoring Org.
Report No.Stamdard Report No. IMS Subject Code
KAERI/RR-2026/99
Title / Subtitle Liquid Metal Reactor Design Technology Development /
Development of Mechanical Structure Design Technology forLMR
Project Manager
and DepartmentYoo Bong (KALIMER Technology Development Team)
Researcher and
DepartmentJae-Han Lee, Young-Sang Joo, Hyeong-Yeon Lee, Jong-Bum Kim
Gyeong-Hoi Koo, Seok-Hoon Kim, Chang-Kue Park (KALIMER
Technology Development Team), Ki-Seog Seo (Spent Fuel
Technology Development Team), Young-Sun Choun,
In-Kil Choi (Safety Assessment Team)
Publication
PlaceTaejon Publisher KAERI
Publication
DateMay2000
Page 520 p. 111. & Tab. Yes(O), No ( ) Size A4
Note
Classified Open( O ), Restricted(
Class DocumentReport Type Research Report
Sponsoring Org. Contract No.
Abstract (15-20 Lines)
In this project, fundamentals for conceptual design of mechanical structuresystem for LMR are independently established. The research contents are as follow;at first, conceptual design for SSC, design integration of interfaces, designconsistency to keep functions and interfaces by developing arrangement of reactorsystem and 3 dimensional concept drawings, development and revision of preliminarydesign requirements and structural design basis, and evaluation of structural integrityfor SSC following structural design criteria to check the conceptual design to beproper, at second, development of high temperature structure design and analysistechnology and establishment of high temperature structural analysis codes andscheme, development of seismic isolation design concept to reduce seismic designloads to SCC and establishment of seismic analysis codes and scheme.
Subject Keywords
(About 10 words)
LMR, KALIMER, reactor system, mechanical design, structural
analysis, sesimic analysis, high temperature structure design and
analysis, seismic isolation design
