APR1400-F-A-EC-13012-NP, Presentation Material …APR1400 Design Features (1/3)- SIS consists of 4...

Non-Proprietary

CAREM for LBLOCA Analysis of APR1400

Obj ti Objective

APR1400 Design Features

Overview of CAREM Overview of CAREM

RELAP5/MOD3.3 Modifications

Assessment Matrix Assessment Matrix

Plant Nodalization

Uncertainty Parametersy

BIAS Evaluation & Licensing PCT

Contents of Topical Report

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CAREM : Code Accuracy based Realistic Evaluation Model

Objective

To provide a preview of the APR1400 LBLOCA Realistic To provide a preview of the APR1400 LBLOCA Realistic Evaluation Model (CAREM) Topical Report

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CAREM : Code Accuracy based Realistic Evaluation Model

APR1400 Design Features (1/3)

- SIS consists of 4 mechanically independent trains

- Direct Vessel Injection (DVI)

- A safety injection pump and a safety injection tank are installed in each train

Direct Vessel Injection Nozzle

each train.

- All the ECC water is injected into the upper

Core

ColdLeg Hot

Leg

injected into the upper annulus of reactor pressure vessel

Downcomer

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p


Fluidic Device in SIT regulates the injection flow rate and enhances removal of decay heat in early refloodand enhances removal of decay heat in early reflood phase.

water level ≈ stand pipe top

SIT emptied

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LBLOCA Scenario Specification for APR1400 Cold leg guillotine breakg g LOOP and Single failure of a DG assumed

ⅠⅡ Ⅲ Ⅳ

I : Blowdown (~ 20 sec)break open ~ initiation of SIT

II : Refill (~ 35 sec)

Early Reflood Late Reflood

er L

evel

(m) until water level is reached to

the bottom of active core III : Early Reflood (~ 190 sec)

Wat

e y ( )until SIT empty

IV : Late Refloodafter SIT empty

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SIT Empty

after SIT empty

Overview of CAREM (1/3)

CAREM consists of 3 elements and 14 steps as in CSAUCSAU.

Step 9 checks Experimental Data Covering (EDC) using the uncertainty parameters determined in step 8. If it fails, step 8 repeats until the

fcovering is satisfied.

Non-parametric statistics is used in EDC as well as in plant calculations. References:

- Nuclear Tech. V.148, 3, 2004.

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- Nuclear Tech. V.158, 2007.


Best Estimate + Uncertainty Quantification

( )

RELAP5/MOD3.3 + CONTEMPT4/MOD5

Two codes were consolidated to exchange P & M/E

CSAU BasedUncertainty Quantification

- Non-Parametric Statistics

RELAP5/MOD3.3 was slightly modified

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License History in Korea

( )

Plant Type DevelopmentLicensing Review

Approval Remark

WH 3-Loop 1993 ~ 1996 1997 ~ 2002 Sep. 2002 CLI

OPR1000 2002 ~ 2005 2005 ~ 2007 Apr. 2007 CLIWH 2 Loop 2005 ~ 2006 2006 ~ 2007 Dec 2007 UPIWH 2-Loop 2005 ~ 2006 2006 ~ 2007 Dec. 2007 UPIAPR1400 2004 ~ 2008 2008 ~ 2009 Feb. 2010 DVI

• CLI: Cold Leg Injection • UPI: Upper Plenum Injection • DVI: Direct Vessel Injection

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RELAP5/MOD3.3 Modifications (1/5)

Modifications to improve the predictability of quenching titime Results of code assessment against various SETs and IETs Over-prediction of film boiling HTCsOver prediction of film boiling HTCs Under-prediction of quenching time

Modifications Modifications Logic for selecting dry-/wet-wall Film boiling heat transfer calculation

Reference: - Annals of Nuclear Energy 38 (2011) p.1053-1064

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Logic for selecting dry- wall & wet-wall

Definitions of tgsat, pfinrg in subroutines vertdragregand verthifreg were modified.

Before: Becomes wet-wall when steam super heating is below 51 K

After: Restored the selection logic of the previous versions

heating is below 51 K

e s o s Becomes wet-wall when steam super

heating is below 2 K

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Film Boiling Heat Transfer

Subroutine: pstdnb.f

TS

Subroutine: pstdnb.f

Before

hFB = max(hFBB, hFBNB, hFR)hFB max(hFBB, hFBNB, hFR)where,

( ) ( ) ( )0.51400 1880min 0.05, min 0.999 ,0.5 1FBB QF g FBGR gh z hα α = − − + −

hFBNB = Bromley correlation( ) ( )

( )

0.253 0.5

0.62Pr

g g f g fg w spt pfFBNB a

w spt g

gk h T T Ch M

L T T

ρ ρ ρ − + − = −

hFR = Forslund-Rohsenow correlation

( )0.25

2/33

1/3

6 0.9990.4

4g f g fg

FR

g h kh

α ρ ρπ − =

※ HTC calculated by hFBB is much higher

FSS-31108

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( )1/34

6

FR

w spt gT T dπ πμ

−

hFBB is much higher than the data.


TS

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Effect of Modifications (Wet-wall selection and FB HT)TS

Improved predictive capability was validated from the t i t i SET d IET

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assessments against various SETs and IETs.

Assessment Matrix (1/10)

Includes various SETs, IETs and tests specific to APR1400 MIDAS : ECC bypass MIDAS : ECC bypass VAPER : SIT equipped with fluidic device DOBO : Downcomer boiling ATLAS : Overall reflood phenomena, ECC bypass, DC boiling

Includes developmental assessments in RELAP5 documents as well

Comprehensive and broad range of T/H conditions and scales

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Semiscale 1:1600

TS

ATLAS 1:288LOFT 1:50CCTF 1:25UPTF 1:1

Results of Results of assessments against ※ marked experiments are

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experiments are described in TR.


■ MIDAS Direct ECC Bypass Test

TS

yp

Modified linear scaling law length 1/4.9, area 1/24.3, velocity 1/2 2velocity 1/2.2, flow rate 1/53.9

Superheated steam & water

Steam flow rate0.7 ~ 1.8 kg/s(37 ~ 100 kg/s APR1400)( g )

SI injection~ 1.36 kg/s per DVI nozzle(~74 kg/s APR1400)

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(~74 kg/s APR1400)


DVI 4Broken

■ MIDAS Test 100 ~ 108: SI from DVI 2 & 4 Test 109: SI from DVI 2 Test 110 114: SI form DVI 4CL Test 110 ~ 114: SI form DVI 4

TS

DVI 2

APR1400-F-A-EC-13012-NPFT-CL: CL steam flow, FT-DV: SI flow


■ MIDASTS

DVI 4Broken CL

DVI 2DVI 2

Injection from DVI 4: bypassed

I j ti f DVI 2 b d

TS

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Injection from DVI 2: bypassed

Injection from DVI 4 & DVI 2: bypassed

Assessment Matrix (6/10)TS

■ DOBO

Downcomer Boiling Test Downcomer Boiling Test

Circumferential length 1:47

Height 1:1 g gap-size 0.25m,

height 6.4m

One-side of DC heated

Constant heat flux was

simulated in each test

Window for visual investigation

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■ DOBOTS

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■ ATLAS

IET facility equipped with all major components of APR1400

Length 1/2, volume 1/288g ,

Total 1250 instrumentations for measurements of physical parameters and facility controlparameters and facility control

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■ ATLAS Test 15 Studied typical core reflood phenomena after SIT

empty in ATLAS.

TS

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Plant Nodalization Plant model must be nodalized finely enough to capture both

the important phenomena and design characteristics.

But needs to be coarse to make the calculations practical and economical.

Establishment of standard nodalization is needed to diminish nodalization uncertainty.

APR1400 Nodalization Guidelines and the various nodalizations of NPP & test

facilities in RELAP5 documents and internationalfacilities in RELAP5 documents and international experiences were referenced.

NPP nodalization is kept in the test facility nodalization.

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APR1400 Nodalization Each loop and its components are modeled separately. Downcomer is modeled with 6 channels and 10 axial nodes. Core is modeled with 2 hydraulic channels and 20 axial nodes Core is modeled with 2 hydraulic channels and 20 axial nodes. Explicit and fine noding of SG primary and 2ndry sides.

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Uncertainty Parameters (1/3)y

■ All phenomena in PIRT were considered in■ All phenomena in PIRT were considered in determination of uncertainty parameters.

■ U t i ti f t / h■ Uncertainties of parameter/phenomena were

treated statistically

treated conservatively

treated in bias evaluation

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Uncertainty Parameters (2/3)

Component Process/Phenomena Parameter

Stored energyFq, gap conductance, pellet thermal conductivity,

Dittus Boelter liquid forced convection HT

y

Stored energy Dittus-Boelter liquid forced convection HTcorrelation

Pellet heat transfer Pellet thermal conductivityNucleate boiling Chen nucleate boiling HT correlation

Core/Fuel

uc eate bo g C e uc eate bo g co e at o

Critical heat fluxZuber CHF correlation

Groeneveld CHF correlationRewet

Weismann transition boiling HT correlation(Transition boiling HT)

Weismann transition boiling HT correlation

Film boiling HTBromley film boiling HT correlation

Forslund-Rohsenow film boiling HT correlationR di ti HT C ti lRadiation HT ConservativelyBoron reactivity ConservativelyDecay power ANS-79 DHClad oxidation Cathcart Pawel oxidation correlation

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Clad oxidation Cathcart-Pawel oxidation correlation

Example of the determination of uncertainty parameters

Uncertainty Parameters (3/3)

TS

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BIAS Evaluation TS

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Combination of Uncertainties and Biases

Limiting Break Size was determined from sensitivity calculations. Plant Calculations

g y 124 sensitivity calculations for the limiting break. Code parameters and reactor operational parameters are

considered together.considered together.

Bias Evaluation Biases are evaluated for 1100

1200

1300

3rd highest (95/95)

selected cases from plant sensitivity calculations.

3 biases are evaluated 800

900

1000

EMPERATURE, K .

separately.- ECC bypass during refill- ECC bypass during reflood

Steam binding during500

600

700

CLADDING TE

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- Steam binding during reflood

300

400

0 50 100 150 200 250

TIME, seconds

Licensing PCT

Total Uncertainty

Licensing PCT = PCT95/95 + ΔPCTECCbypass_refill

+ ΔPCTECCb fl d+ ΔPCTECCbypass_reflood

+ ΔPCTsteam-binding

+ ΔPCTadditional

※ ΔPCTECCbypass reflood neglected※ ΔPCTECCbypass_reflood neglected

ΔPCTadditional Uncertainty due to plot frequency, time step, .. etc.

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Contents of Topical Report

TR is prepared in accordance with NUREG-1379, Editorial Style Guide

p p

Structured in the order of CAREM procedures of 3 Elements and 14 Steps

10 Appendices to describe the details of PIRT Code modificationCode modification Code assessments against SETs & IETs Coupling RELAP5 and CONTEMPT4 Uncertainty Parameter Values for APR1400 Plants Uncertainty Parameter Values for APR1400 Plants

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Topical Report Table of Contents (1/6)

1. Introduction General introduction of CAREM, APR1400 design feature,

p p ( )

acceptance criteria

2. Methodology Roadmap

3. Requirements and Capabilities3.1 Scenario Specification (Step 1)3 2 NPP S l ti (St 2)3.2 NPP Selection (Step 2)3.3 Phenomena Identification and Ranking Table(Step 3)3.4 Frozen Code Selection (Step 4)3 5 C d D t ti (St 5)3.5 Code Documentation (Step 5)3.6 Code Applicability Determination (Step 6) constitutive equations, numerical solution method,

component models control functions and overall code

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component models, control functions, and overall code capability


4. Assessment and Ranging of Parameters4 1 E t bli h t f A t M t i (St 7)

p p ( )

4.1 Establishment of Assessment Matrix (Step 7) Includes RELAP5 developmental assessments

4.2 Plant Nodalization and Experiment Evaluation (Step 8)4.2 Plant Nodalization and Experiment Evaluation (Step 8) Plant nodalization (Step 8.1) Determination of code uncertainty parameters and

their ranges (Step 8 2)their ranges (Step 8.2) Determination of code parameters for scale bias

evaluation (Step 8.3)

4.3 Check Experimental Data Coverings (Step 9) Code accuracy evaluation (Step 9.1) Check data covering (Step 9.2)

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4.4 Determination of scale bias coverings (Step 10)


5. Sensitivity and Uncertainty Analysis5 1 D t i ti f Pl t I t U t i t (St 11)

p p ( )

5.1 Determination of Plant Input Uncertainty (Step 11)5.2 Combine Uncertainties and Biases (Step 12) Plant base calculation and SRS calculations E l ti f l bi Evaluation of scale biases

6. Quantification of total uncertainties (Step 13, 14)

7. Conclusion

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Topical Report Table of Contents (4/6) Appendices

Appendix A: Identification and Ranking of Phenomena or Processes

Appendices

Appendix B: Freezing of RELAP5/MOD3.3/K Modification of a portion of reflood model Modification on gap conductance calculation Modification to improve code fails due to non-condensable

gases

Appendix C: Assessment of RELAP5/MOD3 3/K against SETs Appendix C: Assessment of RELAP5/MOD3.3/K against SETs

FLECHT-SEASET CCTF

THTF PKL

NEPTUN

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Topical Report Table of Contents (5/6)Appendices

Appendix D: Assessment of RELAP5/MOD3.3/K against IETs LOFT

Appendices

LOFT SEMISCALE LOBI

Appendix E: Assessment of RELAP5/MOD3.3/K against Reflood Test

Appendix F: Assessment of RELAP5/MOD3.3/K against ECC Bypass TestTest UPTF 21D MIDAS (Multi-dimensional Investigation in Downcomer Annulus Simulation)

Appendix G: Assessment of RELAP5/MOD3.3/K against DowncomerBoiling Test DOBO (DOwncomer BOiling)

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( g)

Topical Report Table of Contents (6/6)Appendices

Appendix H: Assessment of RELAP5/MOD3.3/K against FD/SIT VAPER

Appendices

VAPER (VAlve Performance Evaluation Rig)

Appendix I: Coupling RELAP5/MOD3.3/KJ and CONTEMPT4/MOD5

Appendix J: Sampled Uncertainty Parameter Values for 124 Plant Appendix J: Sampled Uncertainty Parameter Values for 124 Plant Calculations

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Information for RAI A complete set of drawings of the reactor primary system, including

the reactor vessel, reactor core, cold leg and hot leg piping, steam generator, pressurizer and the accumulator; a diagram of the emergency core cooling system piping; A set of full size hard copies and copies in PDF format p

: All set will be prepared.

A complete set of code manuals including the theory manual, the input manual and the testing manual. If these manuals are identical to NUREG reports issued by NRC associated with RELAP-5 Mod 3.3, provide a reference list of these NUREG reports

: All set will be prepared.

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Information for RAI A CD containing all the source code, executables, input deck for

Shin-Kori (SKN) unit 3 and unit 4. PVM package used to link the ( ) p gCONTEMPT4/MOD5 with RELAP-5 code

: It needs to be discussed.

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Thank you for your attention

APR1400-F-A-EC-13012-NP

APR1400-F-A-EC-13012-NP, Presentation Material …APR1400 Design Features (1/3)- SIS consists of 4...

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