Supercritical-water Cooled Power Reactor Development Project

1. IAE* Fund Program K. Kataoka/ Material & Water chemistry N. SaitoLong Term Scope

2. IAE R & D Program Progress Report S. Kasahara- Overview- Irradiation Test & Mechanical Property

3. IAE R & D Program Progress Report N. Saito- Corrosion, SCC, Water Chemistry

4. R&D Collaboration (Discussion)

*1 The Institute of Applied Energy, founded under the auspices of leading industries and the Ministry of Economy, Trade and Industry (METI former MITI).

Supercritical-water Cooled Power Reactor Development Project

Long Term Scope and Milestone for Material & Water Chemistry

Toshiba Corp.Hitachi Ltd.

Hokkaido Univ.Tokyo Univ.

SCPR Research Groups- Materials & Water Chemistry -

Hokkaido U.

Hitachi Ltd.

U. Tokyo

Toshiba Corp.

MIT

U. Michigan

U. Wisconsin ANL

INEEL

USA Japan

Tsuchiya Kano Saito

Sekimura

TakahashiLatanision

Was

CorradiniKasaharaKasahara

Schedule of Generation IV Program

SCPR supporter (US): INEER, U. Michigan, Wisconsin U., MIT, ANL(J): U. Tokyo, Toshiba, Hitachi, Kyushu U., Hokkaido U.

(EU): Framatome ANP, Karlsruhe(FZK), PSI, etc.

Test item Tech. Working Gr. 00 01 02 03

TW1 (Water-cooledReactors)

TW2 (Gas-cooledReactors)

TW3 (Liquid MetalReactors)

TW4 (Non-classicalReactors)

Transition

NERI $16MI-NERI $8.3MGen IV $8M

Budget

TechnicalWorkingGroup

Cross-cutting Group

Fu

el C

ycle

Cro

sscu

t

Eco

no

mic

s

Fu

els

&M

ater

ials

En

erg

yP

rod

uct

s

Ris

k &

Saf

ty

Na, Pb-Bi(Na, Pb, Pb-Bi) X (MOX, U-TRU,-Zr metal,Th-U-TRU-Zr metal, nitride), total 33 concepts

MSR

PMRCANDU-NG

GFR, VHTR

SCWR(T, F)

Vepor Core Reactor, Advanced HighTemperature Reactor, Molten Salt Reactor

6 Reactor Types,Gen IV International

R & D Program ?

Screening of Poential R & D Projects

Gas Cooled Thermal Reactor, Prismatic FuelModular Reactor, Very High Temperature

Reactor, Gas Cooled Fast Reactor

Supercritical Water-cooled Power Reactor,CANDU-NG

Cost Estimation for Material Tests in SCPR R & D (Gen IV Report)

Test item Facilities 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15

Cold test:4 loops

Hot cell test:2 loops(pre-irrad. sample)

In-pile test *:1-2loops (thermal)1-2loops (fast)

Waterchemistry

Out-pile test loopsIn-pile test loops

Materialsstability(Swellig,Phase)

AcceleratorIn-pile test loops

Cold tests

Hot cell test:(pre-irrad. sample)

DBTT

*Candidate: ATR at INEEL Total : $515-565million/25-30years

Research period (years)

Corrosion& SCC

Mechanicalproperty(Strength,Embr'mnt,Creep)

Thermal ($8M/y/loop, $2-4M/y for PSI)

Fast neutron condition ($8M/y/loop, $2-4M/y for PSI)

3 to 5 years ($4M/y)

3 to 5 years ($6M/y) Subtotal: $250 to 330 million

8 years ($15M/y) Subtotal: $120 million

15 years ($3M/y) Subtotal: $45 million

7-8 years ($3M/y)Subtotal:$100 million10 years ($5M/y)

10 years ($3M/y)

Sponsor 00 01 02 03 04 05-10 11-15

National, UtilityJoint Project

IAE* / METI** *The Institute of Applied Energy**Ministry of Economy, Trade and Industry

MEXT******Ministry of Education, Culture, Sports, Science and Technology

SCPR-T (Materials, General design study, Thermohydraulics, Material & Water chemistry)

Fund: 100 M yen/year(1 M$)

Cost-reduced Low-moderationSpectorum BWR

Passive Safety Reduced-moderation LWR

Integrated Modular Reactor

Internal CRD BWR

Water chemistry(from LWR to SCPR)

Fund: 100-500 M yen/year

?

?

SCPR Phase IIFund: 1000 M

yen/year

SCPR Phase IIIFund: 1000 M

yen/year

On-going Future plan

Innovative & Viable Nuclear Energy Technology Development Project

Cladding Material Viability

Water Chemistry Control Viability

MaterialOptimization

ManufacturingProcess

SCPR-T (Materials & Water chemistry,General design study, Thermohydraulics)

Fund: 100 M yen/year(1 M$)

Materials & Water chemistry R & D (Phase II & III)

Phase IIPhase II Phase IIIPhase III

MaterialOptimization

ManufacturingProcess

Test Item Facilities 05 06 07 08 09 10 11 12 13 14 15

Corrosion / SCC/ Uniform corrosion/ SCC/ Hydrogen embrittlement

/ Corrosion loop/ SSRT loop/ Hydrogen absorption test

Irradiation property/ Swelling/ Embrittlement/ Phase Stability/ PCI

/ electron irradiation/ ion irradiation/ neutron irradiation (I) (specimen)/ neutron irradiation (II) (cladding)

Mechanical Property/ Tensile strength/ Thermal creep

/ High temperature tensile test/ Thermal creep test

Manufacturing Process/ Tube, Plate etc./ Welding

/ Processing test/ Welding test

Water chemistry/ Dissolution Rate/ Deposition/ Water chem. Control

/ γ-irrad. loop/ Hot-cell loop

Corrosion testsSCC tests

electron irradiation testion irradiation test

Creep test

Tensile strength

Hydrogen embrittlement

neutron irradiation test (I)

Manufacturing Process

γ-irradiation loop test

Hot-cell loop test

neutron irradiation test (II)

SCPR Target Condition

--*n-spectrum

•6-10 (Cladding)•60 (Plant)

• 5 (Cladding)•60 (Plant)

• 5 (Cladding)•60 (Plant)Lifetime (years)

100-150 (Cladding)10-20(Cladding)10-15 (Cladding)Max. dose (dpa)

--25 MPaPressure

•280-450 to 500oC(Cladding) •LWR+30 to 50oC(Vessel)

•290-560oC(Water) •Comparable to PWR(Vessel)Temperature

FastThermal•Thermal•Once throughReactor Type

Gen IV R & D Report (US)IAE Program (J)

Materials & Water chemistry R & D Collaboration

1. Total Plan

2. Facilities

3. Data Share

4. Cross Check of Evaluation Method

5. Cooperative Experiment Plan

Supercritical-water Cooled Power Reactor Development Project

1. IAE Fund Program (J-NERI) K. Kataoka/ Material & Water chemistry N. SaitoLong Term Scope and Milestone

2. IAE R & D Program Progress Report S. Kasahara- Overview- Irradiation Test & Mechanical Property

3. IAE R & D Program Progress Report N. Saito- Corrosion, SCC, Water Chemistry

4. R&D Collaboration (Discussion)

IAE/METI R & D Program Progress Report

1.Corrosion & SCC2.Water Chemistry

Toshiba Corp.Hitachi Ltd.

Hokkaido Univ.Tokyo Univ.

Test Item Facilities (Condition) 00 01 02 03 04 05-06

Corrosion / SCC/ Uniform corrosion/ SCC

/ Corrosion loop

(Cold, 550oC, 25MPa)/ SSRT loop

(Cold, 550oC, 25MPa)

Irradiation property/ Swelling

/ Electron beam：1000kV, (290, 450, 550oC×5 dpa)

Mechanical Property/ Tensile strength

/ Tensile test

(RT, 550oC)

Water chemistry/ Radiolysis/ Dissolution rate/ E-pH diagram/ E, pH monitoring/ Dose rate simulation

/ γ-irrad. loop

(Cold, 600oC, 50MPa)/ SCW loop (Cold, 600oC, 50MPa)

Materials screening/ Commercial alloys(5 Austenitic alloys, 7 Ni-base alloys, 2 Ferritic alloys, 6 Ti alloys)/ New alloys(Austenitic alloys Ferritic alloys Ni-base alloys)<40-50 M yen / year>

/ G value/ Corrosion environment/ Dissolution rate/ Water chemistry control basic plan<100-500 M yen / year>

On-going Future plan

/ Candidate alloys (2 Alloy types X 2-3 alloys)/ Alloy development plan (Preferable additives, microstructure , etc.)/ Requirements &Criteria (irradiation, corrosion, SCC, Mechanical

Goal in IAE Project (Phase I) - Materials & Water chemistry -

SCPR Materials R & D Team (J) : Toshiba, Hitachi, Hokkaido U., U. TokyoSCPR Water chemistry Team (J) : U. Tokyo, Toshiba, Hitachi, JAERI, CRIEPI

CladdingCladdingMaterialMaterialViabilityViability

WaterWaterChem.Chem.ControlControlViabilityViability

R & D Plan of SCPR Core Component Materials (Phase I)

(Plant Design)

R & D Flow of SCPR Core Component Materials

Electron Beam Testsfor Void Swelling

Optimization of Chemical Composition & Microstructure for Candidate Alloys

Electron Beam Irrad. Testsfor Void Swelling

Corrosion Properties

Assessment

UniformCorrosion

Tests

SCCTests

MechanicalProperties

Assessment

High-temp.TensileTests

FBR

Stainless Steel(Irradiation resistance)

SCWO

Ni Alloys, Ti-Alloys(Corrosion resistance)

Promising Alloys Selection +Alloy Design for Improvement

Viability of Existing Materials

Supercritical Thermal Power

Stainless Steels, Ni-Alloys(High-Temp. strength, Creep)

• Zircaloy is not applicable for SCPR cladding

• Viability assessment of existing alloys in terms of

– Corrosion（SCC）properties

– Irradiation properties

– High-temp. strength

• Improvement of existing materials

• Optimization for SCPR core component materials

Screening commercial alloys

Candidate materials (Interim)• Existing materials (commercial, prototype)

TP: Supercritical pressure thermal power plant materialsWP: Waste processing plants materialsFBR: Fast Breeder Reactor

• New material (Additives, Microstructure)

Ti-6Al-4VTi-13V-11Cr-3Al

Needs irradiation

property datahighInsufficient thermal

creep resistanceFew data available

Excellent(WP)Ti alloy

Alloy625 Alloy690Alloy800

Improve irradiation resistance

middleGood high temp. strength

Poor（FBR)

Good(WP)

Ni alloy(High-Ni alloy)

Modified12Cr- 1Mo

316310

Typical material

Needs corrosion

data

Improve irradiation resistance

Subject

Ferritic

Austenitic

Exist improvedmaterial high temp. strength

Good(FBR)

Poor(TP)

low

Good high temp. strength

Poor(FBR)

Good(TP, WP)Stain-

less steel

CostMechanical properties

Irradiationresistance

Corrosionresistance

Property, achievements, Data base etc.Material

SS316L

SS316LSS310

SS316LNeeds

corrosion data

Better high temp. strengthSingle crystal

Better high temp. strengthFine grain

Needs cost

evalu-ation

Equivalent to 316LImprove

irradiationresistance

A few date available

Trace element addition

Experimental Plan –Corrosion & SCC-

-Ti-6Al-4V, Ti-3Al-2.5V, Ti-15V-3Sn-3Al-3Cr, Ti-15Mo-5Zr-3Al

Ti-6Al-4V, Ti-3Al-2.5V,Ti-15V-3Sn-3Al-3Cr,Ti-15Mo-5Zr-3Al

Ti Alloy

Selected alloys600, 625, 825, 800H, 690, 718, C276, C22

600, 625, 825, 800H, 690, 718, C276, C22

Ni-base alloy

-12C-1Mo-1WVNb,Mod.9Cr-1Mo

12C-1Mo-1WVNb,Mod.9Cr-1Mo

Ferritic

New alloy

Austenitic Sens. 304*, 316L, Selected SS

Sens. 304, 304H, 316, 316L, 310S304, 304H, 316, 316L,310S

Materials

Cylindrical: 4 mmφ, 20 mmG.L.

Coupon specimen: 10X60X2 mm, 8 mmIR

Coupon specimen: 10X20X2 mmTest Specimen

ε: 4X10-7/sε: Constant-Mechanical Condition

SCC

--ODS, Fine grain SS,Single crystal

Evaluation(Analysis)

EnvironmentalCondition

•Fracture surface analysis (SCC ratio)•Maximum stress

Crack initiation•Weight change•Oxide film analysis

Temp. : 290, 450, 550oCPressure: 25MPaO2: 8 ppm

SSRTDouble U-bendUniform corrosion

.

*Finished

SCC Susceptibility

U-bend specimen20 mm

Uniformcorrosion

SCW Loop for Uniform Corrosion and U-bend Test

Supercritical waterSupercritical waterWater chemistry control sectionWater chemistry control section

Sampling line

DO

µS

PHeater

Co

ole

r

N2+

O2

Heat exchanger

Control Control TankTank

Coupon specimen

20 mm

P

N2

Ion exchange resin

Test vessel

SCW

Test vessel

SCW

SpecificationMax. Temp. : 600oCMax. Press. : 25MPaFlow Rate : 50 ml/min

SCW Loop for Slow Strain Rate Test

Supercritical waterSupercritical waterWater chemistry control sectionWater chemistry control section

Test Piece

破 面 拡 大

Example550oC, 25MPa,Sens. Type 304SS

Sampling line

DO

µS

P

Heater

Co

ole

r

N2+

O2

Heat exchanger

Control Control TankTank

P

N2

Ion exchange resin

SSRT Apparatus

SpecificationMax. Temp. : 600oCMax. Press. : 25MPaFlow Rate : 50 ml/min

Web-monitoring systemData and external view can be monitored with PC from outside of building

Requirements & Criteria for Corrosion & SCC Tests

Not Susceptible

Not SusceptibleSCC

O2(8ppm)

Oxidizing species Criteria

Flow rate (m/s)

Temp.(oC)RequirementFlow rate

(m/s)Oxidizingspecies

Water temp.

Refer toBWR

Refer to BWR

Refer to BWR

10-4290450 550

Test Condition

*Thinning

*Oxide film(Deposition)

*

2-5

O2(?ppm)H2O2(?ppm)Radicals

(?mmp)

290 –560(oC)

CP release

Plant Condition (Assumption)

* Needs Discussion

Cladding Material Viability Cladding Material Viability Assessment by 2005.3Assessment by 2005.3

Supercritical-water Cooled Power Reactor Development Project

Toshiba Corp.Hitachi Ltd. Tokyo Univ.

CRIEPIJAERI

1. Corrosion & SCC2. Water Chemistry

Engineering-Reactor Water, MS-

Condensate Demin. Design

Reactor Water Clean up

Degassystem

Radiolysis& Kinetics

Chemical Form of N-compound

Chemical formof FP,TRU

Research Items

Chemical Form & Dissolution Rate of Metal Oxides

Radionuclide Release Rate

Activation of Water

1.Corrosion Environment

・Radiolysis・Electrochemical

Monitoring

2.Radionuclide Transportation

・Dissolution Rate・Chemical Form・Filtration / Deposition

3.Fundamentals of SCW・Thermodynamics・Kinetics

・・Radiation Buildup ModelRadiation Buildup Model

・・Radionuclide Removal Radionuclide Removal SystemSystem

Water Chemistry R & D Plan

Water Chem.Modification

H2O2, O2, H2Concentration

Model Calculation

Radiolysisof SCW

H2O2, H2Evolution Rate

Thermodynamics,Electrochemistry

Oxide Deposition on Cladding Surface

Engineering-Off Gas, Condensate, FW-

Electrochem.Monitoring

Co-free Material

CorrosionTests

CorrosionEnvironment

Requirements for Oxygen conc.

in Condensate

High-temp.Filter

Amount of Corrosion Products （Condensate, Feed Water, SCW）

Activation Rate Calc.

FP,TRU Generation

Metal Release into Coolant

Requirements for CP Reduction in FW

High-temp. Filter

Co-free Material

N-16 Generation

Fundamentals Engineering Key Factor

RadiationBuildupModel

Main SubjectsMain Subjects

Thermodynamics Calculation of SCW

( )

( )( )

( )

( )

( )rT,PT,P

T,P

T,P

r

4r3

r

2r1

r

r

2r

2

r

r

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o

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o

f

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1ω1

ε

1ω

PΨ

PΨlnaPPa

ΘT

1

ΘT

1

PΨ

PΨlnaPPa

ΘTT

ΘTTln

Θ

T

Θ

TΘ

ΘT

1

ΘT

1c

TTT

TＴlncTTSGΔGΔ

rrrr

rr

rr

rr

−−

−−

−+

++

+−

−+

−+

++

+−+

−−

−

−

−

−

−−

+−

−−−=

( )

( ) ∫∫∫ ++−−−=−

+−=−+≡

P

P

oT

T

T

oP

T

T

o

P

r

oT,P

oT,P

oTP,

oT,P

oTP,

of

o

rr

r

r

r

rrrr

rr

dPVdTCdTT

CＴTTSGG

VdPSdTdG

GGGΔGΔ

( ) ( )( ) ( )( ) pH

zF

2.3RTlogaαlogaβ

zF

2.3RT

zE

ΔG　

aa

aaln

zF

RTEE

OcHβSzexHαS

Potential Reduction Cell Half

12

1

22

SS

oT

x

H

α

S

C

OH

β

SoTT

221

⋅−⋅−⋅⋅−−=

−=

+=++

+

−+

( )

( ) ( ) ( ) ( )

( ) ( )

( ) ( )

( ) ( )( )

( ) ( )( ) ( )o

298oT

o298

oT

o298

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A

CBAo298

o298

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SST/298ln

298TS298STGG

ionfor

T2982

298TTφ

2

298TTφ

298

TlnT298TTφ

TCφTBφTAφ298TSGG

CTBTATC

dTCdTT

CT298TSGG

formation of energy Gibbs Isothermal

−−+⋅−⋅−=

⋅⋅−−=

−−=

⋅−−=

+++−−=

++=

+−−−=

−

∫∫

abs oHj

abs oj

oj ΞZΞΞ +−≡

:

:abs o

j

o

k

abs o

j

jkj,

o

k

Ξ

Ξ

ΞνΞ ∑=

:ΞΔ

:ΞΔ

:Ξ

:Ξ

:Ξ

ΞΞΞ

ΞΔΞΞΔ

ΞΔΞΔΞΔ

ΞΞΞ

abs o

jc,

abs ojn,

abs ojs,

abs o

je,

abs o

ji,

abs o

js,

abs o

jn,

abs o

j

abs ojc,

abs oji,

abs ojn,

abs ojs,

abs ojc,

abs oje,

abs o

je,

abs o

ji,

abs o

j

+=

+≡

+=

+=

Revised HKF Model Calc. ECalc. E--pH Diagram of SCWpH Diagram of SCW

Conventional (Conventional (CrissCriss & Cobble)& Cobble)

Materials & Water chemistry R & D Collaboration

Needs Information

1. Electron beam accelerator (Hokkaido U., 1000kV)

IrradiationFacilities

Needs Information

1. SSRT Loop (Toshiba, 600oC, 25 MPa)2. Corrosion Loop (Hitachi 600oC, 25MPa)3. Multi-purpose Monitoring Loop* (Toshiba,

600oC, 50 MPa)4. γ-irrad. Loop* (Hitachi, 600oC, 50MPa)

SCW Test Loop

USJapan

1. Total Plan2. Facilities3. Data Share

1. Total Plan2. Facilities3. Data Share

4. Cross Check of EvaluationMethod

5. Cooperative Experiment Plan

4. Cross Check of EvaluationMethod

5. Cooperative Experiment Plan

* Future Plan

Facilities Available for SCPR R & D