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
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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