1

Information exchange meeting between US institutes and JP team

June-July, 2002

K. KataokaToshiba Co.

Development Project of Supercritical-water Cooled Power Reactor

2Presentation overview

PotentialsFour advantages

On going R&D projectPlant conceptual designThermohydraulicsMaterial & water chem.

R&D steps; moving forward

Black smokerWater depth: 2600 mTemperature: 300ºC

3SCPR potentials

Improved power generationHigh thermal efficiency

System simplificationCompact, small volumeNo recirculation/separatorssteam generators

Proven technologiesLWRs, FBR, GCRSCW fossil plants

Flexible core designSCW coolabilityFast/thermal spectrum Supercritical-water

Cooled Power Reactor

4Improved power generation

Thermal efficiency

Regenerative stages: 6Condenser pressure: 5 kPa

SCPR

BWR

Pressure (MPa)

Tem

pera

ture

(°C

)

5System simplification

Reactor

Turbine/Generator

Reactor

Turbine/Generator

ReactorSteam-water separation system

Recirculation system

Turbine/Generator

ReactorSteam-water separation system

Recirculation system

Turbine/Generator

Reactor

Steam generatorPressurizer

Turbine/Generator

Reactor

Steam generatorPressurizer

Turbine/Generator

SCPR ABWR PWR

6Proven technologies

SCW turbine cross-sectional viewNanao-Ota #2 fossil power station700 MWe, TCF4F40", 246 kg/cm2g, 593/593°C

7Flexible core design

0

10

20

30

40

50

100 200 300 400 500 600Temperature (ºC)

Spec

ific

heat

(kJ/

kg/K

)

24 MPa7 MPa

SCW coolability(high heat capacity)

↓Flexible core design

(High/low moderation)↓

Fast/thermal spectrum

8SCPR R&D steps

JP NERI

U Tokyo National, utility joint project

Basic Viable Demonst-rativeStart Goal

CA, EU, JP, RU, US, etc.

International project

2000 20051989 2015

Demo plant construction

9SCPR R&D project

Hokkaido U

Kyushu U

U Tokyo Hitachi

Toshiba

Organization: U Tokyo, Kyushu U, Hokkaido U, Hitachi and Toshiba

Duration: FY2000-FY2004Budget: max. 100 M¥/yearSupport: IAE (METI), JapanStudy themes

Plant conceptual designNuclear boilerSafety systemsTurbine islands, etc.

ThermohydraulicsR22 tests and analyses

Material & water chemistryCladding & structure material

10

Plant conceptual designReference concept: SCLWR (U Tokyo)

Reference plant system

Fuel assembly

Reactor vessel

LPCI

Turbine

Condenser

Condensatewater tank

Main feedwater

pump

CoreWetwell

Demineralizer

CRDPCV

Lowerdry well

Drywell

Suppres-sion pool

RPV

SRVMSIV

AFS

Feedwaterheater

11

ThermohydraulicsTest conditions & items

Fluid

M flux

Sys. P

H flux

Geometry

SCPR

Water Ppc = 22 MPaTpc = 647K

25 MPa(1.1Ppc)

1200 kg/m2/s(rated)

620 kW/m2

(rated)

Rod dia. = 8 mmPitch = 9.5 mm

TestR22

Ppc = 5 MPaTpc = 369K

5.5 MPa(1.1Ppc)

200～2000 kg/m2/s

10～190 kW/m2

Di=4.4 mm

Heated rod

Heated tubeSingle tube

Single rod

Bundle

Fluid channel

FY2001-02: Steady state testsFY2002: Transient tests

FY2003-04: Steady state tests

Fluidchannel

FY2002-03: Steady state tests

12

ThermohydraulicsTest section & supercritical R22 loop

Upperpower connecter

Thermo-couples

Testsectionsupport

Thermalinsulator

Lowerpower connecter

Electricinsulator

Upperflange

Lowerelectric

conductor

Lowerflange

300

Activ

e he

atin

g le

ngth

: 200

0 m

m

700

Inner dia: 4.4 mmThickness: 0.8 mm

Upperelectric

conductor

Heater

13

ThermohydraulicsSingle tube test results

Φ4.4 mm Φ13 mm

q kW/m2

0

50

100

150

200

200 300 400 500

Bulk flud enthalpy hb ｋJ/ｋｇW

all.

tem

pera

ture

Tw

℃

10.11525.130

D-13mmP=5.5MPaG=400 kg/(m2/s)

Heat transfer deterioration

Heat transfer deterioration

14

ThermohydraulicsHeat transfer correlations

Φ4.4 mm Φ13 mm

15

Material & Water ChemistryMaterial screeningSTEP 1: Candidates

Fossil fieldSS, Ni alloys

Waste fieldNi, Ti alloys

LMFBR fieldNi alloys, SS

STEP 2: TestsSimulatedIrradiation

CorrosionSCC Mechanical

STEP 3: Material applicationElementadditive Fine graining Mono

crystallization

Promising candidates

16

Material & Water ChemistryCandidate materials

C o r r o s io nr e s is ta n c e

R a d ia t io nr e s is ta n c e

H ig h -te m p . E x a m p le s

S S 3 0 4 HS S 3 1 0S S 3 1 6S S 3 1 6 L1 2 C r -1 M o 1 W V N bM o d . 1 2 C r -1 M oA llo y 6 9 0A llo y 7 1 8A llo y 8 0 0 HA llo y 8 2 5H a s te l lo y C 2 2H a s te l lo y C 2 7 6N C F 6 0 0N C F 6 2 5T i-3 A l-2 .5 VT i-6 A l-4 VT i-1 5 V -3 A l-3 S n -T i-1 5 M o -5 Z r -3 A l

E x c e l le n t D a tal im ite d G o o d

S ta in- le s ss te e l

A u s te nit ic

F e r r i t ic

N i a l lo y

G o o d D a tal im ite d G o o d

P o o r D a tal im ite d G o o d

T i a l lo y E x c e lle n t N o d a ta P o o r

17

Material & Water ChemistryTEM observation after electron beam irradiation

100nm

550℃450℃290℃

SUS316

SUS316L100nm

100nm

NCF600

NCF625100nm

@ 450°C, 550°CVoid formation@ 450°C, 550°CVoid formation

Little void formation@ 450°C, 550°CDislocation loops

Little void formation@ 450°C, 550°CDislocation loops

18

Material & Water ChemistryEvaluation test of corrosion resistance

DO

P

Heater

Ion exchange resin

N2+

O2

Heat exchanger

ControlTank

Coo

ler

Coo

ler

P

N2

Test sectionMax. temp.: 600 °CMax. pres.: 30 MPa

µS

Generalcorrosion

Test specimen

SCC susceptibility

SSRTDouble U-bendtest specimen

70 m

m70

mm

20 mm

20 m

m20

mm

19

Manned Research Submersible"SHINKAI 6500"

Maximum operation depth: 6,500m

Manned Research Submersible"SHINKAI 6500"

Maximum operation depth: 6,500m

Material & Water ChemistrySCW chemistry & radiolysis

Fundamental aspects of SCW at elevated temperatureThermodynamicsElectrochemistryRadiolysis

Gathering information from variety of industries

LWR technologiesFossil power plantsWaste processing plantsEarth science

System developmentClean upChemical control

20SCPR R&D steps; moving forward

JP NERI

U Tokyo National, utility joint project

Basic Viable Demonst-rativeStart Goal

US, EU, JP, etc.

International project

2000 20051989 2015

Demo plant construction

Role of viable step:To minimize costly-demonstrative R&D

Role of viable step:To minimize costly-demonstrative R&D

21Core design optimization

FA, CR integrity, neutronics, thermohydraulicsReactivity coefficients/control, CR reliability

RPV, internals structure & MS systemsThermal expansion/stress/fatigue & radiation damagesLoad, heat transfer (SRVs, suppression pools)Manufacturability, maintainability

Turbine, startup systemsDesign optimization without reheatingCleanup, water chemistry control systems

Safety systems (licensing)Safety criteria, system design, startup signals/logicSevere accident measures

General arrangement, etc.

Fast option

H-T, P structure(H-T reactors')

U Tokyo design

New JP NERI

International PJ

D. advancingJP NERI to Demo. step

R&D items in the viable step (Designs)

22Heat transfer & pressure drop (develop equations)

Geometric influencesBundle, spacer/grid, HT enhancersFlow direction

Abnormal conditionsLow-flow high-heat-fluxP, T, flow transient conditions

Peaking, stability, natural convectionOrifice design, operation mapWater rod/gap design

OthersCritical flow (develop equations)Flushing during depressurizationDirect heat transfer in suppression poolsFuel ballooning during depressurization

R&D items in the viable step (Thermohydraulics)

Large scale testsCode validation

Performance demo.

Kyushu U tests

Oversea facilitiesInt'l benchmark

Venders & inst.

JP NERI toDemo. step

Fundamental UniversitiesSystem response

23R&D items in the viable step (Mat. & water chem.)

Screening fuel cladding, reactor materialsMany candidates

SS, Ni alloys, Ti alloysAdditive, surface treatment

Various properties under wide range of conditionsMechanical strength, creepCorrosion, SCCEmbitterment

Radioactive transportCP, FP solubility in SCWG value

Principle of SCW chemistry controlling, cleanupChemistry control methods/effectsFilters, separators, etc.

Need more data

Lack of dataRadiolysis

etc.

Screening(JP NERI)

Int'l collaborationReactor tests

New JP PJInt'l collaboration

24R&D items in the demonstrative step

Reactor irradiation tests in SCWCladding materialsReactor structure materialsSCW Radiolysis & mass transfer

Full bundle SCW testsValidation of HT equationsFlow distribution, HT enhancementSystem response under normal/transient conditions

Systems/components performance/reliability testsCRD, safety systemsStructuresWater chemistry controllingStart-up systems, etc.

Detail design & construction of a demo-plant

Large PJ• National PJ• Utilities' PJ• Int'l PJ

Large PJ• National PJ• Utilities' PJ• Int'l PJ

25Summary of our R&D scope

Current JP NERI

Basic Viable Demonst-rativeStart Goal

2000 20051989 2015

JP NERI (H-T, P struct.)

MEXT (Water chem.) --> Systems

INERI (Mat. W chem.) --> Reactor tests

INERI (T/H) --> Large bundle R&D

Demo test, plant design, const.

26R&D item

Design (concept to basic)ThermalFast

H-T, P structureMaterials, structureManufacturing

ThermohydraulicsFundamentalSystem responses

Mat. & Water Chem.Cladding, etc.FundamentalSystems

Demo plantDetail designConstruction, etc.

Int'l collaboration

I-NERI

JAPAN• METI (IAE) Current JP NERI, new proposal on H-T, P structure• MEXT Proposal on water chemistry

University, institute• JAERI Demo plant?• U Tokyo Concept, T/H, Water chem.• Kyushu U R22 tests• Hokkaido U Material study

Utilities• TEPCO (past)

Venders• Toshiba, Hitachi

RUSSIA• IPPE Large T/H facilities• RIAR Irradiation reactor

R&D international collaboration

CANADA• AECL Concept?EU

• EC (FP5&6)Institutes

• FZK Core design• CEA, KFKI, PSI, VTT

Venders• ANP

Utilities• EdF

USA• DOE (NERI, Gen4)

University, institute• INEEL T/H, Irradiation reactor Demo plant?• ANL Water chem.• MIT Materials• Michigan Materials• Wisconsin Materials, T/H

Venders• WH Concept

　Supporters　

27

Development Project of Supercritical-water Cooled Power Reactor

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