super-critical water-cooled reactor gifiaea/ii-05 scwr gif-iaea... · materials and chemistry...

th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19

Super-Critical Water-cooled Reactor

SCWR System Steering Committee

Y.P. Huang (Chair, China)L. Walters (Canada)

M. Krykova (Euratom)A. Yamaji (Japan)

A. Sedov (Russian Federation)


Contents•Gen-IV SCWR System Members and Projects

•System Integration and Assessment Project

•Thermal-Hydraulics and Safety Project

•Materials and Chemistry Project

•External Collaborations

•Summary


Gen-IV SCWR System Members and Projects• SCWR System Arrangement (year of sign.) and Representatives

– Canada (2006, 2016) L. Walters, K. Huynh– China (2014, 2016) Y.P. Huang (SSC Chair), L.F. Zhang– Euratom (2006, 2017) M. Krykova, R. Novotny– Japan (2006, 2016) A. Yamaji– Russian Federation (2011, 2016) A. Sedov, A. Churkin

• Projects:– System Integration and Assessment (provisional)

» Being managed under the System Steering Committee» Project Plan drafted

– Thermal-Hydraulics and Safety (signed 2009)» Canada (A. Nava, C. Azih), China (J. Zang, X. Liu) and Euratom (X. Cheng)» Extension process in progress

– Materials and Chemistry (signed 2010)» Canada (L. Walters, J. Li), China (L. Zhang, B. Gong), Euratom (A. Saez, R. Novotny)» Extension process in progress


Contributions to SCWR Projects

96

27

47

10 8

Thermal-Hydraulics & Safety Deliverables 2009-2017: Total 188

Canada

China (joined 2017)

Euratom

Japan (withdrew 2017)

Joint

59

15

25

5 5

Materials & Chemistry Deliverables 2011-2017: Total 109

Canada

China (joined 2017)

Euratom

Japan (withdrew 2017)

Joint


System Integration & AssessmentProject (Provisional)•Review and assessment of SCWR concepts–Canada

»Optimization of the small SCWR concept

–China»Development of the plant concept

for CSR-1000»A proposal in place to construct a

prototype SCWR, which will also be a small SCWR concept (CSR-150)

–Japan»Continuing the development of a

fast-spectrum SCWR concept


System Integration & AssessmentProject (Provisional)• Benchmarking of neutronic calculations at supercritical pressures–Resolve discrepancies on

neutronic calculations using various analytical tools

–Specifications of the exercise are being developed» Based on a 4-rod bundle configuration

that has been planned for testing in LVR-15 reactor in Czech Republic

–Research institutes and academia in Canada, China and EU are interested to participate (other organizations will be invited to join)

Rod diameter

Cladding thickness

Rod pitch

Wire thickness

Wire pitch

UO2enrichment

Fissile power

Linear heat rate

8 mm

0.5 mm

9.44 mm

1.44 mm

200 mm

19.75%

63.6 kW

39 kW/m

DimensionsTest fuel assembly


Thermal-Hydraulics and Safety Project and update• Improvements in understanding and predictive capability on

technology areas– Experimental studies to obtain thermalhydraulics data at

supercritical pressures– Compilation of thermalhydraulics database for development,

verification and validation of prediction methods– Benchmarking of analytical tools

» Axially non-uniform-heated 4-rod bundle test at U. Wisconsin-Madison• Safety assessment

– A report on SCWR System Safety Assessment has been issued by GIF


Materials and Chemistry• Understanding of long-term corrosion and stress

corrosion cracking behaviours of fuel cladding alloys at high temperatures.

• Quantification of effect of slow micro-structural degradation on fracture and stress-corrosion cracking resistance of in-core and out-core materials

• Quantification of mechanical properties of fuel cladding alloys at high temperatures and pressures, and the effect of irradiation

• Development of advanced coatings for use on in-core and out-core components

• Establishment of a chemistry control strategy and chemistry monitoring requirements

• Potential cross-cutting interactions with other GIF reactor systems


Round Robin Corrosion Testing• Identifying a cladding material to sustain peak cladding temperatures up to 800oC –Understanding factors affecting corrosion resistance of candidate materials

• Round Robin exercise on material corrosion at supercritical pressures and temperatures–Investigate corrosion characteristics for candidate materials

–Confirm corrosion data of different laboratories are comparable thus usable (e.g., for modeling purposes)

–Completed the first exercise»Large scatter of weight change results

–Initiated the second exercise as confirmation


Summary of Results from the 2nd Round Robin Test on Corrosion in SCW

• Introduced tight control and procedures for specimen preparation, surface finish and specimen distribution

» A single organization responsible for each task to minimize uncertainty• Two materials were included in the test

–Stainless Steel SS310S and Nickel-Based Alloy 800H• Comparison of weight change results obtained from

different laboratories


Materials and Chemistry Project Status• Evaluation of general corrosion and stress corrosion

cracking characteristics for candidate alloys of all key components in the SCWR concepts

• Study of water chemistry to better understand component’s anticipated service environment

• A follow-up campaign on Round Robin exercise on corrosion has been initiated to compare results of different laboratories under a controlled environment

• A first Round Robin exercise on stress corrosion cracking has also been initiated to compare the threshold SCC conditions of different alloys

• Interaction with non-GIF member states through IAEA Technical Meetings

• Project Plan has been updated to include potential contributions of Canada, Euratom and China from 2016-2020


IAEA Collaboration• Cooperative Research

Project “Understanding and Prediction of Thermal-Hydraulics Phenomena Relevant to Supercritical Water- Cooled Reactors”– 12 members from 10 member

states– Linking GIF and non-GIF

experts– Sharing of information,

experimental data and expertise

– Extended for 1 year to cover additional scopes

– A draft TECDOC was reviewed at the last Research Coordination Meeting and is being finalized


Information Dissemination• 12th SCWR Information Exchange

Meeting– Held on March 19-20, 2018, in Montreal,

Canada– Hosted by Canadian Nuclear Laboratories

with cooperation of IAEA and GIF– 38 participants from Canada, China, EU and

Japan– 34 presentations covering concept

development and technology areas• 9th International Symposium on

SCWR– Held on March 10-14, 2019, in Vancouver,

Canada– Hosted by Canadian Nuclear Society with

cooperation of IAEA and GIF– 50 participants from Canada, China, EU,

Japan and the Russian Federation– 60 presentations covering concept

development and technology areas


Summary• Development of SCWR concepts is continuing in Canada, China and Japan

• New project plan on System Integration and Assessment has been drafted for review

• Advancements in technology areas (materials, chemistry, thermalhydraulics and safety) have enhanced the confident in SCWR concept development

• IAEA Cooperative Research Project on SCWR thermalhydraulics have successfully integrated GIF and non-GIF member states for sharing information, experimental data and expertise


Super-Critical Water-cooled Reactor

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