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Slide 113th 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)
Slide 213th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 313th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 413th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 513th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 613th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 713th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 813th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 913th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 1013th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 1113th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 1213th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 1313th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 1413th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
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
Slide 1513th GIF–INPRO/IAEA Interface Meeting, Vienna, 2019 March 18-19
Super-Critical Water-cooled Reactor
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