A study on technology development of In-Vessel corium Retention (IVR) and construction of collaboration basis in PWRs between Korea and France
Description
Based on the agreement item, B-5-4-1 Evaluation of the Severe Accident Management Strategies for High Power PWRs, during the 15th France-Korea Joint Coordinating Committee on Nuclear Energy (JCCNE), technology development of IVR and construction of collaboration basis in PWRs between Korea and France have been performed in this project. Basically, CEA and KAERI agreed to cooperate each other and tried to specify the specific items to be interested in each party. The agreement on cooperation on IVR in severe accident was signed by both sides on June 23, 2003. The first meeting in the frame of the IVR Agreement was held at CEA Grenoble in France on May 26, 2006. The second meeting was held at the Sheraton Grand Walker Hill hotel in Seoul on October 8, 2003 in parallel with the NURETH 10 meeting. The third meeting was held in Aix en Provence of France on March 19, 2004. The forth meeting will be held in Korea at the beginning of 2005. From these meetings, BALI experimental results on the heat transfer of the corium pool in the lower plenum, SULTAN experimental results on the critical heat flux, and ANAIS experimental results on water injection into the corium pool have been acquired. As this international collaboration project has been performed, the experimental and analytical results on the corium behavior and heat transfer in the lower plenum from the CEA will be used in IVR evaluation of the APR 1400 which is domestic a high power PWR and in IVR methodology development of the future reactor. The LILAC computer code and the related thermal hydraulic model from the domestic long range nuclear R and D program can be evaluated by technical IVR collaboration between CEA and KAERI. By using the evaluated computer code and the related thermal hydraulic model, heat transfer enhancement in the outer vessel and in-vessel water injection of the IVR method in the high power reactor can be developed
Availability note (English)
Available from INIS in electronic form; Also available from Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)Files
36095305.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 303 p.
- Report number
- KAERI/RR--2443/2003
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 36095305
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COOLING; CORIUM; FRANCE; HEAT TRANSFER; PWR TYPE REACTORS; REACTOR ACCIDENTS; REPUBLIC OF KOREA; RETENTION; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; ASIA; DEVELOPED COUNTRIES; DEVELOPING COUNTRIES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EUROPE; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WESTERN EUROPE
Optional Information
- Notes
- 42 refs, 21 figs, 6 tabs