Flow analyses using RELAP5/ MOD3.3 code have been performed to investigate the occurrence and the effects of steam binding for the LAVA-ERVC experiments. The main objectives of the LAVA-ERVC experiments are investigations of coolability through external reactor vessel cooling according to RPV insulation design. It could be found from the sensitivity studies for the flow path in the annulus of insulation that steam binding could occur in case of the limited steam venting capacity, which is definitely coincident with the LAVA-ERVC experimental results. In case of sufficient flow path for the steam venting, the vessel experienced effective cooling by nucleate boiling heat transfer. And existence of the upper free volume had little effect on occurrence of steam binding in the LAVA-ERVC experiments.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4689-X
PROCEEDINGS PAPER
Flow Analyses Using RELAP/MOD3.3 Code for the Simulant Melt Experiments (LAVA-ERVC) Under the External Reactor Vessel Cooling
Kyoung-Ho Kang,
Kyoung-Ho Kang
Korea Atomic Energy Research Institute, Daejeon, Korea
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Rae-Joon Park,
Rae-Joon Park
Korea Atomic Energy Research Institute, Daejeon, Korea
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Sang-Baik Kim,
Sang-Baik Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
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Hee-Dong Kim
Hee-Dong Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
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Kyoung-Ho Kang
Korea Atomic Energy Research Institute, Daejeon, Korea
Rae-Joon Park
Korea Atomic Energy Research Institute, Daejeon, Korea
Sang-Baik Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
Hee-Dong Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE12-49190, pp. 51-56; 6 pages
Published Online:
November 17, 2008
Citation
Kang, K, Park, R, Kim, S, & Kim, H. "Flow Analyses Using RELAP/MOD3.3 Code for the Simulant Melt Experiments (LAVA-ERVC) Under the External Reactor Vessel Cooling." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 51-56. ASME. https://doi.org/10.1115/ICONE12-49190
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