An evaluation of the ex-vessel core catcher system of a sample advanced light water reactor was presented. The core catcher was designed to cool down the molten corium through a combined injection of water and gas from the bottom of the molten corium, which could be effective in the reduction of rapid steam generation and in the suppression of a steam explosion. By using the MELCOR code, a scenario analysis was performed for a representative severe accident scenario of the ALWR, that is, the 6-inches large break loss of coolant accident without safe injection. The corium spreading regime was estimated by an asymptotic calculation. The composition of the molten corium, the decay power level, and the sacrificial concrete ablation depth with time were obtained by a sacrificial concrete ablation analysis. The corium cooling history in the core catcher during the coolant injection was evaluated to calculate the temporal steam generation rate by considering an energy conservation equation. These were used as the major inputs for the temporal calculations of containment pressure which was performed by using the GASFLOW code. Several cases with change of water and gas injection rates were calculated. It was confirmed that the bottom water injection system was an effective corium cooling method in the ex-vessel core catcher to preclude a possible steam explosion and to suppress the quick release of steam.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4931-6
PROCEEDINGS PAPER
An Evaluation of a Direct Corium Cooling Method for the Ex-Vessel Melt Retention
Kwang Soon Ha,
Kwang Soon Ha
Korea Atomic Energy Research Institute, Daejeon, Korea
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Hwan Yeol Kim,
Hwan Yeol Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
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Jongtae Kim,
Jongtae Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
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Jong Hwa Park
Jong Hwa Park
Korea Atomic Energy Research Institute, Daejeon, Korea
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Kwang Soon Ha
Korea Atomic Energy Research Institute, Daejeon, Korea
Hwan Yeol Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
Jongtae Kim
Korea Atomic Energy Research Institute, Daejeon, Korea
Jong Hwa Park
Korea Atomic Energy Research Institute, Daejeon, Korea
Paper No:
ICONE18-29141, pp. 359-367; 9 pages
Published Online:
April 8, 2011
Citation
Ha, KS, Kim, HY, Kim, J, & Park, JH. "An Evaluation of a Direct Corium Cooling Method for the Ex-Vessel Melt Retention." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 3. Xi’an, China. May 17–21, 2010. pp. 359-367. ASME. https://doi.org/10.1115/ICONE18-29141
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