In developing the severe accident management guideline (SAMG), it was highly considered to maintain the integrity of reactor pressure vessel (RPV) as a key strategy aimed to reduce the risk of containment failure and fission product releases into the environment effectively. For the operating nuclear power plants with no dedicated safety features for the severe accident management (SAM), the improvement of the current mitigative strategy in SAMG domain could be one of counter-measures to extend the survival time of RPV. In this study, the effectiveness of the RCS depressurization to delay the RPV survival time with different RCS depressurization rate was evaluated for station blackout (SBO) accident assuming only SIT is available for Uljin unit 1 plant by MELCOR 1.8.5 code. According to the analysis results, it was shown that the conditions for RCS depressurization such as depressurization capacity and the time interval are the key elements to extend the RPV integrity in such a way to earn time for restoring the heat sink in order to prevent the accident propagation to the RPV failure.
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17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4353-6
PROCEEDINGS PAPER
Effectiveness of RCS Depressurization Strategy for Severe Accident Management
Changwook Huh,
Changwook Huh
Korea Institute of Nuclear Safety, Daejeon, Republic of Korea
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Namduk Suh,
Namduk Suh
Korea Institute of Nuclear Safety, Daejeon, Republic of Korea
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Goon-Cherl Park
Goon-Cherl Park
Seoul National University, Seoul, Republic of Korea
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Changwook Huh
Korea Institute of Nuclear Safety, Daejeon, Republic of Korea
Namduk Suh
Korea Institute of Nuclear Safety, Daejeon, Republic of Korea
Goon-Cherl Park
Seoul National University, Seoul, Republic of Korea
Paper No:
ICONE17-75937, pp. 747-753; 7 pages
Published Online:
February 25, 2010
Citation
Huh, C, Suh, N, & Park, G. "Effectiveness of RCS Depressurization Strategy for Severe Accident Management." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance. Brussels, Belgium. July 12–16, 2009. pp. 747-753. ASME. https://doi.org/10.1115/ICONE17-75937
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