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Effect of In-Vessel Retention Strategies under Postulated SGTR Accidents of OPR1000

Title
Effect of In-Vessel Retention Strategies under Postulated SGTR Accidents of OPR1000
Author
김성중
Issue Date
2015-10
Publisher
Korean Nuclear Society
Citation
Transactions of the Korean Nuclear Society Autumn Meeting Gyeongju, Korea, October 29-30, 2015, Page. 1-5
Abstract
During a steam generator tube rupture (SGTR) accident, direct release of radioactive nuclides into the environment is postulated via bypassing the containment building. This conveys a significant threat in severe accident management (SAM) for minimization of radionuclide release. To mitigate this risk, a numerical assessment of SAM strategies was performed for an SGTR accident of an Optimized Power Reactor 1000 MWe (OPR1000) using MELCOR code. Three in-vessel mitigation strategies were evaluated and the effect of delayed operation action was analyzed. The MELCOR calculations showed that activation of a prompt secondary feed and bleed (F&B) operation using auxiliary feed water and use of an atmospheric dump valve could prevent core degradation. However, depressurization using the safety depressurization system could not prevent core degradation, and the injection of coolant via high-pressure safety injection without the use of reactor coolant system (RCS) depressurization increased fission product release. When mitigation action was delayed by 30 minutes after SAMG entrance, a secondary F&B operation failed in depressurizing the RCS sufficiently, and a significant amount of fission products were released into the environment. These results suggest that appropriate mitigation actions should be applied in a timely manner to achieve the optimal mitigation effects.
URI
http://www.kns.org:8115/kns_files/34/15A-636최원준.pdfhttp://hdl.handle.net/20.500.11754/27979
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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