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dc.contributor.author김성중-
dc.date.accessioned2018-03-24T06:17:24Z-
dc.date.available2018-03-24T06:17:24Z-
dc.date.issued2014-02-
dc.identifier.citationJournal of Nuclear Science and Technology, Volume 51, 2014 - Issue 2, Pages 181-195en_US
dc.identifier.issn0022-3131-
dc.identifier.issn1881-1248-
dc.identifier.urihttps://www.tandfonline.com/doi/abs/10.1080/00223131.2014.854713-
dc.identifier.urihttp://hdl.handle.net/20.500.11754/51849-
dc.description.abstractSevere accident analysis for Small Break (SB), Middle Break (MB), and Large Break (LB) Loss-Of-Coolant Accident (LOCA), Station Black Out (SBO), Total Loss-Of-Feed-Water (TLOFW) was performed and effectiveness of Reactor Coolant System (RCS) depressurization strategies of OPR1000 was analyzed using MELCOR 1.8.6 code. Required injection flow rate has been derived using Core Exit Temperature (CET) information obtained from MELCOR calculation and a simple model and corresponding coolability map have been suggested to assist effective operator action. The depressurization strategies using secondary Atmospheric Dump Valve (ADV) for SBLOCA, pressurizer Safety Depressurization System (SDS) for SBO and TLOFW were introduced in 5 min since the initiation of Severe Accident Management Guidance (SAMG). Respective mitigation strategy employed leads to significant delay of the reactor pressure vessel failure and RCS pressure at Reactor Pressure Vessel (RPV) failure was lower than the SAMG target pressure of 2.86 MPa. Thus, possibility of High Pressure Melt Ejection (HPME) and impair of containment building is expected to avoid effectively. Using CET information obtained from MELCOR calculation, a simple model and a coolability map for the required injection flow rate were developed for recovery of core coolability. It is suggested that the coolability map based on MELCOR calculation results may provide decisive and intuitive information to operators for more effective safety management.en_US
dc.description.sponsorshipThis work was supported by the National Research Foundation of Korea (NRF) grant funded by the Korea government (MSIP) [grant number NRF-2013M2A8A4027332], [grant number NRF-2012M2A8A4025885].en_US
dc.language.isoenen_US
dc.publisherTaylor and Francis Onlineen_US
dc.subjectaccident managementen_US
dc.subjectsevere accidenten_US
dc.subjectin-vessel retentionen_US
dc.subjectLOCAen_US
dc.subjectLWR-type reactoren_US
dc.subjectPWR-type reactoren_US
dc.titleValidation of RCS depressurization strategy and core coolability map for independent scenarios of SBLOCA, SBO, and TLOFWen_US
dc.typeArticleen_US
dc.relation.no2-
dc.relation.volume51-
dc.identifier.doi10.1080/00223131.2014.854713-
dc.relation.page181-195-
dc.relation.journalJOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY-
dc.contributor.googleauthorLee, Seongnyeon-
dc.contributor.googleauthorHa, Kwang Soon-
dc.contributor.googleauthorKim, Hwan-Yeol-
dc.contributor.googleauthorKim, Sung Joong-
dc.relation.code2014034025-
dc.sector.campusS-
dc.sector.daehakCOLLEGE OF ENGINEERING[S]-
dc.sector.departmentDEPARTMENT OF NUCLEAR ENGINEERING-
dc.identifier.pidsungjkim-
Appears in Collections:
COLLEGE OF ENGINEERING[S](공과대학) > NUCLEAR ENGINEERING(원자력공학과) > Articles
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