A study on the safety assessment methodology of nuclear power plant for beyond design basis accidents = 설계기준초과사고에 대한 원자력발전소의 안전성 평가 방법론에 관한 연구

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dc.contributor.advisorChang, Soon-Heung-
dc.contributor.advisor장순흥-
dc.contributor.authorKang, Dong-Gu-
dc.contributor.author강동구-
dc.date.accessioned2015-04-23T07:09:38Z-
dc.date.available2015-04-23T07:09:38Z-
dc.date.issued2014-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=568686&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/197266-
dc.description학위논문(박사) - 한국과학기술원 : 원자력및양자공학과, 2014.2, [ viii, 103 p. ]-
dc.description.abstractThe concept and assessment approach of nuclear safety in nuclear power plants (NPPs) have been evolved with the technological progress and the lessons learned from the major events. Recently, studies on the integrated approach of deterministic and probabilistic method have been done. In this study, a combined deterministic and probabilistic procedure (CDPP) was proposed for safety assessment of the beyond design basis accidents (BDBAs). In the CDPP, the conditional exceedance probability (CEP) obtained by the best estimate plus uncertainty method acts as go-between deterministic and probabilistic safety assessments, resulting in more reliable values of core damage frequency (CDF) and conditional core damage probability (CCDP). To verify applicability of the methodology, performance of the APR-1400 emergency core cooling system (ECCS) was assessed against large break loss of coolant accident (LOCA), under the premise that LOCAs for any breaks larger than transition break size would be regarded as BDBA. It was confirmed that current APR-1400 ECCS design has capability to mitigate BDB LOCA. In addition, discussions were made for analysis results for allowable NPP changes of emergency diesel generator (EDG) start time extension and power uprating. The safety assessment of OPR-1000 for station blackout (SBO) accident, which is a typical BDBA and important contributor to overall plant risk, was performed by applying the CDPP. It was confirmed that the SBO risk should be reevaluated by eliminating excessive conservatism in existing probabilistic safety assessment (PSA) to meet the targeted CDF and CCDP. By estimating the offsite power restoration time appropriately applying CDPP, the SBO risk was reevaluated, and it was finally confirmed that current OPR-1000 system has capability to mitigate the SBO. Therefore, it is concluded that the proposed CDPP is applicable to safety assessment of BDBAs in NPPs without significant erosion of the safety margin.eng
dc.languageeng-
dc.publisher한국과학기술원-
dc.subjectBeyond design basis accident-
dc.subject발전소정전사고-
dc.subjectECCS 성능평가-
dc.subject설계기준 LOCA 재정의-
dc.subjectCombined deterministic and probabilistic procedure-
dc.subject설계기준초과사고-
dc.subjectCombined deterministic and probabilistic procedure-
dc.subjectDesign basis LOCA redefinition-
dc.subjectECCS performance assessment-
dc.subjectStation blackout-
dc.titleA study on the safety assessment methodology of nuclear power plant for beyond design basis accidents = 설계기준초과사고에 대한 원자력발전소의 안전성 평가 방법론에 관한 연구-
dc.typeThesis(Ph.D)-
dc.identifier.CNRN568686/325007 -
dc.description.department한국과학기술원 : 원자력및양자공학과, -
dc.identifier.uid020095266-
dc.contributor.localauthorChang, Soon-Heung-
dc.contributor.localauthor장순흥-
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