지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
커뮤니티
연구자들이 자신의 연구와 전문성을 널리 알리고, 새로운 협력의 기회를 만들 수 있는 네트워킹 공간이에요.
초록· 키워드
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Objective: The purpose of this study is to select the methodology for SMR HRA which has characteristics that are different from existing nuclear power plants and digitalbased plants.
Background: We must assure safety to preoccupy export of technology to developing countries or countries interested in nuclear application. And we can be an advanced country in nuclear technology by securing original technology in the field of SMR such as SMART.
Method: THERP, which is the most representative HRA methodology among all, and RARA, which is the latest HRA methodology. This study compared and evaluated THERP and RARA.
Results: As a result of applying THERP and RARA methodologies which are based on LOCA EOG task analysis result, this research concluded that RARA has higher personal errors than THERP.
Conclusion: This study needs validation for LOCA, emergency operations, normal and abnormal scenarios since HRA methodology was only focused on LOCA scenario.
Application: The results of this study can apply as base line data when designing MMIS, which is the main control room of SMART, and when building a simulator.
Background: We must assure safety to preoccupy export of technology to developing countries or countries interested in nuclear application. And we can be an advanced country in nuclear technology by securing original technology in the field of SMR such as SMART.
Method: THERP, which is the most representative HRA methodology among all, and RARA, which is the latest HRA methodology. This study compared and evaluated THERP and RARA.
Results: As a result of applying THERP and RARA methodologies which are based on LOCA EOG task analysis result, this research concluded that RARA has higher personal errors than THERP.
Conclusion: This study needs validation for LOCA, emergency operations, normal and abnormal scenarios since HRA methodology was only focused on LOCA scenario.
Application: The results of this study can apply as base line data when designing MMIS, which is the main control room of SMART, and when building a simulator.
목차
1. Introduction
2. Consideration of HRA Existing Methodologies
3. Task Analysis for SMART HRA Method Selection
4. Result
5. Discussion/Conclusion
References
참고문헌 (39)
참고문헌 신청
1. [기타자료] - ABB-CE / 1993 / System 80+ PRA
2. [학술지(정기간행물)] - 차우창 / 2009 / 운전원 콘솔의 인간공학적 설계요소 추출을 위한디지털과 아날로그 시스템 환경의 비교연구 / 산업경영시스템학회지 32 (2) : 140 ~ 146
3. [학술대회논문] - Dave Ciesielski / 2004 / Qualified Software Tools For Safety I&C Applications / NPIC&HMIT 2004
4. [학술지(정기간행물)] - Dougherty, E. / 1992 / Human Reliability Analysis - Where should sthou turn? / Journal of Reliability Engineering and System Safety 29 : 283 ~ 299
5. [단행본] - Doughtery, E.M. / 1988 / Human Reliability Analysis: A System Engineering Approach With Nuclear Power Plant Applications / John Wiley & Sons
2. [학술지(정기간행물)] - 차우창 / 2009 / 운전원 콘솔의 인간공학적 설계요소 추출을 위한디지털과 아날로그 시스템 환경의 비교연구 / 산업경영시스템학회지 32 (2) : 140 ~ 146
3. [학술대회논문] - Dave Ciesielski / 2004 / Qualified Software Tools For Safety I&C Applications / NPIC&HMIT 2004
4. [학술지(정기간행물)] - Dougherty, E. / 1992 / Human Reliability Analysis - Where should sthou turn? / Journal of Reliability Engineering and System Safety 29 : 283 ~ 299
5. [단행본] - Doughtery, E.M. / 1988 / Human Reliability Analysis: A System Engineering Approach With Nuclear Power Plant Applications / John Wiley & Sons
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UCI(KEPA) : I410-ECN-0101-2015-500-001264559