DC Field | Value | Language |
---|---|---|
dc.contributor.advisor | Chung, Kun-Mo | - |
dc.contributor.advisor | Ra, Jung-Woong | - |
dc.contributor.advisor | 정근모 | - |
dc.contributor.advisor | 나정웅 | - |
dc.contributor.author | Pyo, Sam-Soo | - |
dc.contributor.author | 표삼수 | - |
dc.date.accessioned | 2011-12-14T02:18:40Z | - |
dc.date.available | 2011-12-14T02:18:40Z | - |
dc.date.issued | 1976 | - |
dc.identifier.uri | http://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=62016&flag=dissertation | - |
dc.identifier.uri | http://hdl.handle.net/10203/39433 | - |
dc.description | 학위논문(석사) - 한국과학기술원 : 전기 및 전자공학과, 1976.2, [ v, 100 p. ] | - |
dc.description.abstract | The general characteristics of the loss of coolant accident (LOCA) for pressurized water reactor systems(PWR) is reviewed and the emergency core cooling system(ECCS) of the ``$\mbox{\underline{Ko Ri}}$ nuclear power plant unit 1`` and its time response characteristics against LOCA are investigated. For the simulation analysis, a modified version of ``RELAP-4``, a computer program for the transient analysis of PWR following LOCA is run using the parameters of ECCS of the ``$\mbox{\underline{Ko Ri}}$ nuclear power plant unit 1``. In this computation, a cold- leg double-ended severance rupture is postulated. The result of the simulation computation is compared with those of similar studies for other PWR systems. | eng |
dc.language | eng | - |
dc.publisher | 한국과학기술원 | - |
dc.title | (A) simulation stydy of the emergency core cooling system for the "Ko Ri nuclear power plant | - |
dc.title.alternative | 고리 원자력 발전소 비상 냉각 장치의 시뮬레이션 연구 | - |
dc.type | Thesis(Master) | - |
dc.identifier.CNRN | 62016/325007 | - |
dc.description.department | 한국과학기술원 : 전기 및 전자공학과, | - |
dc.identifier.uid | 000741138 | - |
dc.contributor.localauthor | Chung, Kun-Mo | - |
dc.contributor.localauthor | Ra, Jung-Woong | - |
dc.contributor.localauthor | 정근모 | - |
dc.contributor.localauthor | 나정웅 | - |
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