(A) simulation stydy of the emergency core cooling system for the "Ko Ri nuclear power plant고리 원자력 발전소 비상 냉각 장치의 시뮬레이션 연구

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dc.contributor.advisorChung, Kun-Mo-
dc.contributor.advisorRa, Jung-Woong-
dc.contributor.advisor정근모-
dc.contributor.advisor나정웅-
dc.contributor.authorPyo, Sam-Soo-
dc.contributor.author표삼수-
dc.date.accessioned2011-12-14T02:18:40Z-
dc.date.available2011-12-14T02:18:40Z-
dc.date.issued1976-
dc.identifier.urihttp://library.kaist.ac.kr/search/detail/view.do?bibCtrlNo=62016&flag=dissertation-
dc.identifier.urihttp://hdl.handle.net/10203/39433-
dc.description학위논문(석사) - 한국과학기술원 : 전기 및 전자공학과, 1976.2, [ v, 100 p. ]-
dc.description.abstractThe 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.languageeng-
dc.publisher한국과학기술원-
dc.title(A) simulation stydy of the emergency core cooling system for the "Ko Ri nuclear power plant-
dc.title.alternative고리 원자력 발전소 비상 냉각 장치의 시뮬레이션 연구-
dc.typeThesis(Master)-
dc.identifier.CNRN62016/325007-
dc.description.department한국과학기술원 : 전기 및 전자공학과, -
dc.identifier.uid000741138-
dc.contributor.localauthorChung, Kun-Mo-
dc.contributor.localauthorRa, Jung-Woong-
dc.contributor.localauthor정근모-
dc.contributor.localauthor나정웅-
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EE-Theses_Master(석사논문)
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