Two-stage scaling methodology and direct contact condensation of the core makeup tank in a passive PWR피동 PWR에 있어서 종합적 2단계 스케일 방법 개발과 노심 보충수 탱크의 직접응축에 관한 연구

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Center for Advanced Reactor Research has developed a passive PWR concept called CARR passive reactor 1300MWe(CP-1300). The CP-1300 has new passive safety features. It is necessary to study the performance of the new safety feature and their interactions in order to assess the response of the CP-1300 under postulated accident conditions. Since it is not feasible to build and test a full power prototype system, a scaled-down integral facility is the best alternative. Therefore, it is necessary to have a rational scaling method. To the end, a two-stage scaling method with validation of scaling methodology is developed for a full-pressure full height scaled-down integral test facility simulating a small-break loss-of-coolant accident in the CP-1300. The present scaling method consists of two stages: scaling methodology stage and validation stage of the scaling methodology and a safety analysis code. In the scaling methodology stage, the whole system and the transient scenario are divided into several subsystems and several phases, respectively. For each subsystem potentially important phenomena are identified and ranked in terms of their relative importance for each phase. The global governing equations for each subsystem are nondimensionalized and expressed as nonlinear integral response functions with nondimensional scaling parameters. In the validation stage of code and scaling methodology the system code is assessed to identify little-known phenomena with high relative importance. The direct contact condensation in the CMT is identified as a little-known phenomenon with high importance. The scaling method is validated through comparison of the key parameters of the model and the prototype using the improved code. For full-height full-pressure scaling it is found out that the power scaling ratio is the same as the volume scaling ratio and the area scaling ratio and the horizontal pipes including the surge line are scaled by an exponent 2/5 of the scaling ratio. ...
No, Hee-Cheonresearcher노희천researcher
한국과학기술원 : 원자력공학과,
Issue Date
114519/325007 / 000925258

학위논문(박사) - 한국과학기술원 : 원자력공학과, 1997.2, [ xiv, 150 p. ]


Core makeup tank; Similarity; RELAP5; Direct contact condensation; Scaling; CP-1300; 피동 원자로; 노심보충수 탱크; 유사성; 직접응축; 스케일; Passive PWR

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