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원자로 냉각재 펌프의 과도 상태의 유동 및 열전달 해석 연구
허남건,김성원,유기풍,김승태,Hur, N.,Kim, S.,Yoo, K.-P.,Kim, S. T. 한국유체기계학회 2000 한국유체기계학회 논문집 Vol.3 No.2
The structural analysis of a reactor coolant pump(RCP) of a nuclear power plant is very important for the safety assessment of the plant. Accurate boundary conditions for the heat transfer coefficient are required for reliable thermal stress analysis of the pump casing, especially in transient operations of the pump since the coolant properties are largely dependent on operational conditions. In the present study, a 3D mixed flow type coolant pump was modeled from the RCP drawings and analyzed in the steady state and number of transient flow conditions by using a commercial code STAR-CD. From the result of the computation, it is seen that the average heat transfer coefficients for the cases considered are found to be the suggested values of the manufacturer, Westinghouse Energy System. The unevenness in local heat transfer coefficients, however, is found to be considerable so that the use of average heat transfer coefficients in all boundaries might not give reliable thermal stress predictions.
허남건(N. Hur),윤성영(S. Y. Yoon),조원국(W. K. Cho),김광호(K. H. Kim) 한국자동차공학회 1992 한국자동차공학회 춘 추계 학술대회 논문집 Vol.1992 No.11
Row fields in model engine cooling passages are studied numerically by using TURBO-3D program, a finite volume based 3-D turbulent flow program adopting a general body fitted coordinate system. The effects of exit position on mass flow rate at each gasket hole are examined for a model cooling passage in order to understand the flow distribution inside the water jacket. The results of the present study can be applied to the design of high performance, high reliability engine.
거리-시간 측정에 의한 고정도 타행시험법: Ⅰ.관련이론 및 정밀도 향상방법 고찰
허남건(N.Hur),안이기(I.K.Ahn) 한국자동차공학회 1994 한국자동차공학회 춘 추계 학술대회 논문집 Vol.- No.-
A coast down test method has been used to determine the resistance forces on running vehicle due to the aerodynamic drag, rolling resistance and driveline resistance. Most of the tests. however. are the tests based on the Velocity-Time measurements.<br/> which require a sophisticated velocity measuring device and contains much error by nature. In the present study a coast down test method based on Distance-Time measurements is introduced, which contains the original idea of Russian scientist Prof. Petrushov along with the suggestions for improvement of the accuracy.<br/>
원자로 냉각재 펌프의 과도 상태의 유동 및 열전달 해석 연구
허남건(N. Hur),김성원(S. Kim),유기풍(K.-P. Yoo),김승태(S. T. Kim) 한국유체기계학회 1999 유체기계 연구개발 발표회 논문집 Vol.- No.-
The structural. analysis of a reactor coolant pump(RCP) of a nuclear power plant is very important for the safety assessment of the plant. Accurate boundary conditions for the heat transfer coefficient are required for reliable thermal stress analysis of the pump casing, especially in transient operations of the pump since the coolant properties are largely dependent on operational conditions. In the present study, a 3D mixed flow type coolant pump was modeled from the RCP drawings and analyzed in the steady state and number of transient flow conditions by using a commercial code STAR-CD. From the result of the computation, it is seem that the average heat transfer coefficients for the cases considered are found to be the suggested values of the manufacturer, Westinghouse Energy System. The unevenness in local heat transfer coefficients, however, is found to be considerable so that the use of average heat transfer coefficients in all boundaries might not give reliable thermal stresses.