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곽영균(Young Kyun Kwack),신창환(Chang Hwan Shin),박주용(Ju Yong Park),이치영(Chi Young Lee),오동석(Dong Seok Oh),전태현(Tae Hyun Chun),인왕기(Wang Kee In) 대한기계학회 2013 대한기계학회 춘추학술대회 Vol.2013 No.12
Dual-cooled nuclear fuel for a Pressurized Water Reactor(PWR) has been introduced for a significant increase in reactor power. The spacer grid was accordingly designed. We studied about hydraulic characteristics of the developed spacer grid. The pressure loss coefficient of a spacer grid is a significant factor of the grid design because it influence the hydraulic performance of the existing fuel assembly. The pressure loss is dependent on the reduction of the flow area and the flow constriction in the spacer region of the dual-cooled nuclear fuel assembly. It is also affected by the presence or absence of coning and chamfering on the spacer grid. The pressure loss coefficients of the spacer grid were compared with three types such as spacer grid with chamfering/coining, with only coining and without chamfering/coining.
CFD를 이용한 이중냉각핵연료의 봉단마개 측면오리피스를 통과하는 내측수로 유동에 대한 연구
곽영균(Young Kyun Kwack),신창환(Chang Hwan Shin),이치영(Chi Young Lee),박주용(Ju Yong Park),전태현(Tae Hyun Chun),인왕기(Wang Kee In) 대한기계학회 2012 대한기계학회 춘추학술대회 Vol.2012 No.11
A bottom end plug with side orifices was developed for sufficient coolant flowing to inner channel in the case of complete entrance blockage of the inner channel. In this event, the flow rate of the inner channel should be greater than 60% of normal condition in order to avoid a damaged condition of the nuclear fuel. The flow rate and the pressure loss coefficient were obtained through simulation analysis of single rod for the end plug. According to the blockage rate of the outer channel, flow pattern and pressure loss coefficient of the side hole were investigated.