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박주용(J.Y. Park),신창환(C.H. Shin),이치영(C.Y. Lee),곽영균(Y.K. Kwack),전태현(T.H. Chun),오동석(D.S. Oh),인왕기(W.K. In) 대한기계학회 2012 대한기계학회 춘추학술대회 Vol.2012 No.11
For power uprate of Pressurized Water Reactor(PWR), a dual-cooled annular fuel is being developed in Korea Atomic Energy Research Institute(KAERI). The annular fuel rod is configured to allow the coolant flow through the inner channel as well as outer channel. Since the inner channel is isolated from the neighbor channels unlike the outer channels, an inner channel blockage is one of the principal technical issues of a dual-cooled annular fuel. As a hypothetical event, if the inner channel is completely blocked by the debris, the inner cladding may experience a rapid temperature increase because of no further coolant supply. To complement the entrance blockage of an inner channel a long end plug with side holes is conceptually suggested. The experiment is performed to estimate the flow rate through side holes at the side hole blockage event. In this paper, the inner channel flow rate by the side holes was measured and the loss coefficient of side holes was evaluated.
5X5 핵연료 봉다발에서 지지격자 가공 상태에 따른 압력손실 실험
박주용(J. Y. Park),오동석(D. S. Oh),장석규(S. K. Chang),인왕기(W. K. In) 대한기계학회 2011 대한기계학회 춘추학술대회 Vol.2011 No.10
In Korea Atomic Energy Research Institute(KAERI), it holds a patent right in the U.S.A, Korea, and Japan about development of fuel rod spacer grid for high performance of Pressurized Water Reactor(PWR). We performed experiments about hydraulic characteristics of the developed spacer grid. There were 4 types of spacer grid such as Plain Spacer Grid, Chamfering/Coining, spacer grid with mixing vane without Chamfering/Coining treatment(Mixing Vane), spacer grid with spot welding and chamfering/coining treatment(Mixing Vane_SC), and spacer grid with line welding in Mixing Vane_SC(Mixing Vane_LC). We compared pressure drop coefficient and found the pressure drop coefficient is greatly affected by chamfering/coining treatment and wasnt affected by welding procedure.
곽영균(Y.K. Kwack),신창환(C.H. Shin),이치영(C.Y. Lee),박주용(J.Y. Park),인왕기(W.K. In) 한국전산유체공학회 2012 한국전산유체공학회 학술대회논문집 Vol.2012 No.5
In nuclear reactors, it is important from the point of view of safety to provide adequate cooling of a fuel. Pressure drop and flow distribution are used as key factors. They were obtained by a numerical study of flow in a plate-type nuclear fuel assembly. In the top end fitting, effects of the sudden transition from the circular pipe to the rectangular duct and the fixing bar presence on the flow distribution in each channel were studied. The pressure drops along the assembly were compared with results of experiments.
모바일 환경에서 조선소 패널공정의 생산실행시스템의 개념설계
류철호(C. Ryu),황준하(J. Hwang),김원돈(W.D. Kim),신종계(J.G. Shin),박주용(J.Y.Park),장성록(S.R. Chang) (사)한국CDE학회 2012 한국 CAD/CAM 학회 학술발표회 논문집 Vol.2012 No.2
조선소 공장에서 실시되고 있는 상위 생산정보의 하향식 전달방식에서 벗어나 상위 생산정보와 하위 생산정보의 쌍방향 융합을 통한 작업 생산성 향상, 작업자의 안전관리 향상, 조선소의 물류비용 절감을 위해, 스마트조선소의 구축을 목표로, 시간과 공간에 제약을 받지 않는 조선생산실행업무가 가능하도록 하는 스마트워크 기반 조선생산실행시스템의 개념설계를 제안한다. 스마트 조선생산실행시스템의 기능과 주요 특징, 주요 구성요소를 정의하고 조선생산실행시스템이 시간과 공간의 제약을 받지 않도록 무선 메쉬망과 Application 가상화 시스템의 구축을 통해 모바일 환경을 지원하게 되도록 시스템 아키텍쳐가 구성된다. 현재는 모바일 환경에서 조선소 패널공정의 스마트 생산실행시스템에 대한 설계가 진행 중에 있으며, 설계를 완료하고 사례 시스템의 시제품 구현을 진행하면서 시스템의 기능 및 아키텍쳐를 검증하고 스마트 조선생산실행시스템을 전사적으로 확장해야 할 것이다.
봉간격이 좁은 봉다발에서 압력손실의 실험 및 전산해석 평가
신창환(C.H. Shin),이치영(C.Y. Lee),박주용(J.Y. Park),오동석(D.S. Oh),인왕기(W.K. In) 한국전산유체공학회 2011 한국전산유체공학회 학술대회논문집 Vol.2011 No.11
A dual-cooled annular nuclear fuel has been introduced for a significant increase in reactor power. The KAERI has been researching the development of a dual-cooled annular fuel for a power increase in an optimized PWR in Korea, OPR-1000. The pitch-to-diameter ratio of the annular fuel assembly is decreased in order to maintain the fuel amount ratio within the same assembly size as the solid fuel assembly. In the tight lattice rod bundle, a pressure loss for the rod friction may be definitely different from that in the conventional solid fuel assembly. In this study, the friction loss of the 4x4 or 5x5 bare rod bundles without the obstacles such as the spacer grids is measured for the pitch-to-diameter 1.08 and 1.35, respectively. The measured results are compared with the general correlations for the conventional rod bundle. CFD studies are performed to investigate the friction pressure loss for the simulated single rod geometry and the spacer grid effects in the rod bundle is estimated in the view of a friction loss for a rod.