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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.
OPR-1000 원자로의 출력증강을 위한 18×18 원통형 핵연료의 열수력적 타당성 평가
신창환(C. H. Shin),김효일(H. I. Kim),인왕기(W. K. In),전태현(T. H. Chun) 대한기계학회 2009 대한기계학회 춘추학술대회 Vol.2009 No.11
The thermal hydraulic analysis of the 18×18 solid fuel assembly has been carried out for the power uprate of OPR-1000. The suggested 18x18 solid fuel assembly has a structural compatibility for reloading to operating PWR reactors of OPR-1000. In the thermal hydraulic analysis, the mixing effect between the neighboring channels has to be carried out in a subchannel analysis. A subchannel analysis code, MATRA has been developed by KAERI. The main parameters for the thermal hydraulic design, such as a pressure drop and DNBR, and the maximum temperature in a fuel pellet have been estimated. The 18×18 solid fuel in the 120% power uprate showed an increased pressure drop and a similar DNBR behavior. The peak temperature in the fuel centerline, however, was slightly higher than that of the 16×16 solid fuel assembly for the normal operation condition. The peak temperature of a fuel pellet in the solid fuel should be seriously considered for increasing power density.
복합혼합날개를 장착한 5×5 봉다발에서 부수로 혼합 및 임계열유속 실험 연구
강경호(K. H. Kang),신창환(C. H. Shin),추연준(Y. J. Choo),윤영중(Y. J. Youn),박종국(J. K. Park),문상기(S. K. Moon),천세영(S. Y. Chun) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
Experiments were performed to determine the thermal (or turbulent) diffusion coefficient (TDC) and to investigate the critical heat flux (CHF) performance in the 5×5 rod bundle with 5 unheated rods which are supported by Hybrid Mixing Vane. In this study, HFC-134a fluid was used as working fluid and the fluid temperature were measured in the important subchannels. To determine the TDC value, the measured fluid temperatures were compared with the predicted values obtained from the MATRA code. The best optimized value of β was found to be 0.02 by considering prediction statistics, i.e., average and standard deviations of the differences between the experimental results and code calculations. Using the best optimized value of β as 0.02, the MATRA code predicts the test results of the fluid temperature within ±1.0 % of error. According to the experimental results on CHF of 5 non-heating guide tubes, the case with non-heating guide tube showed a little good performance in terms of CHF.
이중냉각핵연료에서 봉단마개의 측면오리피스에 대한 손실계수 평가
곽영균(Y.K Kwack),신창환(C.H. Shin),이치영(C.Y. Lee),박주용(I.Y . Park),전태현(T.R Chun),인왕기(W.K. In) 한국전산유체공학회 2012 한국전산유체공학회 학술대회논문집 Vol.2012 No.11
In the case of complete entrance blockage of the inner channel, 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 fad. For this purpose, the pressure loss coefficient of a side orifice of bottom end plug was evaluated. 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