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〈학술논문〉 초임계압수 냉각로 노심열수력 특성 예비평가
변충섭(C. S. Byun),최훈(H. Choi),이광호(K. H. Lee),배성만(S.M. Bae),김용배(Y. B. Kim),홍승열(S. Y. Hong) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5
Supercritical water-cooled reactors (SCWR) are among the most promising advanced nuclear systems because of their high thermal efficiency (about 45%) with superior thermodynamic conditions and considerable plant simplification compared to light water reactor. Because of dramatic change of thermal properties of supercritical water, the core thermal-hydraulic analysis is important to evaluate the feasibility of the SCWR. This study contributes to setup the software tool for sub-channel analysis and to validate it. The VIPRE code was adapted for the analysis of reactor cores with supercritical water and the calculation module for thermal properties of super critical water was added in it, and new heat transfer correlation that are considered adequate for SCWR analysis were implemented in the code. For validating, 1/4 core model for SCWR concept using for the feasibility study in Idaho National Laboratory was developed. The preliminary evaluation shows the revised software code to be working well and the characteristics of supercritical water in the core channel to be predicted well.