发布时间：2025-04-30

论文名称：Subchannel analysis of CANDU-SCWR fuel

发表刊物：Progress in Nuclear Energy

摘要：A cooperative study has been initiated at Xi’an Jiaotong University (XJTU) with Atomic Energy of Canada
Limited (AECL) to develop a subchannel code ATHAS for preliminary analyses of flow and enthalpy
distributions and cladding temperatures in CANDU fuel at super-critical water conditions. The code is
applicable for transient and steady-state calculations. Then the paper uses the ATHAS code to analyze
CANDU-SCWR which is operating at 25.0 MPa pressure. The results show that the maximum claddingsurface
temperature of CANFLEX bundle is 804.1 C, which is below the limit of design, and it is appropriate
for use in the CANDU super-critical water-cooled reactor (SCWR) based on heat-transfer analysis.

合写作者：Changying Li, Jianqiang Shan, Laurence K.H. Leung

卷号：51 (2009)

页面范围：799–804

是否译文：否

发表时间：2009-08-11