Subchannel analysis of CANDU-SCWR fuel |
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| Authors: | Changying Li Jianqiang Shan Laurence K.H. Leung |
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| Affiliation: | aState Key Laboratories of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an Shaanxi 710049, China;bChina Nuclear Power Technology Research Institute, Guangdong Shenzhen 518026, China;cChalk River Laboratories, Atomic Energy of Canada Limited, Chalk River, Ontario, Canada K0J 1J0 |
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| Abstract: | 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 cladding-surface 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. |
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| Keywords: | Subchannel CANDU-SCWR ATHAS CANFLEX |
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