Date:

2025-04-30

Title of Paper:

Subchannel analysis of CANDU-SCWR fuel

Journal:

Progress in Nuclear Energy

Summary:

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.

Co-author:

Changying Li, Jianqiang Shan, Laurence K.H. Leung

Volume:

51 (2009)

Page Number:

799–804

Translation or Not:

No

Date of Publication:

2009-08-11