Subchannel and Radiation Heat Transfer Analysis of 54-element CANDU-SCWR Bundle

Abstract

In order to improve the fuel utilization for the CANFLEX-ACR-based bundle under SCWR conditions, a significantly different design with 54-element, has been proposed by Boczar et al. on the CCSC-2010 conference. Their calculation illustrates that the reactor physics feasibility of this design. The present paper analyzed its thermal-hydraulics performance with ATHAS code and CATHENA code. The results show that (1) the proposed bundle can meet the thermal hydraulics criteria well at both BOC and EOC; (2) the bundle can remove 2% full power only through radiation heat transfer to passive moderator.