SUBCHANNEL AND RADIATION HEAT TRANSFER ANALYSIS OF 54-ELEMENT CANDU-SCWR BUNDLE
The 5th International Symposium on SuperCritical Water-cooled Reactors - 2011 March 13-16


Presented at:
The 5th International Symposium on SuperCritical Water-cooled Reactors
2011 March 13-16
Location:
Vancouver,Canada
Session Title:
Fuel Design (II)

Authors:
Jianqiang Shan (Xi'an Jiaotong University)
Yang Jiang (Xi'an Jiaotong University)
Laurence Leung (Atomic Energy of Canada Limited)
  

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.

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