Published 2011 | Version v1
Miscellaneous

Subchannel and radiation heat transfer analysis of 54-element CANDU-SCWR bundle

  • 1. Xi'an Jiaotong Univ., Shaanxi (China)
  • 2. Atomic Energy of Canada Limited, Chalk River, ON (Canada)

Description

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. (author)

Part of:
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors

Additional details

Publishing Information

Publisher
Canadian Nuclear Society
Imprint Place
Toronto, Ontario (Canada)
ISBN
978-1-926773-02-5
Imprint Title
ISSCWR-5. The 5th International Symposium on Supercritical-Water-Cooled Reactors
Imprint Pagination
90.1 Megabytes
Journal Page Range
[13 p.]

Conference

Title
5. International Symposium on Supercritical-Water-Cooled Reactors
Dates
13-16 Mar 2011
Place
Vancouver, BC (Canada)

Optional Information

Notes
9 refs., 8 tabs., 8 figs.