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Development of Plenum Temperature Model for Accident Analysis

[+] Author Affiliations
Wenjie Li

Science and Technology on Reactor System Design Technology Laboratory, Shuangliu, China

Yongjun Jiao, Bingde Chen

Nuclear Power Institute of China, Shuangliu, China

Paper No. ICONE24-60330, pp. V001T02A014; 8 pages
  • 2016 24th International Conference on Nuclear Engineering
  • Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors
  • Charlotte, North Carolina, USA, June 26–30, 2016
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5001-5
  • Copyright © 2016 by ASME


Plenum temperature is an important parameter in the calculation of LWR fuel rod internal pressure, since plenum contributes over 40% of free volume in typical LWR fuel design. In many fuel performance codes the plenum temperature are determined in a simple and empirical method. There is a concern about whether such a simple method can properly reflect the temperature variation during fast transients and accident conditions. Therefore, a detailed simulation of heat transfer process in plenum based on COMSOL Multiphysics software was performed to give a fine resolution of temperature and to investigate the heat transfer mechanisms. Since the COMSOL application is a stand-alone model, a new plenum temperature model which can be coupled with fuel performance code was also developed. Finally the validation of the new plenum temperature model is performed by comparing its results with COMSOL model and FUPAC code.

Copyright © 2016 by ASME



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