TY - GEN
T1 - Development of plenum temperature model for accident analysis
AU - Li, Wenjie
AU - Jiao, Yongjun
AU - Chen, Bingde
N1 - Publisher Copyright:
Copyright © 2016 by ASME.
PY - 2016
Y1 - 2016
N2 - 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.
AB - 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.
UR - https://www.scopus.com/pages/publications/84995793693
U2 - 10.1115/ICONE24-60330
DO - 10.1115/ICONE24-60330
M3 - 会议稿件
AN - SCOPUS:84995793693
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I and C, Digital Controls, and Influence of Human Factors
PB - American Society of Mechanical Engineers (ASME)
T2 - 2016 24th International Conference on Nuclear Engineering, ICONE 2016
Y2 - 26 June 2016 through 30 June 2016
ER -