Table of Contents
International Journal of Nuclear Energy
Volume 2014 (2014), Article ID 751070, 9 pages
http://dx.doi.org/10.1155/2014/751070
Research Article

Development of Thermal Models and Analysis of UO2-BeO Fuel during a Loss of Coolant Accident

1School of Nuclear Engineering, Purdue University, West Lafayette, IN 47907, USA
2Division of Advanced Nuclear Engineering, POSTECH, Pohang, Gyeongbuk 784-790, Republic of Korea

Received 29 June 2014; Revised 22 July 2014; Accepted 5 August 2014; Published 26 August 2014

Academic Editor: Adem Acir

Copyright © 2014 Deepthi Chandramouli and Shripad T. Revankar. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Abstract

Small fraction of high conductivity BeO in UO2 fuel significantly improves thermal conductivity and also affects the overall performance of the fuel during steady state operation and during transients. In this study, performance of UO2-BeO composite under transient conditions such as loss of coolant accident (LOCA), using FRAPTRAN (fuel rod analysis program transient), was carried out. The subroutines in FRAPTRAN code that calculate key thermophysical properties such as thermal conductivity, specific heat capacity, and specific enthalpy were modified to account for the presence of the BeO in UO2. The fuel performance parameters like gas gap pressure, energy stored in fuel, and temperature profiles were studied. The simulation results showed reductions in fuel centerline temperatures and lower temperature drop across fuel rod cross-section under normal fuel operations. It was observed that there was reduction in gas gap pressure and energy stored in fuel. Transient conditions involving cladding rupture were investigated and important performance parameters such as cladding strain were studied. During these transients, the addition of BeO to UO2 fuel seems beneficiary.