Thermal Performance of UO_2‐BeO Fuel during a Loss of Coolant Accident

Shripad T. Revankar ； Wenzhong Zhou ； Deepthi Chandramouli

《International Journal of Nuclear Energy Science and Engineering》 5卷 (2015/03) Pp. 1-8

https://doi.org/10.14355/ijnese.2015.05.001

並列摘要

A ceramic‐ceramic composite nuclear fuel consisting of UO_2 as matrix and BeO additive has high thermal conductivity compared to UO_2. In this study performance of UO_2‐BeO composite under transient conditions such as loss of coolant accident (LOCA), using RELAP5 code was carried out. To model performance of this composite, the thermo‐physical properties such as thermal conductivity, specific heat capacity and specific enthalpy were modified to account for the presence of the 10% volume BeO in UO_2. Simulation were carried out with REPLAP5 MOD3.3 code for pressurized water reactor (PWR) with 2% cold leg break to study temperature patterns, pressure, core water level and void fraction. Results from RELAP‐5 showed about 20% drop in average fuel temperatures of UO_2‐BeO composite fuel compared UO_2 fuel.

並列關鍵字

UO_2‐BeO Composite Fuel ； Enhance Thermal Conductivity ； Thermal Performance ； RELAP5 MOD3.3 ； LOCA