scholarly journals Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics Executive Summary

2014 ◽  
Author(s):  
Shannon Bragg-Sitton
Keyword(s):  
Performance Metrics ◽  
Light Water Reactor ◽  
Reactor Accident ◽  
Fuel Performance ◽  
Executive Summary ◽  
Light Water ◽  
Water Reactor ◽  
Advanced Fuels

scholarly journals Advanced Fuels Campaign Light Water Reactor Accident Tolerant Fuel Performance Metrics

2014 ◽  
Author(s):  
Brad Merrill ◽  
Melissa Teague ◽  
Robert Youngblood ◽  
Larry Ott ◽  
Kevin Robb ◽  
...  
Keyword(s):  
Performance Metrics ◽  
Light Water Reactor ◽  
Reactor Accident ◽  
Fuel Performance ◽  
Light Water ◽  
Water Reactor ◽  
Advanced Fuels

Multiphysics coupled modeling of light water reactor fuel performance

2016 ◽  
Vol 91 ◽  
pp. 38-48 ◽  
Author(s):  
Rong Liu ◽  
Andrew Prudil ◽  
Wenzhong Zhou ◽  
Paul K. Chan
Keyword(s):  
Reactor Fuel ◽  
Light Water Reactor ◽  
Coupled Modeling ◽  
Fuel Performance ◽  
Light Water ◽  
Water Reactor

scholarly journals Planning support document for the EPRI Light Water Reactor Fuel Performance program

1977 ◽  
Author(s):  
J. T.A. Roberts ◽  
F. E. Gelhaus ◽  
H. Ocken ◽  
S. T. Oldberg ◽  
G. R. Thomas
Keyword(s):  
Reactor Fuel ◽  
Light Water Reactor ◽  
Fuel Performance ◽  
Light Water ◽  
Water Reactor ◽  
Planning Support

Multiphysics Modeling of Thorium-Based (Th, U)O2 and (Th, Pu)O2 Fuel Performance in a Light Water Reactor

2018 ◽  
Author(s):  
Rong Liu ◽  
Jie-Jin Cai ◽  
Wen-Zhong Zhou ◽  
Ye Wang
Keyword(s):  
Fuel Burnup ◽  
Light Water Reactor ◽  
Gas Release ◽  
Fuel Performance ◽  
Light Water ◽  
Water Reactor ◽  
Fission Gas ◽  
Fission Gas Release ◽  
Centerline Temperature ◽  
Plenum Pressure

ThO2 has been considered as a possible replacement for UO2 fuel for future generation of nuclear reactors, and thorium-based mixed oxide (Th-MOX) fuel performance in a light water reactor was investigated due to better neutronics properties and proliferation resistance compared to conventional UO2 fuel. In this study, the thermal, mechanical properties of Th0.923U0.077O2 and Th0.923Pu0.077O2 fuel were reviewed with updated properties and compared with UO2 fuel, and the corresponding fuel performance in a light water reactor under normal operation conditions were also analyzed and compared by using CAMPUS code. The Th0.923U0.077O2 fuel were found to decrease the fuel centerline temperature, while Th0.923Pu0.077O2 fuel was found to have a bit higher fuel centerline temperature than UO2 fuel at the beginning of fuel burnup, and then much lower fuel centerline than UO2 fuel at high fuel burnup. The Th0.923U0.077O2 fuel was found to have lowest fuel centerline temperature, fission gas release and plenum pressure. While the Th0.923Pu0.077O2 fuel was found to have earliest gap closure time with much less fission gas release and much lower plenum pressure compared to UO2 fuel. So the fuel performance could be expected to be improved by applying Th0.923U0.077O2 and Th0.923Pu0.077O2 fuel.

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