Evaluation of Fission Gas Release in High-Burnup Light Water Reactor Fuel Rods

1993 ◽  
Vol 102 (2) ◽  
pp. 210-231 ◽  
Author(s):  
John O. Barner ◽  
Mitchel E. Cunningham ◽  
Maxwell D. Freshley ◽  
Donald D. Lanning
Keyword(s):  
Reactor Fuel ◽  
Light Water Reactor ◽  
Gas Release ◽  
Fuel Rods ◽  
Light Water ◽  
Water Reactor ◽  
Fission Gas ◽  
High Burnup ◽  
Fission Gas Release

scholarly journals Initial Results from Dissolution Testing of Various Air-Oxidized Spent Fuels

1993 ◽  
Vol 333 ◽  
Author(s):  
W. J. Gray ◽  
L. E. Thomas
Keyword(s):  
Light Water Reactor ◽  
Dissolution Testing ◽  
Gas Release ◽  
Test Results ◽  
Light Water ◽  
Water Reactor ◽  
Dissolution Tests ◽  
Fission Gas ◽  
Fission Gas Release ◽  
Initial Results

ABSTRACTFlowthrough dissolution tests have been conducted on two different light-water-reactor spent fuels oxidized to U4O9+x or U3O8. Oxidation had a bigger impact on the dissolution of U and a smaller impact on the dissolution of Tc from the fuel with higher burnup and higher fission gas release. Possible reasons for the observed differences in test results are discussed, but clarification awaits results from tests on other fuels, which are in progress.

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.

On the behaviour of cesium and iodine in light water reactor fuel rods

1981 ◽  
Vol 97 (1-2) ◽  
pp. 157-164 ◽  
Author(s):  
M. Peehs ◽  
R. Manzel ◽  
W. Schweighofer ◽  
W. Haas ◽  
E. Haas ◽  
...  
Keyword(s):  
Reactor Fuel ◽  
Light Water Reactor ◽  
Fuel Rods ◽  
Light Water ◽  
Water Reactor

A Stress Corrosion Cracking Model for Pellet-Cladding Interaction Failures in Light-Water Reactor Fuel Rods

2009 ◽  
pp. 285-285-21 ◽  
Author(s):  
JTA Roberts ◽  
RL Jones ◽  
D Cubicciotti ◽  
AK Miller ◽  
HF Wachob ◽  
...  
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Reactor Fuel ◽  
Light Water Reactor ◽  
Fuel Rods ◽  
Light Water ◽  
Water Reactor

Liquid-Metal-Bonded Gap for Light Water Reactor Fuel Rods

1999 ◽  
Vol 128 (3) ◽  
pp. 300-312 ◽  
Author(s):  
Yeon Soo Kim ◽  
D. R. Olander ◽  
S. K. Yagnik
Keyword(s):  
Liquid Metal ◽  
Reactor Fuel ◽  
Light Water Reactor ◽  
Fuel Rods ◽  
Light Water ◽  
Water Reactor

Neutron Radiography of Light Water Reactor Fuel Rods at the High Flux Reactor Petten

1987 ◽  
pp. 381-393 ◽  
Author(s):  
J. Bakker ◽  
A. Baritello ◽  
J. Bordo ◽  
J. F. W. Markgraf ◽  
H. P. Leeflang ◽  
...  
Keyword(s):  
Neutron Radiography ◽  
Reactor Fuel ◽  
Light Water Reactor ◽  
High Flux ◽  
Fuel Rods ◽  
High Flux Reactor ◽  
Light Water ◽  
Water Reactor ◽  
Flux Reactor
Sign in / Sign up

Export Citation Format

Share Document