Behavior of Breached Light Water Reactor Spent Fuel Rods in Air and Inert Atmospheres at 229°C

1985 ◽  
Vol 69 (1) ◽  
pp. 55-71 ◽  
Author(s):  
Robert E. Einziger ◽  
James A. Cook
Keyword(s):  
Light Water Reactor ◽  
Spent Fuel ◽  
Fuel Rods ◽  
Light Water ◽  
Water Reactor

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

scholarly journals Storage of LWR (light-water-reactor) spent fuel in air

1989 ◽  
Author(s):  
L.E. Thomas ◽  
L.A. Charlot ◽  
J.E. Coleman ◽  
R.W. Knoll
Keyword(s):  
Light Water Reactor ◽  
Spent Fuel ◽  
Light Water ◽  
Water Reactor

scholarly journals Investigation on Aerosol Pool Scrubbing Model During Severe Accidents

2021 ◽  
Vol 9 ◽  
Author(s):  
L. W. He ◽  
Y. X. Li ◽  
Y. Zhou ◽  
S. Chen ◽  
L. L. Tong ◽  
...  
Keyword(s):  
Bubble Size ◽  
Nuclear Power ◽  
Predictive Ability ◽  
Decontamination Factor ◽  
Light Water Reactor ◽  
Severe Accident ◽  
Spent Fuel ◽  
Analysis Model ◽  
Light Water ◽  
Water Reactor

During a nuclear power plant severe accident, discharging gas mixture into the spent-fuel pool is an alternative containment depressurization measurement through which radioactive aerosols can be scrubbed. However, it is necessary to develop a code for analyzing the decontamination factor of aerosol pool scrubbing. This article has established the analysis model considering key aerosol pool scrubbing mechanisms and introduced the Akita bubble size relationship. In addition, a code for evaluating the decontamination factor of aerosol pool scrubbing was established. The Advanced Containment Experiment and Light Water Reactor Advanced Containment Experiment were simulated with the code considering different bubble sizes of the Akita model and MELCOR default value to verify the suitability of the Akita bubble size model for simulating aerosol pool scrubbing. Furthermore, the simulation results were compared with the results analyzed by MELCOR code and COCOSYS code from literature, and equivalent predictive ability was observed. In addition, a sensitivity analysis on bubble size was conducted, and the contribution of different behaviors and mechanisms has been discussed. Finally, the bubble breakup equation was revised and verified with the conditions of the multi-hole bubbler in the Advanced Containment Experiment and Light Water Reactor Advanced Containment Experiment.

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
Sign in / Sign up

Export Citation Format

Share Document