Monte Carlo Calculated Material Bucklings of 3 wt% Enriched Uranium-Water Lattices with Uranium in the Water Moderator
- Battelle Pacific Northwest Labs., Richland, WA (United States)
A difficult technical problem of importance in processing reactor fuels involves criticality of uranium rods in uranium solution (problem of uranium dissolution). The material buckling for such a mixture is difficult to evaluate by standard methods. MONTE CARLO techniques were used to evaluate the material bucklings for 3 wt% enriched uranium water lattices with various uranium concentrations in the moderator. The maximum material buckling that may be obtained under optimum geometry conditions was calculated to occur with uranium absent from the moderator. These results apply to solid rods only since tubular fuel elements were not considered.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); US Atomic Energy Commission (AEC)
- DOE Contract Number:
- AT(45-1)-1830
- NSA Number:
- NSA-19-047954
- OSTI ID:
- 4621104
- Report Number(s):
- BNWL-127
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BUCKLING
Buckling
CRITICALITY
Criticality
Enriched Uranium
Enriched Uranium-Water Lattices
FUEL ELEMENTS
LATTICES
Lattices
MODERATORS
MONTE CARLO METHOD
Moderators
Monte Carlo Method
NUMERICALS
Nuclear Criticality Safety Program (NCSP)
RODS
Safety
URANIUM
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22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BUCKLING
Buckling
CRITICALITY
Criticality
Enriched Uranium
Enriched Uranium-Water Lattices
FUEL ELEMENTS
LATTICES
Lattices
MODERATORS
MONTE CARLO METHOD
Moderators
Monte Carlo Method
NUMERICALS
Nuclear Criticality Safety Program (NCSP)
RODS
Safety
URANIUM
WATER MODERATOR
Water Moderator