Evaluation of ENDF/B-IV and Hansen--Roach /sup 233/U cross sections for use in criticality calculations
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5134318
Eleven /sup 233/U solution critical assemblies spanning an H//sup 233/U ratio range of 40 to 2000 and an unreflected metal /sup 233/U assembly were calculated with ENDF/B-IV and Hansen--Roach cross sections. Results from these calculations are compared with the experimental results and with each other. An increasing disagreement is observed between calculations with ENDF/B and Hansen--Roach data with decreasing H//sup 233/U ratio, indicative of large differences in their intermediate-energy cross sections. The Hansen--Roach cross sections appeared to give reasonably good agreement with experiments over the whole range, whereas the ENDF/B calculations yielded high values for k/sub eff/ on assemblies of low moderation. It is concluded that serious problems exist in the ENDF/B-IV representation of the /sup 233/U cross sections in the intermediate energy range and that further evaluation of this nuclide is warranted. In addition, it is recommended that an experimental program be undertaken to obtain /sup 233/U criticality data at low H//sup 233/U ratios for verification of generalized criticality safety guidelines. 3 figures, 15 tables.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 5134318
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 65:3; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
652016* -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
COMPARATIVE EVALUATIONS
CRITICALITY
CROSS SECTIONS
CRYOGENIC FLUIDS
ELEMENTS
ENERGY DEPENDENCE
EXPERIMENTAL REACTORS
FISSION
FLUIDS
HADRON REACTIONS
HYDROGEN
MODERATING RATIO
NEUTRON REACTIONS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
REACTORS
RESEARCH AND TEST REACTORS
TARGETS
URANIUM 233 TARGET
ZERO POWER REACTORS
A=220 & above
Theoretical-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
COMPARATIVE EVALUATIONS
CRITICALITY
CROSS SECTIONS
CRYOGENIC FLUIDS
ELEMENTS
ENERGY DEPENDENCE
EXPERIMENTAL REACTORS
FISSION
FLUIDS
HADRON REACTIONS
HYDROGEN
MODERATING RATIO
NEUTRON REACTIONS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
REACTORS
RESEARCH AND TEST REACTORS
TARGETS
URANIUM 233 TARGET
ZERO POWER REACTORS