Evaluation of ENDF/B-IV and Hansen--Roach /sup 233/U cross sections for use in criticality calculations
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), Vol. 65:3
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of Hansen--Roach and ENDF/B-IV cross sections for $sup 233$U criticality calculations
Validation of KENO V.a with ENDF/B-V cross sections for {sup 233}U systems
Related Subjects
NEUTRON REACTIONS
FISSION
URANIUM 233 TARGET
COMPARATIVE EVALUATIONS
CRITICALITY
CROSS SECTIONS
ENERGY DEPENDENCE
HYDROGEN
MODERATING RATIO
ZERO POWER REACTORS
BARYON REACTIONS
CRYOGENIC FLUIDS
ELEMENTS
EXPERIMENTAL REACTORS
FLUIDS
HADRON REACTIONS
NONMETALS
NUCLEAR REACTIONS
NUCLEON REACTIONS
REACTORS
RESEARCH AND TEST REACTORS
TARGETS
652016* - Nuclear Properties & Reactions
A=220 & above
Theoretical- Spontaneous & Induced Fission- (-1987)