Fast and Thermal Data Testing of U-233 Critical Assemblies
Conference
·
OSTI ID:7815
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); ORNL
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Data testing has been performed for U-233 fast and thermal benchmarks. Results are presented for both ENDF/B-VI and a modified JENDL-3.2 evaluation. The revised JENDL-3.2 evaluation is summarized and comparisons with ENDF/B-VI and measured values are discussed. Calculated results using both cross section sets are presented for 10 fast benchmarks (reflected and unreflected U-233 metal) and 38 thermal benchmarks (uranyl-nitrate solutions in spherical and cylindrical geometry). Using the revised JENDL-3.2 evaluation, very good results are obtained for the calculated k-effs for almost all of the 48 benchmarks considered in this study. Possible future work is discussed briefly.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Office of Environmental Management (EM)
- DOE Contract Number:
- AC05-96OR22464
- OSTI ID:
- 7815
- Report Number(s):
- ORNL/CP-103003; ON: DE00007815
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
Benchmarks
Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications
Evaluated Nuclear Data File (ENDF)
Evaluation
Fast Benchmarks
Fast Fission
JENDL-3.2 Evaluation
Nuclear Criticality Safety Program (NCSP)
Nuclear Data Collections
Thermal Benchmarks
Thermal Fission
Uranium 233
Uranyl-Nitrate Cylinders
Uranyl-Nitrate Spheres
Zero Power Reactors
97 MATHEMATICS AND COMPUTING
Benchmarks
Cross Section Evaluation Working Group (CSEWG) Benchmark Specifications
Evaluated Nuclear Data File (ENDF)
Evaluation
Fast Benchmarks
Fast Fission
JENDL-3.2 Evaluation
Nuclear Criticality Safety Program (NCSP)
Nuclear Data Collections
Thermal Benchmarks
Thermal Fission
Uranium 233
Uranyl-Nitrate Cylinders
Uranyl-Nitrate Spheres
Zero Power Reactors