CSRL-V ENDF/B-V Library and Thermal Reactor and Criticality Safety Benchmarks

Conference · Mon May 17 04:00:00 EDT 1982

OSTI ID:5340325

Ford, III, W. E. ^[1]; Diggs, B. R. ^[1]; Knight, J. R. ^[1]; Greene, N. M. ^[1]; Petrie, L. M. ^[1]; Williams, M. L. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

CSRL-V, an ENDF/B-V 227-group neutron cross-section library which has recently been expanded to include Bondarenko factor data for unresolved resonance processing, was used to calculate performance parameters for a series of thermal reactor and criticality safety benchmarks. Among the thermal benchmarks calculated were the Babcock and Wilcox lattice critical experiments B and W-XIII and B and W-XX. These two slightly enriched (2.46%) UO₂, water-moderated, tight-pitch lattice experiments were chosen because (a) they have similar U²³⁸ resonance shielding characteristics as power reactor cores, and (b) they provide benchmark results representative of high-leakage and low-leakage lattices, respectively. Among the criticality safety benchmarks calculated were homogeneous, highly enriched (93.2%) uranyl fluoride spheres with hydrogen-to-uranium ratios varying from 76 to 972.

• 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); US Nuclear Regulatory Commission (USNRC), Office of Nuclear Regulatory Research; US Nuclear Regulatory Commission (USNRC), Office of Nuclear Material Safety and Safeguards; Electric Power Research Inst. (EPRI), Palo Alto, CA (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5340325
• Report Number(s): CONF-820566-2; ON: DE82015684
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
97 MATHEMATICS AND COMPUTING
Babcock
Bondarenko Factor Data
CROSS SECTIONS
Evaluated Nuclear Data File (ENDF)
KINETICS
Lattice Critical Experiment
NUCLEAR DATA COLLECTIONS
Neutron Cross-Section Library
Nuclear Criticality Safety Program (NCSP)
REACTOR KINETICS
Wilcox