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Validation of KENO V.a with ENDF/B-V cross sections for {sup 233}U systems

Journal Article · · Nuclear Technology
OSTI ID:89662
; ; ; ; ;  [1];  [2];  [3]
  1. Univ. of Tennessee, Knoxville, TN (United States). Nuclear Engineering Dept.
  2. Martin Marietta Energy Systems, Piketon, OH (United States)
  3. Japan Atomic Energy Research Inst., Tokai (Japan)

The multigroup Monte Carlo code KENO V.a and the 238- and 44-energy-group ENDF/B-V cross-section libraries were validated for {sup 233}U systems. Fifty-one critical experiments involving {sup 233}UO{sub 2}(NO{sub 3}){sub 2}, {sup 233}UO{sub 2}F{sub 2}, or {sup 233}U metal were selected for the validation. The H/{sup 233}U ratios for the experiments range from 0 to 1986. Each experiment was modeled with KENO V.a, and the effective multiplication factor k{sub eff} was calculated for each system using the 44- and 238-group ENDF/B-V, the 27- and 218-group ENDF/B-IV, and the 16-group Hansen-Roach cross-section libraries. The mean calculated k{sub eff} for all experiments using the 44- and 238-group libraries is 1.0090 {+-} 0.0021 and 1.0064 {+-} 0.0020, respectively. For comparison, the mean calculated k{sub eff} using the 27-, 218-, and 16-group libraries is 1.0142 {+-} 0.0038, 1.0125 {+-} 0.0038, and 0.9991 {+-} 0.0019, respectively. In general, an improvement exists in the agreement between the calculated k{sub eff}`s and the experimental results (i.e., k{sub eff} = 1.0) obtained with the newer ENDF/B-V libraries relative to ENDF/B-IV. This study is pertinent to {sup 233}U storage outside of the reactor.

OSTI ID:
89662
Journal Information:
Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 2 Vol. 111; ISSN 0029-5450; ISSN NUTYBB
Country of Publication:
United States
Language:
English