New calculations for critical assemblies using MCNP4B

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A suite of 41 criticality benchmarks has been modeled using MCNP{trademark} (version 4B). Most of the assembly specifications were obtained from the Cross Section Evaluation Working Group (CSEWG) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) compendiums of experimental benchmarks. A few assembly specifications were obtained from experimental papers. The suite contains thermal and fast assemblies, bare and reflected assemblies, and emphasizes {sup 233}U, {sup 235}U, {sup 238}U, and {sup 239}Pu. The values of k{sub eff} for each assembly in the suite were calculated using MCNP libraries derived primarily from release 2 of ENDF/B-V and release 2 of ENDF/B-VI. ... continued below

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9 p.

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Adams, A. A.; Frankle, S. C. & Little, R. C. July 1997.

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Description

A suite of 41 criticality benchmarks has been modeled using MCNP{trademark} (version 4B). Most of the assembly specifications were obtained from the Cross Section Evaluation Working Group (CSEWG) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) compendiums of experimental benchmarks. A few assembly specifications were obtained from experimental papers. The suite contains thermal and fast assemblies, bare and reflected assemblies, and emphasizes {sup 233}U, {sup 235}U, {sup 238}U, and {sup 239}Pu. The values of k{sub eff} for each assembly in the suite were calculated using MCNP libraries derived primarily from release 2 of ENDF/B-V and release 2 of ENDF/B-VI. The results show that the new ENDF/B-VI.2 evaluations for H, O, N, B, {sup 235}U, {sup 238}U, and {sup 239}Pu can have a significant impact on the values of k{sub eff}. In addition to the integral quantity k{sub eff}, several additional experimental measurements were performed and documented. These experimental measurements include central fission and reaction-rate ratios for various isotopes, and neutron leakage and flux spectra. They provide more detailed information about the accuracy of the nuclear data than can k{sub eff}. Comparison calculations were performed using both ENDF/B-V.2 and ENDF/B-VI.2-based data libraries. The purpose of this paper is to compare the results of these additional calculations with experimental data, and to use these results to assess the quality of the nuclear data.

Physical Description

9 p.

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INIS; OSTI as DE97009128

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  • 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997

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  • Other: DE97009128
  • Report No.: LA-UR--97-2536
  • Report No.: CONF-971125--
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 642734
  • Archival Resource Key: ark:/67531/metadc694617

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  • July 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • Nov. 24, 2015, 5:14 p.m.

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Adams, A. A.; Frankle, S. C. & Little, R. C. New calculations for critical assemblies using MCNP4B, article, July 1997; New Mexico. (digital.library.unt.edu/ark:/67531/metadc694617/: accessed September 22, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.