Criticality benchmark results for the ENDF60 library with MCNP{trademark}

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The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation transport code MCNP4A, was released in the fall of 1994. The ENDF60 library is comprised of 124 nuclide data files based on the ENDF/B-VI (B-VI) evaluations through Release 2. Fifty-two percent of these B-VI evaluations are translations from ENDF/B-V (B-V). The remaining forty-eight percent are new evaluations which have sometimes changed significantly. Among these changes are greatly increased use of isotopic evaluations, more extensive resonance-parameter evaluations, and energy-angle correlated distributions for secondary particles. In particular, the upper energy limit for the resolved resonance region of {sup ... continued below

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5 p.

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Keen, N.D.; Frankle, S.C. & MacFarlane, R.E. July 1, 1995.

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Description

The continuous-energy neutron data library ENDF60, for use with the Monte Carlo N-Particle radiation transport code MCNP4A, was released in the fall of 1994. The ENDF60 library is comprised of 124 nuclide data files based on the ENDF/B-VI (B-VI) evaluations through Release 2. Fifty-two percent of these B-VI evaluations are translations from ENDF/B-V (B-V). The remaining forty-eight percent are new evaluations which have sometimes changed significantly. Among these changes are greatly increased use of isotopic evaluations, more extensive resonance-parameter evaluations, and energy-angle correlated distributions for secondary particles. In particular, the upper energy limit for the resolved resonance region of {sup 235}U, {sup 238}U and {sup 239}Pu has been extended from 0.082, 4.0, and 0.301 keV to 2..25, 10.0, and 2.5 keV respectively. As regulatory oversight has advanced and performing critical experiments has become more difficult, there has been an increased reliance on computational methods. For the criticality safety community, the performance of the combined transport code and data library is of interest. The purpose of this abstract is to provide benchmarking results to aid the user in determining the best data library for their application.

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5 p.

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INIS; OSTI as DE95015306

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  • Winter meeting of the American Nuclear Society (ANS), San Francisco, CA (United States), 29 Oct - 1 Nov 1995

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  • Other: DE95015306
  • Report No.: LA-UR--95-2069
  • Report No.: CONF-951006--20
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 106463
  • Archival Resource Key: ark:/67531/metadc618432

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  • July 1, 1995

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  • June 16, 2015, 7:43 a.m.

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  • Feb. 25, 2016, 2:22 p.m.

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Keen, N.D.; Frankle, S.C. & MacFarlane, R.E. Criticality benchmark results for the ENDF60 library with MCNP{trademark}, article, July 1, 1995; New Mexico. (digital.library.unt.edu/ark:/67531/metadc618432/: accessed September 25, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.