Testing of the ENDF/B-VI neutron data library ENDF60 for use 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. It is comprised of 124 nuclide data files based on the ENDF/B-Vi evaluations through Release 2. Forty-eight percent of these materials are new or modified evaluations, while the balance are translations from ENDF/B-V. The new evaluations include most of the important materials for criticality safety calculations, and include significant enhancements such as more isotopic evaluations, better resonance-range representations, and the new correlated energy-angle distributions for emitted particles. As part of the overall quality assurance testing of ... continued below

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9 p.

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Frankle, S.C. & MacFarlane, R.E. July 1, 1995.

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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. It is comprised of 124 nuclide data files based on the ENDF/B-Vi evaluations through Release 2. Forty-eight percent of these materials are new or modified evaluations, while the balance are translations from ENDF/B-V. The new evaluations include most of the important materials for criticality safety calculations, and include significant enhancements such as more isotopic evaluations, better resonance-range representations, and the new correlated energy-angle distributions for emitted particles. As part of the overall quality assurance testing of the ENDF60 library, calculations for well known benchmark assemblies were performed. The results of these calculations help the user to know how the combination of ENDF60 and MCNP4A will perform for real problems.

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9 p.

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INIS; OSTI as DE95015199

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  • 5. international conference on nuclear criticality safety, Albuquerque, NM (United States), 17-22 Sep 1995

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  • Other: DE95015199
  • Report No.: LA-UR--95-1886
  • Report No.: CONF-9509100--28
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 104782
  • Archival Resource Key: ark:/67531/metadc624744

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  • July 1, 1995

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  • June 16, 2015, 7:43 a.m.

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  • Feb. 26, 2016, 6:42 p.m.

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Frankle, S.C. & MacFarlane, R.E. Testing of the ENDF/B-VI neutron data library ENDF60 for use with MCNP{trademark}, article, July 1, 1995; New Mexico. (digital.library.unt.edu/ark:/67531/metadc624744/: accessed September 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.