ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP

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Calculations for the ANS UO{sub 2} lattice benchmark have been performed with the MCNP Monte Carlo code and its ENDF/B-V and EnDF/B-VI continuous-energy libraries. Similar calculations were performed previously for the experiments upon which these benchmarks are based, using continuous-energy libraries derived from EnDF/B-V and from Release 2 of EnDF/B-VI (ENDF/B-VI.2). This study extends those calculations to the infinite-lattice configurations given in the benchmark specifications and also includes results from Release 3 of EnDF/B-VI (ENDF/B-VI.3) for both the core and infinite-lattice configurations. For this set of benchmarks, the only significant difference between the ENDF/B-VI.2 and EnDF/B-VI.3 libraries is the cross-section ... continued below

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11 p.

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Mosteller, R. D. August 1998.

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  • Los Alamos National Laboratory
    Publisher Info: Los Alamos National Lab., Nonproliferation and International Security Div., NM (United States)
    Place of Publication: New Mexico

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Calculations for the ANS UO{sub 2} lattice benchmark have been performed with the MCNP Monte Carlo code and its ENDF/B-V and EnDF/B-VI continuous-energy libraries. Similar calculations were performed previously for the experiments upon which these benchmarks are based, using continuous-energy libraries derived from EnDF/B-V and from Release 2 of EnDF/B-VI (ENDF/B-VI.2). This study extends those calculations to the infinite-lattice configurations given in the benchmark specifications and also includes results from Release 3 of EnDF/B-VI (ENDF/B-VI.3) for both the core and infinite-lattice configurations. For this set of benchmarks, the only significant difference between the ENDF/B-VI.2 and EnDF/B-VI.3 libraries is the cross-section behavior of {sup 235}U. EnDF/B-VI.3 contains revised cross sections for {sup 235}U below 900 eV, although those changes principally affect the range below 110 eV. In particular, relative to EnDF/B-VI.2, EnDF/B-VI.3 increases the epithermal capture-to-fission ratio for {sup 235}U and slightly increases its thermal fission cross section.

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11 p.

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INIS; OSTI as DE98007154

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  • International conference on the physics of nuclear science and technology, Long Island, NY (United States), 5-8 Oct 1998

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  • Other: DE98007154
  • Report No.: LA-UR--98-23
  • Report No.: CONF-981003--
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 674737
  • Archival Resource Key: ark:/67531/metadc710489

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  • August 1998

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  • Sept. 12, 2015, 6:31 a.m.

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  • Feb. 25, 2016, 4:30 p.m.

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Mosteller, R. D. ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP, article, August 1998; New Mexico. (digital.library.unt.edu/ark:/67531/metadc710489/: accessed October 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.