MCNP calculations for criticality-safety benchmarks with ENDF/B-V and ENDF/B-VI libraries

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Description

The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-section libraries, has been benchmarked against results from 27 different critical experiments. The predicted values of k{sub eff} are in excellent agreement with the benchmarks, except for the ENDF/B-V results for solutions of plutonium nitrate and, to a lesser degree, for the ENDF/B-V and ENDF/B-VI results for a bare sphere of {sup 233}U.

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12 p.

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Iverson, J. L. & Mosteller, R. D. July 1, 1995.

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Description

The MCNP Monte Carlo code, in conjunction with its continuous-energy ENDF/B-V and ENDF/B-VI cross-section libraries, has been benchmarked against results from 27 different critical experiments. The predicted values of k{sub eff} are in excellent agreement with the benchmarks, except for the ENDF/B-V results for solutions of plutonium nitrate and, to a lesser degree, for the ENDF/B-V and ENDF/B-VI results for a bare sphere of {sup 233}U.

Physical Description

12 p.

Notes

INIS; OSTI as DE95015255

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

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  • Other: DE95015255
  • Report No.: LA-UR--95-1856
  • Report No.: CONF-9509100--25
  • Grant Number: W-7405-ENG-36
  • Office of Scientific & Technical Information Report Number: 97187
  • Archival Resource Key: ark:/67531/metadc792846

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  • July 1, 1995

Added to The UNT Digital Library

  • Dec. 19, 2015, 7:14 p.m.

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  • Feb. 25, 2016, 8:49 p.m.

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Iverson, J. L. & Mosteller, R. D. MCNP calculations for criticality-safety benchmarks with ENDF/B-V and ENDF/B-VI libraries, article, July 1, 1995; New Mexico. (digital.library.unt.edu/ark:/67531/metadc792846/: accessed September 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.