Monte Carlo testing of new cross section data sets for thermal and intermediate highly enriched uranium critical assemblies

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The purpose of this study is to investigate the eigenvalue sensitivity to new {sup 235}U, hydrogen, and oxygen cross section data sets by comparing RACER Monte Carlo calculations for several thermal and intermediate spectrum critical experiments. The new {sup 235}U library (Version 107) was derived by L. Leal and H. Derrien by fitting differential experimental data for {sup 235}U while constraining the fit to match experimental capture and fission resonance integrals and Maxwellian averaged thermal K1 (v fission minus absorption). The new hydrogen library (Version 45) consists of the ENDF/B-VI release 3 data with a 332.0 mb 2,200 m/s cross ... continued below

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8 p.

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Weinman, J.P. June 1, 1998.

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  • Weinman, J.P. Lockheed Martin Corp., Schenectady, NY (United States)

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  • Knolls Atomic Power Laboratory
    Publisher Info: Knolls Atomic Power Lab., Schenectady, NY (United States)
    Place of Publication: Schenectady, New York

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Description

The purpose of this study is to investigate the eigenvalue sensitivity to new {sup 235}U, hydrogen, and oxygen cross section data sets by comparing RACER Monte Carlo calculations for several thermal and intermediate spectrum critical experiments. The new {sup 235}U library (Version 107) was derived by L. Leal and H. Derrien by fitting differential experimental data for {sup 235}U while constraining the fit to match experimental capture and fission resonance integrals and Maxwellian averaged thermal K1 (v fission minus absorption). The new hydrogen library (Version 45) consists of the ENDF/B-VI release 3 data with a 332.0 mb 2,200 m/s cross section which replaces the value of 332.6 mb in the current library. The new oxygen library (Version 39) is based on a recent evaluation of {sup 16}O by E. Caro. Nineteen Oak Ridge and Rocky Flats thermal solution benchmark critical assemblies that span a range of hydrogen-to-{sup 235}U (H/U) concentrations (2,052 to 27.1) and above-thermal neutron leakage fractions (0.555 to 0.011) were analyzed. In addition, three intermediate spectrum critical assemblies (UH3-UR, UH3-NI, and HISS-HUG) were studied.

Physical Description

8 p.

Notes

INIS; OSTI as DE99001966

Source

  • Annual meeting of the American Nuclear Society, Nashville, TN (United States), 7-12 Jun 1998

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  • Other: DE99001966
  • Report No.: KAPL-P--000200
  • Report No.: K--97142;CONF-980606--
  • Grant Number: AC12-76SN00052
  • Office of Scientific & Technical Information Report Number: 319814
  • Archival Resource Key: ark:/67531/metadc688059

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Creation Date

  • June 1, 1998

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • May 18, 2016, 2:45 p.m.

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Weinman, J.P. Monte Carlo testing of new cross section data sets for thermal and intermediate highly enriched uranium critical assemblies, article, June 1, 1998; Schenectady, New York. (digital.library.unt.edu/ark:/67531/metadc688059/: accessed July 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.