Monte Carlo cross section testing for thermal and intermediate {sup 235}U/{sup 238}U critical assemblies, ENDF/B-V vs ENDF/B-VI

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Description

The purpose of this study is to investigate the eigenvalue sensitivity to changes in ENDF/B-V and ENDF/B-VI cross section data sets by comparing RACER vectorized Monte Carlo calculations for several thermal and intermediate spectrum critical experiments. Nineteen Oak Ridge and Rocky Flats thermal solution benchmark critical assemblies that span a range of hydrogen-to-{sup 235}U (H/U) concentrations (2052 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.

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8 p.

Creation Information

Weinman, J.P. June 1, 1997.

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This article is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. More information about this article can be viewed below.

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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 changes in ENDF/B-V and ENDF/B-VI cross section data sets by comparing RACER vectorized Monte Carlo calculations for several thermal and intermediate spectrum critical experiments. Nineteen Oak Ridge and Rocky Flats thermal solution benchmark critical assemblies that span a range of hydrogen-to-{sup 235}U (H/U) concentrations (2052 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 DE99002614

Source

  • ARS `97: American Nuclear Society (ANS) international meeting on advanced reactors safety, Orlando, FL (United States), 1-5 Jun 1997

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  • Other: DE99002614
  • Report No.: KAPL-P--000242
  • Report No.: K--96165;CONF-970607--
  • Grant Number: AC12-76SN00052
  • Office of Scientific & Technical Information Report Number: 350945
  • Archival Resource Key: ark:/67531/metadc682429

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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Creation Date

  • June 1, 1997

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

Description Last Updated

  • May 18, 2016, 2:45 p.m.

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Weinman, J.P. Monte Carlo cross section testing for thermal and intermediate {sup 235}U/{sup 238}U critical assemblies, ENDF/B-V vs ENDF/B-VI, article, June 1, 1997; Schenectady, New York. (digital.library.unt.edu/ark:/67531/metadc682429/: accessed April 22, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.