Assessment of the available {sup 233}U cross-section evaluations in the calculation of critical benchmark experiments

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In this report we investigate the adequacy of the available {sup 233}U cross-section data for calculation of experimental critical systems. The {sup 233}U evaluations provided in two evaluated nuclear data libraries, the U.S. Data Bank [ENDF/B (Evaluated Nuclear Data Files)] and the Japanese Data Bank [JENDL (Japanese Evaluated Nuclear Data Library)] are examined. Calculations were performed for six thermal and ten fast experimental critical systems using the S{sub n} transport XSDRNPM code. To verify the performance of the {sup 233}U cross-section data for nuclear criticality safety application in which the neutron energy spectrum is predominantly in the epithermal energy range, ... continued below

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55 p.

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Leal, L.C. & Wright, R.Q. October 1, 1996.

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Description

In this report we investigate the adequacy of the available {sup 233}U cross-section data for calculation of experimental critical systems. The {sup 233}U evaluations provided in two evaluated nuclear data libraries, the U.S. Data Bank [ENDF/B (Evaluated Nuclear Data Files)] and the Japanese Data Bank [JENDL (Japanese Evaluated Nuclear Data Library)] are examined. Calculations were performed for six thermal and ten fast experimental critical systems using the S{sub n} transport XSDRNPM code. To verify the performance of the {sup 233}U cross-section data for nuclear criticality safety application in which the neutron energy spectrum is predominantly in the epithermal energy range, calculations of four numerical benchmark systems with energy spectra in the intermediate energy range were done. These calculations serve only as an indication of the difference in calculated results that may be expected when the two {sup 233}U cross-section evaluations are used for problems with neutron spectra in the intermediate energy range. Additionally, comparisons of experimental and calculated central fission rate ratios were also made. The study has suggested that an ad hoc {sup 233}U evaluation based on the JENDL library provides better overall results for both fast and thermal experimental critical systems.

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55 p.

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INIS; OSTI as DE97050532

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  • Other Information: PBD: Oct 1996

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  • Other: DE97050532
  • Report No.: ORNL/TM--13313
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/417002 | External Link
  • Office of Scientific & Technical Information Report Number: 417002
  • Archival Resource Key: ark:/67531/metadc686321

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Office of Scientific & Technical Information Technical Reports

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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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  • October 1, 1996

Added to The UNT Digital Library

  • July 25, 2015, 2:20 a.m.

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  • Jan. 15, 2016, 12:49 p.m.

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Leal, L.C. & Wright, R.Q. Assessment of the available {sup 233}U cross-section evaluations in the calculation of critical benchmark experiments, report, October 1, 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc686321/: accessed November 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.