Criticality safety validation: Simple geometry, single unit {sup 233}U systems

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Typically used LMITCO criticality safety computational methods are evaluated for suitability when applied to INEEL {sup 233}U systems which reasonably can be modeled as simple-geometry, single-unit systems. Sixty-seven critical experiments of uranium highly enriched in {sup 233}U, including 57 aqueous solution, thermal-energy systems and 10 metal, fast-energy systems, were modeled. These experiments include 41 cylindrical and 26 spherical cores, and 41 reflected and 26 unreflected systems. No experiments were found for intermediate-neutron-energy ranges, or with interstitial non-hydrogenous materials typical of waste systems, mixed {sup 233}U and plutonium, or reflectors such as steel, lead, or concrete. No simple geometry experiments were ... continued below

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[200] p.

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Putman, V.L. June 1, 1997.

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Description

Typically used LMITCO criticality safety computational methods are evaluated for suitability when applied to INEEL {sup 233}U systems which reasonably can be modeled as simple-geometry, single-unit systems. Sixty-seven critical experiments of uranium highly enriched in {sup 233}U, including 57 aqueous solution, thermal-energy systems and 10 metal, fast-energy systems, were modeled. These experiments include 41 cylindrical and 26 spherical cores, and 41 reflected and 26 unreflected systems. No experiments were found for intermediate-neutron-energy ranges, or with interstitial non-hydrogenous materials typical of waste systems, mixed {sup 233}U and plutonium, or reflectors such as steel, lead, or concrete. No simple geometry experiments were found with cubic or annular cores, or approximating infinite sea systems. Calculations were performed with various tools and methodologies. Nine cross-section libraries, based on ENDF/B-IV, -V, or -VI.2, or on Hansen-Roach source data, were used with cross-section processing methods of MCNP or SCALE. The k{sub eff} calculations were performed with neutral-particle transport and Monte Carlo methods of criticality codes DANT, MCNP 4A, and KENO Va.

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[200] p.

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INIS; OSTI as DE98050474

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  • Other Information: PBD: Jun 1997

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  • Other: DE98050474
  • Report No.: INEL/EXT--97-00668
  • Grant Number: AC07-94ID13223
  • DOI: 10.2172/578708 | External Link
  • Office of Scientific & Technical Information Report Number: 578708
  • Archival Resource Key: ark:/67531/metadc690942

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

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  • June 1, 1997

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  • Aug. 14, 2015, 8:43 a.m.

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  • June 14, 2016, 6:47 p.m.

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Putman, V.L. Criticality safety validation: Simple geometry, single unit {sup 233}U systems, report, June 1, 1997; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc690942/: accessed January 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.