Validation of MCNP4a for highly enriched uranium using the Battelle process safety and risk management IBM RS/6000 workstation

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This document has been prepared to allow use of the Radiation Shielding and Information Center (RSIC) release of MCNP4a, which has been installed on the Battelle Process Safety and Risk Management (PSRM) IBM RS/6000 workstation, for production calculations for the Portsmouth Gaseous Diffusion Plant (PORTS). This hardware/software configuration is under the configuration control plan listed in Reference 1. The first portion of this document outlines basic information with regard to validation of MCNP4a using the supplied cross sections and the additional MCNPDAT cross sections. A basic discussion of MCNP is provided, along with discussions of the validation database in general. ... continued below

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110 p.

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Negron, S.B.; Lee, B.L. Jr. & Tayloe, R.W. Jr. January 1, 1996.

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Description

This document has been prepared to allow use of the Radiation Shielding and Information Center (RSIC) release of MCNP4a, which has been installed on the Battelle Process Safety and Risk Management (PSRM) IBM RS/6000 workstation, for production calculations for the Portsmouth Gaseous Diffusion Plant (PORTS). This hardware/software configuration is under the configuration control plan listed in Reference 1. The first portion of this document outlines basic information with regard to validation of MCNP4a using the supplied cross sections and the additional MCNPDAT cross sections. A basic discussion of MCNP is provided, along with discussions of the validation database in general. A description of the statistical analysis then follows. The results of this validation indicate that the software and data libraries examined may be used with confidence for criticality calculations at the Portsmouth Gaseous Diffusion Plant (PORTS). When the validation results are treated as a single group, there is a 95% confidence that 99.9% of future calculations of similar critical systems will have a calculated k{sub eff} > 0.95. Based on this result, the Battelle PSRM Nuclear Safety Group has adopted the calculational acceptance criteria that a calculated k{sub eff} + 2{sigma}, {le} 0.95 is safely subcritical. The conclusion of this document is that MCNP4a and all associated cross section libraries installed on the PSRM IBM RS/6000 are acceptable for use in performing production criticality safety calculations for the Portsmouth Gaseous Diffusion Plant.

Physical Description

110 p.

Notes

INIS; OSTI as DE96005116

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  • Other Information: PBD: Jan 1996

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  • Other: DE96005116
  • Report No.: POEF-SH--33
  • Grant Number: AC05-84OT21400
  • DOI: 10.2172/188622 | External Link
  • Office of Scientific & Technical Information Report Number: 188622
  • Archival Resource Key: ark:/67531/metadc672854

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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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  • January 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Nov. 30, 2015, 12:53 p.m.

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Negron, S.B.; Lee, B.L. Jr. & Tayloe, R.W. Jr. Validation of MCNP4a for highly enriched uranium using the Battelle process safety and risk management IBM RS/6000 workstation, report, January 1, 1996; United States. (digital.library.unt.edu/ark:/67531/metadc672854/: accessed December 14, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.