Validation of MCNP4a for highly enriched uranium using the ports NCS IBM RS/6000 workstation
Technical Report
·
OSTI ID:266898
This document has been prepared to allow use of the Radiation Shielding & Information Center (RSIC) release of MCNP4a, which has been installed on the Portsmouth Gaseous Diffusion Plant (PORTS) NCS IBM RS/6000 workstation, for production (criticality safety) calculations at 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 percent confidence that 99.9 percent of future calculations of similar critical systems win have a calculated k{sub eff} > 0.95. Based on this result, the PORTS NCS group has adopted the calculational acceptance criteria that a calculated k{sub eff} + 2{sigma} {<=} 0.95 is safely subcritical. The conclusion of this document is that MCNP4a and all associated cross section libraries installed on the PORTS NCS IBM RS/6000 are acceptable for use in performing production criticality safety calculations for the Portsmouth Gaseous Diffusion Plant.
- Research Organization:
- Portsmouth Gaseous Diffusion Plant, OH (United States)
- OSTI ID:
- 266898
- Report Number(s):
- POEF-LMUS--12; ON: DE96013150
- Country of Publication:
- United States
- Language:
- English
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