PC-Based Criticality Code use at an "Isolated Site"

Conference · Sun Jun 20 00:00:00 EDT 1993 · Transactions of the American Nuclear Society

OSTI ID:5769365

Knief, R. A. ^[1]; Simpkins, B. ^[2]

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1. Ogden Environmental and Energy Services, Albuquerque, NM (United States)
2. Battelle Pantex, Amarillo, TX (United States)

Personal computer (PC)-based codes were used to conduct evaluations for subcriticality of fissile material in staging areas at the Pantex plant. The calculations, whose results were used in safety analysis reports (SARS) and a radiological hazards analysis (RHA), were performed by an individual practitioner located off-site. The Pantex evaluations addressed plutonium-metal components, modeling them as identical generic units. The model is conservative for criticality safety purposes in assuming a spherical shell with increased mass and reduced radius, while the plutonium content is treated as if it is all ²³⁹Pu. The computer codes KEN05APC (with 16-group Hansen-Roach cross sections) and MCNP4 (in a package with grouped cross sections) were obtained from the Radiation Shielding Information Center (RSIC). Calculations were performed for arrays of units in various numbers and arrangements with a variety of moderations and reflection conditions and with and without containers.

• Research Organization: Ogden Environmental and Energy Services, Albuquerque, NM (United States); Battelle Pantex, Amarillo, TX (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5769365
• Report Number(s): CONF-930601-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society, Vol. 68; Conference: American Nuclear Society (ANS) Annual Meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
• Publisher: American Nuclear Society
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICS AND COMPUTING
BOLTZMANN EQUATION
NUMERICAL SOLUTION
CRITICALITY
COMPUTERIZED SIMULATION
SAFETY ANALYSIS
NEUTRON TRANSPORT
PERSONAL COMPUTERS
COMPUTERS
DIFFERENTIAL EQUATIONS
DIGITAL COMPUTERS
EQUATIONS
MICROCOMPUTERS
NEUTRAL-PARTICLE TRANSPORT
PARTIAL DIFFERENTIAL EQUATIONS
RADIATION TRANSPORT
SIMULATION
Nuclear Criticality Safety Program (NCSP)
Personal Computer (PC)-Based Codes
Safety Analysis Reports (SARS)
MCNP4
Radiation Shielding Information Center (RSIC)
420203* - Engineering- Handling Equipment & Procedures
663610 - Neutron Physics- (1992-)
990200 - Mathematics & Computers