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Using MCNP4A - the general Monte Carlo n-particle transport code to verify criticality accident alarm coverage

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:436923
; ;  [1]
  1. Office of Nuclear Waste Isolation, Columbus, OH (United States)
The purpose of the work described in this paper was to evaluate the adequacy of criticality accident alarm system (CAAS) coverage of several buildings at the Portsmouth Gaseous Diffusion Plant (PORTS) located in Piketon, Ohio. An analysis was performed in which the General Monte Carlo N-Particle Transport Code (MCNP) was used to model several of the buildings at PORTS, simulate criticality accidents, and then tally the neutron fluence at the location of the detectors.
OSTI ID:
436923
Report Number(s):
CONF-9606116--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN TANSAO; ISSN 0003-018X
Country of Publication:
United States
Language:
English