Computing the moments of the neutron population using deterministic neutron transport

Conference · Mon Jul 01 00:00:00 EDT 2013

OSTI ID:22212763

Fichtl, E. D.; Baker, R. S. ^[1]

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1. Los Alamos National Laboratory, Computational Physics and Methods, CCS-2, PO Box 1663, Los Alamos, NM, 87544 (United States)

It is important to treat the inherent stochasticity of the fission process in systems where the behavior of the system is stochastic. This occurs when there are few neutrons in the system, or when the neutron source is weak. In order to characterize such systems, the capability to compute the first four moments of the neutron population distribution has been added to the deterministic neutral particle transport code, PARTISN. The moments are then fitted to probability density functions from the Pearson family. PARTISN is compared against MCNP6, with which it agrees well. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22212763
• Resource Relation: Conference: M and C 2013: 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, Sun Valley, ID (United States), 5-9 May 2013; Other Information: Country of input: France; 11 refs.; Related Information: In: Proceedings of the 2013 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering - M and C 2013| 3016 p.
• Country of Publication: United States
• Language: English

Related Subjects

97 MATHEMATICAL METHODS AND COMPUTING
COMPARATIVE EVALUATIONS
FISSION
NEUTRON SOURCES
NEUTRON TRANSPORT
NEUTRONS
PROBABILITY DENSITY FUNCTIONS
STOCHASTIC PROCESSES