14-MeV Neutron Generator Used as a Thermal Neutron Source

Journal Article · Tue Mar 10 00:00:00 EDT 2009 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.3120188· OSTI ID:21289682

Dioszegi, I; Smith, G; Schaknowski, N ^[1]

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1. Brookhaven National Laboratory, Upton, New York 11973 (United States)

One of the most important applications of the general purpose Monte Carlo N-Particle (MCNP5 and MCNPX) codes is neutron shielding design. We employed this method to simulate the shielding of a 14-MeV neutron generator used as a thermal neutron source providing an external thermal neutron beam for testing large area neutron detectors developed for diffraction studies in biology and also useful for national security applications.

• OSTI ID: 21289682
• Journal Information: AIP Conference Proceedings, Vol. 1099, Issue 1; Conference: CAARI 2008: 12. international conference on application of accelerators in research and industry, Fort Worth, TX (United States), 10-15 Aug 2008; Other Information: DOI: 10.1063/1.3120188; (c) 2009 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

73 NUCLEAR PHYSICS AND RADIATION PHYSICS
COMPUTERIZED SIMULATION
M CODES
MEV RANGE
MONTE CARLO METHOD
NEUTRON BEAMS
NEUTRON GENERATORS
NEUTRON TRANSPORT
SHIELDING
THERMAL NEUTRONS