Monte Carlo model of a low-energy neutron interrogation system for detecting fissile material

(cont.) Further MCNP simulations of the neutron source impinging on cargo containers suggest that this technique can respond, as expected, qualitatively differently to containers containing SNM from containers that do not. Containers that contain small amounts of fissile isotopes as in the case of a few grams of uranium-235 in a kilogram of depleted uranium will also respond to this method but much more weakly. The system as proposed is viable and further simulation and experimental work will elucidate the behavior of this system under a wide range of cargo environments.

Department dc:contributor.department

Massachusetts Institute of Technology. Dept. of Nuclear Science and Engineering.

Grantor dc:publisher

Massachusetts Institute of Technology

Year dc:date.issued

2006

Author dc:creator

• Johnson, Erik D., Ph. D. Massachusetts Institute of Technology

Advisor dc:contributor.advisor

• Richard C. Lanza.

• Nuclear Science and Engineering.

Statement dc:rights

• M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission.

Licence dc:rights.uri

• http://dspace.mit.edu/handle/1721.1/7582

Language dc:language.iso

eng

Handle dc:identifier.uri

http://hdl.handle.net/1721.1/41262

OAI identifier oai:identifier

oai:dspace.mit.edu:1721.1/41262