Monk, Stephen and Selwood, Mark (2011) A Monte Carlo simulation of monoenergetic neutrons traversing rectangular and spherical polyethylene moderators. Radiation Protection Dosimetry, 144 (1-4). pp. 182-186. ISSN 1742-3406Full text not available from this repository.
A Monte Carlo-based simulation of the transport of a series of monoenergetic neutron sources through first a rectangular block of 0.93 g cm−3 density polyethylene and secondly through a sphere made of the same substance is presented here. In both instances, the neutron fields are monitored at closely spread intervals through the moderator mass, producing a lot of data in the process. To reduce the amount of data presented, a figure of merit is created by estimating the cross section for each discrete neutron energy and by applying this to the number of neutrons present of each energy giving an arbitrary response figure. This work was undertaken in order to aid the design and development of a novel neutron spectrometer.
|Journal or Publication Title:||Radiation Protection Dosimetry|
|Subjects:||T Technology > TA Engineering (General). Civil engineering (General)|
|Departments:||Faculty of Science and Technology > Engineering|
|Deposited By:||Dr Stephen Monk|
|Deposited On:||09 Dec 2010 13:16|
|Last Modified:||24 Apr 2017 03:15|
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