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A Monte Carlo simulation of monoenergetic neutrons traversing rectangular and spherical polyethylene moderators.

Research output: Contribution to Journal/MagazineJournal article

<mark>Journal publication date</mark>03/2011
<mark>Journal</mark>Radiation Protection Dosimetry
Issue number1-4
Number of pages5
Pages (from-to)182-186
Publication StatusPublished
<mark>Original language</mark>English


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.