4.4 Article

An investigation on the response of PADC detectors to neutrons

Journal

APPLIED RADIATION AND ISOTOPES
Volume 69, Issue 2, Pages 340-345

Publisher

PERGAMON-ELSEVIER SCIENCE LTD
DOI: 10.1016/j.apradiso.2010.10.009

Keywords

Neutron dosimetry; Electrochemical etching; MCNPX; PADC track detector; Simulation

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The response of PADC was calculated by Monte Carlo simulation using MCNPX code. H. C and O recoils as well as nuclear reactions have been taken into account. The calculated results show important contribution to detection efficiency of PADC due to H, C and O recoils. The irradiated detectors with Am-241-Be source and Am-241-Be softened with a spherical polyethylene moderator were electrochemically etched. The paper presents the results of the experimental and Monte Carlo simulations, which are in a good agreement. (C) 2010 Elsevier Ltd. All rights reserved.

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