Abstract
Semiconductors used for neutron detector are always coated by a thin-film, which is used to convert free neutrons into charged particles. The thin-film commonly used in such detectors utilize the 10B(n, α)7Li reaction, the 6Li(n, α)3He reaction, or the recoil proton reaction. The detection efficiency of these detectors coated with single thin-film varied with the energy of neutrons. So the energy response performance of personnel dosimeter with these detectors is not satisfactory. The purpose of the article is designing a suitable neutron detector for personnel dosimeter. In order to overcome the disadvantage of the energy response performance the neutron detectors are coated by a single thin-film. In these designs a neutron personnel dosimeter detector fabricated with three silicon diodes are coated by two different thin-films. One silicon diode is uncoated and will be used to subtract the response to gamma rays of the coated silicon diodes. The response of each silicon diodes coated by different thin-films are calculated with Monte Carlo code MCNPX. The total personnel doserate results will be obtained by summing-up each response of the coated silicon diodes multiplied with different gain factors.
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References
D. T. Bartlett, R. J. Tanner, D. J. Thomas. Active Neutron Personal Dosemeters: A Review of Current Status. Radiation Protection Dosimetry, Vol. 86, No. 2, pp. 107–122 (1999)
M. Luszik-Bhadra. A Prototype Personal Neutron Dosemeter with One Silicon Diode. Radiation Protection Dosimetry, Vol. 96, Nos 1–3, pp. 227–229 (2001)
C. Guardiola, C. Fleta, D. Quirion, et al. First investigations of a silicon neutron detector with a carborane converter. 2011 JINST 6 P11001
D. S. McGregor, R. T. Klannb, J. D. Sandersc, et al. Recent Results From Thin-Film-Coated Semiconductor Neutron Detectors. X-Ray and Gamma Ray Detectors and Applications IV, Proceedings of SPIE, Vol. 4784 (2002)
ICRP, Conversion Coefficients for Use in Radiological Protection Against External Radiation, Publication74, International Commission on Radiological Protection, Annalsofthe ICRP, 26, no. 3/4, Pergamon Press, Oxford, 1996
J.S. Hendricks et al. eds., Monte Carlo N-Particle Transport Code System for Multiparticle and High Energy Applications, version 2.6.0, Los Alamos National Laboratory, NM, LA-UR-08-2216 (2008)
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© 2017 Springer Science+Business Media Singapore
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Xia, W., Gong, J., Chen, J. (2017). Design of a Thin-Film Neutron Detector Used for Personnel Dosimeter. In: Jiang, H. (eds) Proceedings of The 20th Pacific Basin Nuclear Conference. PBNC 2016. Springer, Singapore. https://doi.org/10.1007/978-981-10-2317-0_68
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DOI: https://doi.org/10.1007/978-981-10-2317-0_68
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