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Radiation Protection Dosimetry Advance Access published online on August 17, 2007
Radiation Protection Dosimetry, doi:10.1093/rpd/ncm059
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© The Author 2007. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oxfordjournals.org

DEVELOPMENT OF ADVANCED-TYPE MULTI-FUNCTIONAL ELECTRONIC PERSONAL DOSEMETER

T. Nunomiya1,*, S. Abe1, K. Aoyama1 and T. Nakamura2

1 Fuji Electric Systems Co., Ltd. Fuji-machi, Hino, Tokyo, Japan
2 Tohoku University, Aoba, Aramaki, Aoba-ku, Sendai, Japan

* Corresponding author: nunomiya-tomoya{at}fesys.co.jp

An advanced-type small, light, multi-functional electronic personal dosemeter has been developed using silicon semiconductor radiation detectors for dose management of workers at nuclear power plants and accelerator facilities. This dosemeter is 62 x 82 x 27 mm3 in size and ~130 g in weight, which is capable of measuring personal gamma ray and neutron dose equivalents, Hp(10), simultaneously. The neutron dose equivalent can be obtained using two types of silicon semiconductors: a slow-neutron sensor (<1 MeV) and a fast-neutron sensor (>1 MeV). The slow neutron sensor is a 10 x 10 mm2 p-type silicon on which a natural boron layer is deposited around an aluminium electrode. The fast neutron sensor is also a 10 x 10 mm2 p-type silicon crystal on which an amorphous silicon hydride is deposited. The neutron energy response corresponding to the fluence-to-dose-equivalent conversion coefficient given by ICRP Publication 74 has been evaluated using a monoenergetic neutron source from 250 keV to 15 MeV at the Fast Neutron Laboratory of Tohoku University. As the result, the Hp(10) response to neutrons in the energy range of 250 keV and 4.4 MeV within ±50% difference has been obtained.


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