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Technical Briefs

The Design of an Ambient Neutron Dose-Equivalent Meter

[+] Author and Article Information
Xia Wenming

College of Naval Architecture and Power, Naval University of Engineering, 717 Jie-fang Avenue, Wuhan, Hubei 430033, Chinaxiawenming_2008@163.com

Jia Mingchun

College of Naval Architecture and Power, Naval University of Engineering, 717 Jie-fang Avenue, Wuhan, Hubei 430033, Chinajiamingchun_303@163.com

Guo Zhirong

719 Research Institute, China Shipbuilding Industry Company, 450 Zhong-shan Road, Wuhan, Hubei 430064, Chinaguozhirong_404@163.com

J. Eng. Gas Turbines Power 133(8), 084501 (Apr 08, 2011) (4 pages) doi:10.1115/1.4002818 History: Received July 03, 2010; Revised July 04, 2010; Published April 08, 2011; Online April 08, 2011

At present, most of the developed neutron dosimeters used to measure the neutron ambient dose-equivalent that has a moderator with a single counter, applied in neutron radiation fields within large range energies from thermal to MeV neutrons, are not a satisfaction to energy response. The purpose of this article is to design a suitable neutron dosimeter for radiation protection purpose. In order to overcome the disadvantage of the energy response of the neutron dosimeters combining a single sphere with a single counter, three spheres and three H3e counters were combined for the detector design. The response function of moderators with different thicknesses combined with SP9 H3e counters were calculated with Monte Carlo code MCNP 4C . The selection of three different thicknesses of the moderating polyethylene sphere was done with a MATLAB program. A suitable combination of three different thicknesses was confirmed for the detector design. The electronic system of the neutron dosimeter was introduced. The results of ambient dose-equivalent per unit fluence in different radiation areas were calculated, analyzed, and compared with the values recommended in the ISO standard. The calculated result explains that it is very significant to this design of neutron dosimeter; it may be applied to the monitor of the ambient dose in the neutron radiation fields, improving at present the status of the energy response of neutron dosimeters.

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Copyright © 2011 by American Society of Mechanical Engineers
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Figures

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Figure 1

Energy response of SP9 embedded into the center of spherical moderators with different thicknesses

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Figure 2

The structure of the detector

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Figure 3

Block diagram of the electronics

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Figure 4

Block diagram of the CSPA

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Figure 5

Block diagram of the PAD

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Figure 6

Layout of the experiment equipments

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