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MOX燃料设施中使用的中子剂量计剂量当量响应的预测分析。

Prediction analysis of dose equivalent responses of neutron dosemeters used at a MOX fuel facility.

作者信息

Tsujimura N, Yoshida T, Takada C

机构信息

Nuclear Fuel Cycle Engineering Laboratories, Japan Atomic Energy Agency, 4-33 Tokai-mura, Ibaraki-ken 319-1194, Japan.

出版信息

Radiat Prot Dosimetry. 2011 Jul;146(1-3):198-201. doi: 10.1093/rpd/ncr147. Epub 2011 Apr 14.

Abstract

To predict how accurately neutron dosemeters can measure the neutron dose equivalent (rate) in MOX fuel fabrication facility work environments, the dose equivalent responses of neutron dosemeters were calculated by the spectral folding method. The dosemeters selected included two types of personal dosemeter, namely a thermoluminescent albedo neutron dosemeter and an electronic neutron dosemeter, three moderator-based neutron survey meters, and one special instrument called an H(p)(10) monitor. The calculations revealed the energy dependences of the responses expected within the entire range of neutron spectral variations observed in neutron fields at workplaces.

摘要

为预测中子剂量计在MOX燃料制造设施工作环境中测量中子剂量当量(率)的准确程度,采用谱折叠法计算了中子剂量计的剂量当量响应。所选剂量计包括两种个人剂量计,即热释光反照率中子剂量计和电子中子剂量计、三种基于慢化剂的中子测量仪以及一种名为H(p)(10)监测仪的特殊仪器。计算结果揭示了在工作场所中子场观察到的中子谱变化的整个范围内预期响应的能量依赖性。

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