| Cao Lei,Deng Jun,Liu Yunhong,et al.Determination and analysis of uncertainty for individual neutron dose monitoring using CR39[J].Chinese Journal of Radiological Medicine and Protection,2014,34(3):215-218 |
| Determination and analysis of uncertainty for individual neutron dose monitoring using CR39 |
| Received:May 09, 2013 |
| DOI：10.3760/cma.j.issn.0254-5098.2014.03.014 |
| KeyWords:CR39 Individual neutron dose monitoring Uncertainty Expanded uncertainty |
| FundProject:科研院所技术开发研究专项基金（2012EG150137） |
| Author Name | Affiliation | | Cao Lei | Key Laboratory of Radiological Protection and Nuclear Emergency, China CDC, National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088, China | | Deng Jun | Key Laboratory of Radiological Protection and Nuclear Emergency, China CDC, National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088, China | | Liu Yunhong | Key Laboratory of Radiological Protection and Nuclear Emergency, China CDC, National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088, China | | Zhang Guiying | 中国原子能科学研究院 | | Wang Fang | 湖北省疾病预防控制中心 | | Zhou Ning | 江西省职业病防治研究院 | | Guo Wen | Key Laboratory of Radiological Protection and Nuclear Emergency, China CDC, National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088, China | | Hu Aiying | Key Laboratory of Radiological Protection and Nuclear Emergency, China CDC, National Institute for Radiological Protection, Chinese Center for Disease Control and Prevention, Beijing 100088, China |
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| Abstract:: |
| Objective To improve the quality of measurement of individual neutron dose and quantify reliability of result through determining the uncertainty of individual neutron dose monitoring using CR39.Methods The uncertainty of measurement of individual neutron dose using CR39 was determined by establishing mathematic model and calculating uncertainty introduced by detector reading. Results Type A uncertainty mainly comeed from measuring values and background, with the maximum component of about 11.68%. While type B uncertainty was about 7.85% from energy response, 4.0% from dose linearity, 1.68% from distance response and 3.0% from ecthing conditions respectively. In addition, energy response of detector contributes mostly to type B uncertainty. In present work, the relative uncertainty was 32% with k=2. Conclusions In the evaluation of uncertainty for radioisotope workplace,it is the right means to choose certain type neutron detector for the neutrons within narrow energy spectrum (neutron energy grouping) to reduce the introduction of uncertainty. |
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