Neutron Characteristics in Reactor Radiation Field for Calibration of Personal Dosimeters
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概要
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<I>The reactor radiation field, which utilizes neutrons taken out through irradiation plug in top shield from core at the Kinki University Reactor was constructed. The measurement of neutron energy spectrum in the reactor radiation field was carried out using both a NE213 detector with bisumuth shield and a NE213 with twodimensional multichannel analyzer. The analysis and the dose estimation were performed with three-dimensional MCNP Monte Carlo model. From the results, the following conclusions were obtained</I>.<BR>1.<I>Both a NE213 detector with bisumuth and a NE213 with two-dimensional multichannel analyzer are very useful as a neutron spectrometry in radiation field of low neutron intensity and high gamma-ray contamination</I>.<BR>2.<I>The neutron energy spectrum was composed of thermal neutrons and l/E neutrons from a few</I> eV <I>to a few</I> MeV. <I>It is very similar to realistic neutron energy spectra in the vicinity of a nuclear reactor</I>.<BR>3.<I>Effective dose rates of total neutron, themal neutron (<0.5</I> eV) <I>and fast neutron (>0.5</I> MeV) <I>were estimated to be 3.5</I> mSv/h, <I>1.4</I> mSv/h <I>and</I> <I>1.8</I> mSv/h, <I>respectively. These dose rates are most suitable for calibration of personnel dosimeters</I>.<BR><I>In the future, because of flexibilities for dose rate and radiation quality by changing reactor power and constructions in irradiaton plug, the radiation field is very useful not only for calibration of usual dosimeters but also for research and development of new types of dosimeters</I>.
- 社団法人 日本アイソトープ協会の論文
社団法人 日本アイソトープ協会 | 論文
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