A Practical Method for Evaluating the Neutron Dose Equivalent Rate
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概要
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A practical method applicable to field monitoring with survey instruments is presented, which permits evaluation of the dose equivalent rate for neutrons, the spectrum of which is unknown but with energy ranging from epithermal to fast. The detectors employed consist of a BF<SUB>3</SUB> proportional counter with paraffin moderators 6.5 cm and 1.0 cm thick, sheathed in 0.5 mm thick Cd, and a scintillation (ZnS and plastic) counter. The dose equivalent rate D(mrem/hr) of neutrons with a broad spectrum is determined from the equation D=D<SUB>B</SUB>+D<SUB>S</SUB>, where D<SUB>B</SUB> is the dose equivalent rate determined from the effective neutron flux and the effective neutron energy through the counting rates obtained with the BF<SUB>3</SUB> proportional counter with paraffin moderators, and D<SUB>S</SUB> the dose measured with the scintillation counter, the sensitivity of which is nearly proportional to the dose equivalent rate for neutrons above 2 MeV. The error in evaluating the dose equivalent rate by the present method has been calculated to be at most 60% for typical neutron spectra, in the energy range from epithermal to 10 MeV.
- 一般社団法人 日本原子力学会の論文
著者
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TATSUTA Hatsumi
Division of Health Physics and Safety, Japan Atomic Energy Research Institute
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Ryufuku Hiroshi
Division Of Health Physics And Safety Japan Atomic Energy Research Institute
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Tatsuta Hatsumi
Division Of Health Physics And Safety Japan Atomic Energy Research Institute
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YOSHIDA Yoshikazu
Division of Health Physics and Safety, Japan Atomic Energy Research Institute
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KITANO Kyoshiro
Division of Health Physics and Safety, Japan Atomic Energy Research Institute
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FUKUDA Seiji
Division of Health Physics and Safety, Japan Atomic Energy Research Institute
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YOSHIDA Yoshikazu
Division of Health Physics and Safety, Japan Atomic Energy Research Institure
関連論文
- Sensitivity of a Paraffin-Moderated BF_3 Proportional Counter
- Application of Different Orthonormal Expansion Methods to Neutron Measurements. : III. Actual Measurements of Spectra and Dose Equivalent Rates.
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- Application of Different Orthonormal Expansion Methods to Neutron Measurements. : II. Estimation of Dose Equivalent Rates
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