Measurement of Effective Capture Cross Section of Americium-243 for Thermal Neutrons
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概要
- 論文の詳細を見る
The effective capture cross section of 243Am for thermal neutrons was measured with an activation method. A sample of 243Am was irradiated for 10 hrs at Kyoto University Reactor, KUR. After the irradiation, the sample was cooled for one month. In the cooling time, 244mAm and 244gAm produced by the irradiation decayed out to 244Cm. The α rays emitted from 243Am and 244Cm were measured with a silicon surface barrier detector. The neutron flux at the irradiation position was monitored using Au/Al and Co/Al wires. The effective capture cross section was deduced as 174.5±5.3b from the α-ray counts and the neutron flux. The quantity r\\sqrtT⁄T0 in Westcott’s convention was 0.037±0.004. The present result was compared with the effective capture cross sections from the JENDL-3.3 and the Mughabghab evaluations.
- 社団法人 日本原子力学会の論文
- 2006-12-25
著者
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HARADA Hideo
Japan Atomic Energy Agency
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YAMANA Hajimu
Research Reactor Institute, Kyoto University
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Harada H
Japan Atomic Energy Agency
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NAKAMURA Shoji
Japan Atomic Energy Agency
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Fujii Toshiyuki
Res. Reactor Inst. Kyoto Univ.
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Fujii Toshiyuki
Research Reactor Institute Kyoto University
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OHTA Masayuki
Japan Atomic Energy Agency
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Ogawa Masao
Department Of Hepato-biliary-pancreatic Surgery Osaka City University Graduate School Of Medicine
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Ohta Masayuki
Nuclear Sci. And Engineering Directorate Japan Atomic Energy Agency
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Yamana H
Research Reactor Institute Kyoto University
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Yamana Hajimu
Research Reactor Institute Kyoto University
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Nakamura Shoji
Nuclear Sci. And Engineering Directorate Japan Atomic Energy Agency
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Nakamura Shoji
Japan Nuclear Cycle Development Institute
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Yamana Hajimu
Res. Reactor Inst. Kyoto Univ.
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FUJII Toshiyuki
Research Laboratories, Fujisawa Pharmaceutical Co., Ltd.
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