Studies of Ceramic Fuels with the Use of Fission Gas Release Loop, (II) : Measurement of Gamma-ray Spectrum of Fission Gases
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概要
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The γ-ray spectra of fission gases released from U<SUB>O2</SUB>-graphite pellets under neutron irradiation were measured. With and without separating fission gases into xenon and krypton, 25 kinds of γ-ray were observed and assigned to nine nuclides, <SUP>85m</SUP>Kr, <SUP>87</SUP>Kr, <SUP>88</SUP>Kr(<SUP>88</SUP>Rb), <SUP>133</SUP>Xe, <SUP>135</SUP>Xe, <SUP>135</SUP>mXe and <SUP>138</SUP>Xe (<SUP>138</SUP>Cs). A value of 15 min is proposed for the half-life of <SUP>138</SUP>Xe, based on analysis of the decay curves. Discussion is given on problems related to determination of the release rate of each fission product through measurement of the height of each peak in the γ-ray spectrum.
著者
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Fukuda Takeshi
Division Of Gastroenterology Department Of Internal Medicine Nippon Medical School
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Kamemoto Yuichiro
Division of Chemistry Japan Atomic Energy Research Institute
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Shiba Koreyuki
Division of Chemistry Japan Atomic Energy Research Institute
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Yamagishi Shigeru
Division of Chemistry Japan Atomic Energy Research Institute
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SHIBA Koreyuki
Division of Fuel Research and Development, Japan Atomic Energy Research Institute
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HANDA Muneo
Division of Fuel Research and Development, Japan Atomic Energy Research Institute
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TAKAHASHI Yoshihisa
Division of Fuel Research and Development, Japan Atomic Energy Research Institute
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TANIFUJI Takaaki
Division of Fuel Research and Development, Japan Atomic Energy Research Institute
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OMORI Shunzo
Division of Fuel Research and Development, Japan Atomic Energy Research Institute
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FUKUDA Takeshi
Division of Fuel Research and Development, Japan Atomic Energy Research Institute
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