Recoil Release of Fission-Gas from UO<SUB>2</SUB>
スポンサーリンク
概要
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The fission-gas released from in-core UO<SUB>2</SUB> pellets was investigated with the helium-swept fuel irradiation facility installed in the Hitachi Training Reactor. It was found that the release rate of fission-gas increased gradually as irradiation continued for 5hr under a constant thermal neutron flux of 1.0×10<SUP>12</SUP> n/cm<SUP>2</SUP>•sec and at a fuel temperature of about 150°C. This observation indicates that a recoil-activated release mechanism may be more effective than direct-recoil release in the case of clad fuel in the region of temperature where fission-gas release rate is temperature independent.
- 一般社団法人 日本原子力学会の論文
著者
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INOUE Kiyoshi
Hitachi Central Researeh Laboratory
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TANIGUCHI Kaoru
Hitachi Central Researeh Laboratory
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OHSAWA Yasuo
Hitachi Central Research Laboratory
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INOUE Kiyoshi
Hitachi Central Research Laboratory