Fission gases and helium gas behavior in irradiated mixed oxide fuel pin
佐藤 勇; 勝山 幸三; 荒井 康夫
Sato, Isamu; Katsuyama, Kozo; Arai, Yasuo
Release behavior of fission gases such as Kr and Xe from fuel pellets has been extensively investigated from the viewpoints of increase of internal pressure of fuel pins and swelling of fuel pellets. He also contributes to increase the internal pressure of fuel pins, especially in the case of minor actinide containing MOX fuel. In this work, the amounts of fission gases and He in a fuel pin irradiated in the experimental fast reactor, JOYO, to -50 GWd/t as a pin average burnup were quantitatively measured by pin puncture and pellet heating tests. As results, the release fractions of fission gases from fuel pellets were about 50%, but He was released by more than 70%. In addition, 20% of He may be derived from $$alpha$$-decay of actinide species after irradiation. It was suggested that most of He generated during irradiation was released because of the high temperature like in fast reactor environment.
使用言語 : English
掲載資料名 : Journal of Nuclear Materials
: 416
: 1-2
ページ数 : p.151 - 157
発行年月 : 2011/09
出版社名 : Elsevier
発表会議名 : E-MRS 2010 Spring Meeting
開催年月 : 2010/06
開催都市 : Strasbourg
開催国 : France
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論文URL :
キーワード : no keyword
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受委託・共同研究相手機関 :
登録番号 : BB20100178
抄録集掲載番号 : 39001524
論文投稿番号 : 9813
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Materials Science, Multidisciplinary
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