Annealing behavior of (Pu,Cm)O$$_{2}$$ lattice and bulk expansion from self-irradiation damage
高野 公秀; 赤堀 光雄; 荒井 康夫
Takano, Masahide; Akabori, Mitsuo; Arai, Yasuo
In order to investigate the effect of self-irradiation damage and accumulation of He on the oxide fuel pellet containing minor actinides, the expansion and annealing behavior of (Pu$$_{0.95}$$Cm$$_{0.05}$$)O$$_{2}$$ lattice and bulk were examined comparatively. Since the lattice and bulk expansion at room temperature showed the similar dependence on the storage duration, the main factor of bulk swelling was found to be the lattice expansion due to the generation of point defects. The lattice parameter recovered to the undamaged value by annealing at 1429 K for 2 h, whereas the bulk expanded again by annealing at 1433 K and did not recover to the undamaged value at all. On the micrographs of fracture surface of the annealed pellet, formation of gas bubbles along grain boundaries was confirmed. The accumulated He atoms migrated to the grain boundaries and formed gas bubbles, which caused the He gas swelling of the pellet.
使用言語 : English
掲載資料名 : Journal of Nuclear Materials
: 414
: 2
ページ数 : p.174 - 178
発行年月 : 2011/07
出版社名 : Elsevier
特許データ :
論文URL :
キーワード : no keyword
使用施設 :
広報プレスリリース :
: ヘリウム蓄積・放出による燃料ミクロ組織の変化; 結晶格子とペレットの膨張・焼鈍相関を明らかに[/]
受委託・共同研究相手機関 : 文部科学省
登録番号 : AA20100642
抄録集掲載番号 : 39000992
論文投稿番号 : 9244
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Materials Science, Multidisciplinary
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