Post-irradiation examination on particle dispersed rock-like oxide fuel
白数 訓子; 蔵本 賢一*; 山下 利之; 市瀬 健一; 小野 勝人; 二瓶 康夫
Shirasu, Noriko; Kuramoto, Kenichi*; Yamashita, Toshiyuki; Ichise, Kenichi; Ono, Katsuto; Nihei, Yasuo
To evaluate irradiation behavior of the ROX fuel, irradiation experiment was carried out using 20% enriched U instead of Pu. Three fuels were prepared; a single phase fuel of YSZ containing UO$$_{2}$$ (U-YSZ), two particle-dispersed fuels of U-YSZ particle in spinel or corundum matrix. The U-YSZ particles were prepared by crashing presintered U-YSZ pellets and by sieving them. These fuels were irradiated in Japan Research Reactor No.3 for 13 cycles, about 300 days. Though many cracks were observed in the pellets by X-ray photographs, significant appearance changes were not observed for all fuel pins. Distribution of typical FPs was analyzed by the $$gamma$$ scanning over the fuel pin. Non-volatile nuclide remained in the fuel pellet. On the other hand, a part of Cs moved to the gaps between the pellets and to the insulators. $$^{134}$$Cs and $$^{137}$$Cs showed different distributions at the plenum. Fuel pellets were taken out from fuel pins without bonding. Spinel decomposition and subsequent restructuring were not observed probably due to low irradiation temperature.
使用言語 : English
掲載資料名 : Journal of Nuclear Materials
: 352
: 1-3
ページ数 : p.365 - 371
発行年月 : 2006/06
出版社名 : Elsevier
発表会議名 : Europian Materials Research Society 2005 Spring Meeting
開催年月 : 2005/05
開催都市 : Strasbourg
開催国 : France
特許データ :
論文URL :
キーワード : 岩石型燃料; 照射試験; セシウム; $$gamma$$線スキャニング; 粒子分散型
使用施設 :
広報プレスリリース :
受委託・共同研究相手機関 :
登録番号 : B20050088
抄録集掲載番号 : 35000142
論文投稿番号 : 1694
Accesses  (From Jun. 2, 2014)
- Accesses
分野:Materials Science, Multidisciplinary
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