Evaluation of fission product and actinide release behaviors focusing on their chemical forms; Phase relation and fission product release behavior resulting from interaction between molten zircaloy and irradiated MOX fuel

Tanaka, Kosuke ; Miwa, Shuhei ; Sato, Isamu; Hirosawa, Takashi ; Sekine, Shinichi; Seki, Takayuki*; Tokoro, Daishiro*; Obayashi, Hiroshi ; Koyama, Shinichi

In order to establish the method for heating tests focused on the fission product release resulting from the high temperature chemical interaction between fuel and cladding material and to obtain the novel data on fission product release behaviors, the heating test was carried out with irradiate MOX fuel pellet and cladding.

Language	:	Japanese
Report No.	:	JAEA-Research 2013-022
Pages	:	62 Pages
Publication Year/Month	:	2014/01
Patent information	:
PDF	:	JAEA-Research-2013-022.pdf:33.64MB
Paper URL	:	https://doi.org/10.11484/jaea-research-2013-022
Keywords	:	福島第一原子力発電所事故; Fukushima Daiichi Nuclear Power Station Accident
Research Facility	:	AGF(照射燃料試験施設)
Press Release	:
Article of JAEA R&D Review	:
Cooperating Institute	:
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Registration No. : RS20130022
JAEA Abstracts No. : 42000120

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