Evaluation of fission products migration behavior by fuel heating tests, 2; Phase status of the heated fuel sample

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

In order to develop the heating method for both fuel pellet and cladding, irradiated MOX fuel together with Zry-2 cladding were heated by using source term evaluation equipment.

Language	:	Japanese
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Meeting title	:	日本原子力学会2012年秋の大会
Held date	:	2012/09
Location (city)	:	東広島
Location (country)	:	日本
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Keywords	:	no keyword
Research Facility	:	AGF(照射燃料試験施設)
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Registration No. : BB20120850
JAEA Abstracts No. :
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