Axial migration and accumulation behavior of cesium in fast reactor fuel pins, 3; Evaluation of cesium accumulation effect on lifetime of fuel cladding tube

Ikusawa, Yoshihisa ; Uwaba, Tomoyuki ; Tanno, Takashi ; Oka, Hiroshi ; Kaito, Takeji ; Nemoto, Junichi*

In high burnup MOX fuel pins, cesium accumulates at the UO $_{2}$ - MOX pellet boundary and cladding tube diameter is locally increased around the position by FCMI, due to the formation of Cs-U-O compound. Based on the computation results obtained using an irradiation behavior analysis code "CEDAR", we evaluated the effect of this behavior on cladding creep damage. As the computation result, it was found that the cladding creep damage around the UO $_{2}$ - MOX pellet boundary increases by the FCMI stress.

Language	:	Japanese
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Meeting title	:	日本原子力学会2017年秋の大会
Held date	:	2017/09
Location (city)	:	札幌
Location (country)	:	日本
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Keywords	:	高速炉; Cs; 高燃焼度; FCMI; MOX; クリープ損傷
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Registration No. : BB20170685
JAEA Abstracts No. :
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