Blanket fuel with high proliferation resistance in fast breeder reactor, 15; Prediction of irradiation behavior of DU-Am pellets

Shiba, Tomooki*; Sagara, Hiroshi*; Han, C. Y.*; Saito, Masaki*; Onishi, Takashi ; Koyama, Shinichi ; Maeda, Shigetaka

The design consideration of hypothetical depleted U and Am (DU-Am) oxide fuel pin was performed to produce Pu with high proliferation resistance in fast breeder reactors. As a result, DU-Am oxide fuel pellet with large diameter under epithermal neutron spectrum is desirable for the production of denatured Pu.

Language	:	Japanese
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Meeting title	:	日本原子力学会2013年秋の大会
Held date	:	2013/09
Location (city)	:	八戸
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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Article of JAEA R&D Review	:
Cooperating Institute	:	東京工業大学

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Registration No. : BB20130822
JAEA Abstracts No. :
Paper Submission No. :

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