Development of fabrication technology of U-Pu-Zr alloy fuel slug, 3; Injection casting tests of U-8.5wt%-10wt%Zr alloy

Nakamura, Kinya*; Yokoo, Takeshi*; Iwai, Takashi; Arai, Yasuo

Uranium-plutonium-zirconium alloy is one of the candidate nuclear fuels for fast reactors. Development of fabrication technology is progressing and irradiation tests of the U-Pu-Zr alloy fuel pins in JOYO fast reactor are scheduled in collaboration with Central Research Institute of Electric Power Industry and Japan Atomic Energy Agency. As a result of the first injection castingtest of U-Pu-Zr alloy slug in Japan, the cast alloy slug met with target specifications such as length, diameter and chemical composition.

Language	:	Japanese
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Meeting title	:	日本原子力学会2006年春の年会
Held date	:	2006/03
Location (city)	:	大洗
Location (country)	:	日本
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Keywords	:	no keyword
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Article of JAEA R&D Review	:
Cooperating Institute	:	電力中央研究所

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Registration No. : BB20050820
JAEA Abstracts No. :
Paper Submission No. :

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