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JAEA Reports

Application of FORNAX-A

Aihara, Jun; Ueta, Shohei; Nishihara, Tetsuo

JAEA-Technology 2015-040, 32 Pages, 2016/02

JAEA-Technology-2015-040.pdf:0.83MB

Original FORNAX-A is a calculation code for amount of fission product (FP) released from fuel rods of pin-in-type high temperature gas-cooled reactors (HTGRs). This report is for explanation what calculations become possible with minor changed FORNAX-A.

Journal Articles

Research and development of ZrC-coated UO$$_{2}$$ particle fuel in Japan Atomic Energy Research Institute

; Ikawa, Katsuichi; ; ; Iwamoto, K.

Nuclear Fuel Performance, p.163 - 169, 1985/00

no abstracts in English

Journal Articles

Fission product diffusion in ZrC coated fuel particles

; Ikawa, Katsuichi; Iwamoto, K.

Journal of Nuclear Materials, 87(2&3), p.367 - 374, 1979/00

 Times Cited Count:18

no abstracts in English

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