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Preparation and characterization of the simulated burnup americium; Containing uranium-plutonium mixed oxide fuel

模擬燃焼アメリシウム含有MOX燃料の調製と特性評価

田中 康介; 逢坂 正彦; 三輪 周平; 廣沢 孝志; 黒崎 健*; 牟田 浩明*; 宇埜 正美*; 山中 伸介*

Tanaka, Kosuke; Osaka, Masahiko; Miwa, Shuhei; Hirosawa, Takashi; Kurosaki, Ken*; Muta, Hiroaki*; Uno, Masayoshi*; Yamanaka, Shinsuke*

模擬低除染酸化物燃料を調製し、相状態評価及び弾性率,融点測定を実施し、低除染酸化物燃料の高燃焼度領域での特性を評価した。

In order to investigate the effect on fuel thermophysical properties when adding americium and selected fission products to uranium-plutonium mixed fuel, simulated low decontamination MOX fuel with high burn-ups to 250 GWd/t, has been prepared and subjected to characterization tests, elastic moduli measurements, melting temperature measurement.

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パーセンタイル:48.35

分野:Materials Science, Multidisciplinary

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