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西山潤 2019年 研究業績一覧 (12件 / 133件)
論文
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Takeshi Muramoto,
Jun Nishiyama,
Toru Obara.
Numerical analysis of criticality of fuel debris falling in water,
Annals of Nuclear Energy,
Vol. 131,
pp. 112-122,
Mar. 2019.
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Kazuki Kuwagaki,
Jun Nishiyama,
Toru Obara.
Concept of breed and burn reactor with spiral fuel shuffling,
Annals of Nuclear Energy,
Vol. 127,
pp. 130-138,
Jan. 2019.
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Hiroki Osato,
Jun Nishiyama,
Toru Obara.
Application of Melt-refining Process to Transition State of CANDLE Burning Fast Reactor,
Annals of Nuclear Energy,
Vol. 128,
pp. 77-83,
Jan. 2019.
著書
国際会議発表 (査読有り)
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Kazuki Kuwagaki,
Jun Nishiyama,
Toru Obara.
Thermal Hydraulic Analysis for a Breed and Burn Core with Spiral Fuel Shuffling,
Reactor Physics Asia Conference 2019 (RPHA19),
Proc. of Reactor Physics Asia Conference 2019 (RPHA19),
RPHA19-1087,
Dec. 2019.
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Kodai Fukuda,
Jun Nishiyama,
Toru Obara.
Radiation Dose by Criticality Accidents of Fuel Debris in Water,
Reactor Physics Asia Conference 2019 (RPHA19),
Proc. of Reactor Physics Asia Conference 2019 (RPHA19),
RPHA19-1092,
Dec. 2019.
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Takeshi Muramoto,
Jun Nishiyama,
Toru Obara.
Development of Criticality Safety Evaluation Method Based on the Actual Dynamic Behavior of the Fuel Debris in Water,
Reactor Physics Asia Conference 2019 (RPHA19),
Proc. of Reactor Physics Asia Conference 2019 (RPHA19),
RPHA19-1091,
Dec. 2019.
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Hoang Hai Nguyen,
Jun Nishiyama,
Toru Obara.
Monte Carlo Based Analysis for CANDLE Burning Reactor,
Reactor Physics Asia Conference 2019 (RPHA19),
Proc. of Reactor Physics Asia Conference 2019 (RPHA19),
RPHA19-1088,
Dec. 2019.
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Kodai Fukuda,
Delgersaikhan Tuya,
Jun Nishiyama,
Toru Obara.
Supercritical kinetic analysis in a simple fuel debris system by MIK code,
ICNC2019 – 11th International Conference on Nuclear Criticality Safety,
Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety,
A93242KF,
Sept. 2019.
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Takeshi Muramoto,
Jun Nishiyama,
Toru Obara.
Numerical analysis of criticality of fuel debris falling in water by coupling computational fluid dynamics and the continuous energy Monte Carlo code,
ICNC2019 – 11th International Conference on Nuclear Criticality Safety,
Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety,
A93049MT,
Sept. 2019.
国内会議発表 (査読なし・不明)
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大里 洋輝,
西山 潤,
小原 徹.
メルトリファイニング法のCANDLE 燃焼高速炉の移行過程への適用,
日本原子力学会2019春の大会,
日本原子力学会2019春の大会予稿集,
1K11,
Mar. 2019.
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斉藤 雪子,
西山 潤,
小原 徹.
ブリードアンドバーン型高速炉における燃料および冷却材組成が燃焼特性に与える効果,
日本原子力学会2019春の大会,
日本原子力学会2019春の大会予稿集,
1K10,
Mar. 2019.
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