研究者
J-GLOBAL ID:201801008115683224
更新日: 2024年08月20日
方野 量太
Katano Ryota
所属機関・部署:
論文 (10件):
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Cheol Ho Pyeon, Akito Oizumi, Ryota Katano, Masahiro Fukushima. Uncertainty Quantification of 237 Np, 241 Am, and 243 Am Reaction Rates in Highly Enriched Uranium Fuel Cores at Kyoto University Critical Assembly. Nuclear Science and Engineering. 2024. 1-16
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Ryota Katano, Akito Oizumi, Masahiro Fukushima, Cheol Ho Pyeon, Akio Yamamoto, Tomohiro Endo. Impact of Uncertainty Reduction on Lead-Bismuth Coolant in Accelerator-Driven System Using Sample Reactivity Experiments. Nuclear Science and Engineering. 2023. 1-20
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Cheol Ho Pyeon, Ryota Katano, Akito Oizumi, Masahiro Fukushima. Void Reactivity in Lead and Bismuth Sample Reactivity Experiments at Kyoto University Critical Assembly. Nuclear Science and Engineering. 2023. 197. 11. 1-18
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Ryota Katano, Akio Yamamoto, Tomohiro Endo. Sensitivity Coefficient Evaluation of an Accelerator-Driven System Using ROM-Lasso Method. Nuclear Science and Engineering. 2022. 196. 10. 1194-1208
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Ryota Katano, Masao Yamanaka, Cheol Ho Pyeon. Measurement of prompt neutron decay constant with spallation neutrons at Kyoto University Critical Assembly using linear combination method. JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY. 2020. 57. 2. 169-176
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MISC (9件):
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Ryota Katano, Akio Yamamoto, Tomohiro Endo. Proposal and Application of ROM-Lasso Method for Sensitivity Coefficient Evaluation. Proceedings of International Conference on Physics of Reactors 2022 (PHYSOR 2022). 2022. 2032-2041
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岩元大樹, 明午伸一郎, 中野敬太, YEE-RENDON,B., 方野量太, 菅原隆徳, 西原健司, 佐々敏信, 前川藤夫. 加速器駆動システム上部構造の放射線遮蔽解析. 日本原子力研究開発機構JAEA-Research(Web). 2022. 2021-012
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辻本和文, 西原健司, 福島昌宏, 田澤勇次郎, 江口悠太, 菅原隆徳, 大泉昭人, 方野量太, 岩元大樹. J-PARC核変換物理実験施設(TEF-P)安全設計書. 日本原子力研究開発機構JAEA-Technology(Web). 2018. 2017-033. WEB ONLY
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菅原隆徳, 方野量太, 辻本和文. 加速器駆動核変換システムの核設計に対する核変換サイクルの各プロセス中不純物核種の影響評価. 日本原子力学会秋の大会予稿集(CD-ROM). 2017. 2017
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R. Katano, A. Yamamoto, T. Endo. Application of Partially-Converged Solution of Assembly Calculation for Core Sensitivity Analysis based on Reduced Order Modeling. Trans. Am. Nucl. Soc. 2015. 113. 1161-1164
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