山本 俊弘

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氏名(漢字/フリガナ/アルファベット表記)
山本 俊弘/ヤマモト トシヒロ/Yamamoto, Toshihiro
所属部署・職名(部局/所属/講座等/職名)
複合原子力科学研究所/原子力基礎工学研究部門/准教授
協力講座
部局 所属 講座等 職名
工学研究科 原子核工学専攻 核システム工学講座 准教授
連絡先住所
種別 住所(日本語) 住所(英語)
職場 大阪府泉南郡熊取町朝代西2-1010 2-1010 Asashiro-nishi, Kumatori-cho, Sennan-gun, Osaka
所属学会(国内)
学会名(日本語) 学会名(英語)
一般社団法人 日本原子力学会 Atomic Energy Society of Japan
取得学位
学位名(日本語) 学位名(英語) 大学(日本語) 大学(英語) 取得区分
工学修士 大阪大学
博士(工学) 大阪大学
researchmap URL
https://researchmap.jp/215612
研究テーマ
(日本語)
研究炉安全管理工学分野
(英語)
Research Reactor Safety
研究概要
(日本語)
京都大学研究炉KURの安全管理に関する研究。原子炉物理の計算法に関する研究。
(英語)
Research on Safety of Kyoto University Reactor. Research on Calculation Method of Reactor Physics.
研究分野(キーワード)
キーワード(日本語) キーワード(英語)
原子炉 Reactor
原子炉物理 Reactor physics
論文
著者 著者(日本語) 著者(英語) タイトル タイトル(日本語) タイトル(英語) 書誌情報等 書誌情報等(日本語) 書誌情報等(英語) 出版年月 査読の有無 記述言語 掲載種別 公開
Toshihiro Yamamoto, Hiroki Sakamoto Toshihiro Yamamoto, Hiroki Sakamoto Toshihiro Yamamoto, Hiroki Sakamoto Monte Carlo sensitivity analysis method for the effective delayed neutron fraction with the differential operator sampling method Monte Carlo sensitivity analysis method for the effective delayed neutron fraction with the differential operator sampling method Monte Carlo sensitivity analysis method for the effective delayed neutron fraction with the differential operator sampling method Annals of Nuclear Energy, 140 Annals of Nuclear Energy, 140 Annals of Nuclear Energy, 140 2020/06 英語 研究論文(学術雑誌) 公開
Xu Han, Xiuzhong Shen, Toshihiro Yamamoto, Ken Nakajima, Haomin Sun, Takashi Hibiki Xu Han, Xiuzhong Shen, Toshihiro Yamamoto, Ken Nakajima, Haomin Sun, Takashi Hibiki Xu Han, Xiuzhong Shen, Toshihiro Yamamoto, Ken Nakajima, Haomin Sun, Takashi Hibiki Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 × 6 rod bundle Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 × 6 rod bundle Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 × 6 rod bundle International Journal of Heat and Mass Transfer, 144 International Journal of Heat and Mass Transfer, 144 International Journal of Heat and Mass Transfer, 144 2019/12 研究論文(学術雑誌) 公開
山本 俊弘, 坂本 浩紀 山本 俊弘, 坂本 浩紀 Toshihiro Yamamoto, Hiroki Sakamoto Decomposition of neutron noise in a reactor into higher-order mode components and investigation of the space and frequency dependence Decomposition of neutron noise in a reactor into higher-order mode components and investigation of the space and frequency dependence Decomposition of neutron noise in a reactor into higher-order mode components and investigation of the space and frequency dependence Progress in Nuclear Energy, 117 Progress in Nuclear Energy, 117 Progress in Nuclear Energy, 117 2019/11 英語 研究論文(学術雑誌) 公開
山本 俊弘, 坂本 浩紀 山本 俊弘, 坂本 浩紀 Toshihiro Yamamoto, Hiroki Sakamoto Two-step Monte Carlo sensitivity analysis of alpha- and gammaeigenvalues with the differential operator sampling method Two-step Monte Carlo sensitivity analysis of alpha- and gammaeigenvalues with the differential operator sampling method Two-step Monte Carlo sensitivity analysis of alpha- and gamma-eigenvalues with the differential operator sampling method Annals of Nuclear Energy, 133, 100-109 Annals of Nuclear Energy, 133, 100-109 Annals of Nuclear Energy, 133, 100-109 2019/11 英語 研究論文(学術雑誌) 公開
Alberto Talamo, Yoursry Gohar, 山本俊弘, 山中正朗, 卞哲浩 Alberto Talamo, Yoursry Gohar, 山本俊弘, 山中正朗, 卞哲浩 Alberto Talamo, Yoursry Gohar, Toshihiro Yamamoto, Masao Yamanaka, Cheol Ho Pyeon Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors Annals of Nuclear Energy, 131, 138-147 Annals of Nuclear Energy, 131, 138-147 Annals of Nuclear Energy, 131, 138-147 2019/09 英語 研究論文(学術雑誌) 公開
山本 俊弘, 坂本浩紀 山本 俊弘, 坂本浩紀 Toshihiro Yamamoto, Hiroki Sakamoto A Monte Carlo technique for sensitivity analysis of alpha-eigenvalue with the differential operator sampling method A Monte Carlo technique for sensitivity analysis of alpha-eigenvalue with the differential operator sampling method A Monte Carlo technique for sensitivity analysis of alpha-eigenvalue with the differential operator sampling method Annals of Nuclear Energy, 127, 178-187 Annals of Nuclear Energy, 127, 178-187 Annals of Nuclear Energy, 127, 178-187 2019/05 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Hiroki Sakamoto Toshihiro Yamamoto, Hiroki Sakamoto Toshihiro Yamamoto, Hiroki Sakamoto Monte Carlo method for solving a B<inf>1</inf> equation with complex-valued buckling in asymmetric geometries and generation of directional diffusion coefficients Monte Carlo method for solving a B<inf>1</inf> equation with complex-valued buckling in asymmetric geometries and generation of directional diffusion coefficients Monte Carlo method for solving a B<inf>1</inf> equation with complex-valued buckling in asymmetric geometries and generation of directional diffusion coefficients Annals of Nuclear Energy, 122, 37-46 Annals of Nuclear Energy, 122, 37-46 Annals of Nuclear Energy, 122, 37-46 2018/12 英語 研究論文(学術雑誌) 公開
山本 俊弘, 坂本 浩紀 山本 俊弘, 坂本 浩紀 Toshihiro Yamamoto, Hiroki Sakamoto Effect of Higher Harmonics in the Area-Ratio Pulsed Neutron Source Technique Effect of Higher Harmonics in the Area-Ratio Pulsed Neutron Source Technique Effect of higher harmonics in the area-ratio pulsed neutron source technique Progress in Nuclear Energy, 108, 286-294 Progress in Nuclear Energy, 108, 286-294 Progress in Nuclear Energy, 108, 286-294 2018/09 英語 研究論文(学術雑誌) 公開
山本 俊弘, 坂本 浩紀 山本 俊弘, 坂本 浩紀 Toshihiro Yamamoto Monte Carlo perturbation methods using ‘‘virtual density” theory for calculating reactivity due to geometry change Monte Carlo perturbation methods using ‘‘virtual density” theory for calculating reactivity due to geometry change Monte Carlo perturbation methods using “virtual density” theory for calculating reactivity due to geometry change Annals of Nuclear Energy, 119, 362-373 Annals of Nuclear Energy, 119, 362-373 Annals of Nuclear Energy, 119, 362-373 2018/09 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Implementation of a frequency-domain neutron noise analysis method in a production-level continuous energy Monte Carlo code: Verification and application in a BWR Implementation of a frequency-domain neutron noise analysis method in a production-level continuous energy Monte Carlo code: Verification and application in a BWR Implementation of a frequency-domain neutron noise analysis method in a production-level continuous energy Monte Carlo code: Verification and application in a BWR Annals of Nuclear Energy, 115, 494-501 , 115, 494-501 Annals of Nuclear Energy, 115, 494-501 2018/05 英語 研究論文(学術雑誌) 公開
Hironobu Unesaki, Tsuyoshi Misawa, Ken Nakajima, Hirotoshi Uebayashi, Jun-Ichi Hori, Toshihiro Yamamoto, Hiroshi Shiga, Katsuhiro Kamae Hironobu Unesaki, Tsuyoshi Misawa, Ken Nakajima, Hirotoshi Uebayashi, Jun-Ichi Hori, Toshihiro Yamamoto, Hiroshi Shiga, Katsuhiro Kamae Hironobu Unesaki, Tsuyoshi Misawa, Ken Nakajima, Hirotoshi Uebayashi, Jun-Ichi Hori, Toshihiro Yamamoto, Hiroshi Shiga, Katsuhiro Kamae ON THE REASSESSMENT OF SAFETY ASSESSMENT REPORTS AND THE RESTART OF UNIVERSITY RESEARCH REACTORS IN JAPAN ON THE REASSESSMENT OF SAFETY ASSESSMENT REPORTS AND THE RESTART OF UNIVERSITY RESEARCH REACTORS IN JAPAN ON THE REASSESSMENT OF SAFETY ASSESSMENT REPORTS AND THE RESTART OF UNIVERSITY RESEARCH REACTORS IN JAPAN European Research Reactor Conference RRFM 2018 European Research Reactor Conference RRFM 2018 European Research Reactor Conference RRFM 2018 2018/03 英語 研究論文(国際会議プロシーディングス) 公開
山本 俊弘 山本 俊弘 Toshihiro Yamamoto Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method Annals of Nuclear Energy, 112, 150-157 , 112, 150-157 Annals of Nuclear Energy, 112, 150-157 2018/02 英語 研究論文(学術雑誌) 公開
山本 俊弘 山本 俊弘 Toshihiro Yamamoto Time-dependent Monte Carlo simulations for neutron noise in void-containing water flow Time-dependent Monte Carlo simulations for neutron noise in void-containing water flow Time-dependent Monte Carlo simulations for neutron noise in void-containing water flow Progress in Nuclear Energy, 101, 270-278 Progress in Nuclear Energy, 101, 270-278 Progress in Nuclear Energy, 101, 270-278 2017/11 英語 研究論文(学術雑誌) 公開
坂本浩紀, 山本 俊弘 坂本浩紀, 山本 俊弘 Hiroki Sakamoto, Toshihiro Yamamoto Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems Journal of Computational Physics, 345, 245-259 Journal of Computational Physics, 345, 245-259 Journal of Computational Physics, 345, 245-259 2017/09/15 英語 研究論文(学術雑誌) 公開
山本 俊弘, 坂本浩紀 山本 俊弘, 坂本浩紀 Toshihiro Yamamoto, Hiroki Sakamoto New findings on neutron noise propagation properties in void containing water using neutron transport calculations New findings on neutron noise propagation properties in void containing water using neutron transport calculations New findings on neutron noise propagation properties in void containing water using neutron noise transport calculations Progress in Nuclear Energy, 90, 58-68 Progress in Nuclear Energy, 90, 58-68 Progress in Nuclear Energy, 90, 58-68 2016/07/01 英語 研究論文(学術雑誌) 公開
山本 俊弘, 坂本浩紀 山本 俊弘, 坂本浩紀 Toshihiro Yamamoto, Hiroki Sakamoto Frequency domain optical tomography using a Monte Carlo perturbation method Frequency domain optical tomography using a Monte Carlo perturbation method Frequency domain optical tomography using a Monte Carlo perturbation method Optics Communications, 364, 165-176 Optics Communications, 364, 165-176 Optics Communications, 364, 165-176 2016/04 英語 研究論文(学術雑誌) 公開
山本 俊弘 山本 俊弘 Toshihiro Yamamoto, Hiroki Sakamoto Dynamic Monte Carlo calculation method by solving frequency domain transport equation using the complex-valued weight Monte Carlo method Dynamic Monte Carlo calculation method by solving frequency domain transport equation using the complex-valued weight Monte Carlo method Dynamic Monte Carlo calculation method by solving frequency domain transport equation using the complex-valued weight Monte Carlo method Annals of Nuclear Energy, 85, 426-433 Annals of Nuclear Energy, 85, 426-433 Annals of Nuclear Energy, 85, 426-433 2015/11 英語 研究論文(学術雑誌) 公開
Ken Nakajima, Tadafumi Sano, Toshihiro Yamamoto Ken Nakajima, Tadafumi Sano, Toshihiro Yamamoto Ken Nakajima, Tadafumi Sano, Toshihiro Yamamoto Validation of <sup>241</sup>Am Capture Cross Section through Integral Test Using Criticality Data of Light-water Moderated MOX Cores Validation of <sup>241</sup>Am Capture Cross Section through Integral Test Using Criticality Data of Light-water Moderated MOX Cores Validation of <sup>241</sup>Am Capture Cross Section through Integral Test Using Criticality Data of Light-water Moderated MOX Cores Energy Procedia, 71, 237-243 Energy Procedia, 71, 237-243 Energy Procedia, 71, 237-243 2015/05/01 研究論文(国際会議プロシーディングス) 公開
Jian Zhang, Xiuzhong Shen, Yasuyuki Fujihara, Tadafumi Sano, Toshihiro Yamamoto, Ken Nakajima Jian Zhang, Xiuzhong Shen, Yasuyuki Fujihara, Tadafumi Sano, Toshihiro Yamamoto, Ken Nakajima Jian Zhang, Xiuzhong Shen, Yasuyuki Fujihara, Tadafumi Sano, Toshihiro Yamamoto, Ken Nakajima Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode Annals of Nuclear Energy, 76, 410-420 Annals of Nuclear Energy, 76, 410-420 Annals of Nuclear Energy, 76, 410-420 2015/02 研究論文(学術雑誌) 公開
山本 俊弘 山本 俊弘 Toshihiro Yamamoto Higher harmonic analyses of the 252Cf source driven noise analysis method Higher harmonic analyses of the 252Cf source driven noise analysis method Higher harmonic analyses of the <sup>252</sup>Cf source driven noise analysis method Annals of Nuclear Energy, 76, 521-529 Annals of Nuclear Energy, 76, 521-529 Annals of Nuclear Energy, 76, 521-529 2015/02 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Theory of power spectral density and feynman-alpha method in accelerator-driven system and their higher-order mode effects Theory of power spectral density and feynman-alpha method in accelerator-driven system and their higher-order mode effects Theory of power spectral density and feynman-alpha method in accelerator-driven system and their higher-order mode effects Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, 119-128 Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, 119-128 Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, 119-128 2015/01/01 公開
山本 俊弘 山本 俊弘 Toshihiro Yamamoto, Hiroki Sakamoto A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbation A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbation A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbation Annals of Nuclear Energy, 71, 480-488 Annals of Nuclear Energy, 71, 480-488 Annals of Nuclear Energy, 71, 480-488 2014/09 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Higher order mode analyses of power spectral density and Feynman-α method in accelerator driven system with periodically pulsed spallation neutron source Higher order mode analyses of power spectral density and Feynman-α method in accelerator driven system with periodically pulsed spallation neutron source Higher order mode analyses of power spectral density and Feynman-α method in accelerator driven system with periodically pulsed spallation neutron source Annals of Nuclear Energy, 66, 63-73 Annals of Nuclear Energy, 66, 63-73 Annals of Nuclear Energy, 66, 63-73 2014/04 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Frequency domain Monte Carlo simulation method for cross power spectral density driven by periodically pulsed spallation neutron source using complex-valued weight Monte Carlo Frequency domain Monte Carlo simulation method for cross power spectral density driven by periodically pulsed spallation neutron source using complex-valued weight Monte Carlo Frequency domain Monte Carlo simulation method for cross power spectral density driven by periodically pulsed spallation neutron source using complex-valued weight Monte Carlo Annals of Nuclear Energy, 63, 711-720 Annals of Nuclear Energy, 63, 711-720 Annals of Nuclear Energy, 63, 711-720 2014 英語 研究論文(学術雑誌) 公開
山本 俊弘 山本 俊弘 Toshihiro Yamamoto Heterogeneity effect on neutron shielding in borated concrete and Monte Carlo-based cross section homogenization method for particle dispersed media Heterogeneity effect on neutron shielding in borated concrete and Monte Carlo-based cross section homogenization method for particle dispersed media Heterogeneity effect on neutron shielding in borated concrete and Monte Carlo-based cross section homogenization method for particle dispersed media Progress in Nuclear Science and Technology, 4, 404-407 Progress in Nuclear Science and Technology, 4, 404-407 Progress in Nuclear Science and Technology, 4, 404-407 2014 英語 研究論文(学術雑誌) 公開
内藤俶孝, 山本俊弘, 三澤毅, 山根祐一 内藤俶孝, 山本俊弘, 三澤毅, 山根祐一 Yoshitaka Naito, Toshihiro Yamamoto, Tsuyoshi Misawa, Yuichi Yamane Review of studies on criticality safety evaluation and criticality experiment methods Review of studies on criticality safety evaluation and criticality experiment methods Review of studies on criticality safety evaluation and criticality experiment methods Journal of Nuclear Science and Technology, 50, 11, 1045-1061 Journal of Nuclear Science and Technology, 50, 11, 1045-1061 Journal of Nuclear Science and Technology, 50, 11, 1045-1061 2013/11/01 英語 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Monte Carlo method with complex-valued weights for frequency domain analyses of neutron noise Monte Carlo method with complex-valued weights for frequency domain analyses of neutron noise Monte Carlo method with complex-valued weights for frequency domain analyses of neutron noise Annals of Nuclear Energy, 58, 72-79 Annals of Nuclear Energy, 58, 72-79 Annals of Nuclear Energy, 58, 72-79 2013 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Energy-higher order mode analyses in Feynman-α method Energy-higher order mode analyses in Feynman-α method Energy-higher order mode analyses in Feynman-α method Annals of Nuclear Energy, 57, 84-91 Annals of Nuclear Energy, 57, 84-91 Annals of Nuclear Energy, 57, 84-91 2013 英語 研究論文(学術雑誌) 公開
中森輝, 佐野忠史, ZHANG Jian, 藤原靖幸, 山本俊弘, 中島健 中森輝, 佐野忠史, ZHANG Jian, 藤原靖幸, 山本俊弘, 中島健 NAKAMORI AKIRA, SANO TADAFUMI, ZHANG JIAN, FUJIHARA YASUYUKI, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN KUR反応度測定システムの開発とその適用 KUR反応度測定システムの開発とその適用 KUR反応度測定システムの開発とその適用 KURRI KR, 176, 78-83 KURRI KR, 176, 78-83 KURRI KR, 176, 78-83 2013/01 日本語 研究論文(研究会、シンポジウム資料等) 公開
佐野忠史, 藤原泰幸, ZHANG Jian, 高橋佳之, 中森輝, 山本俊弘, 中島健 佐野忠史, 藤原泰幸, ZHANG Jian, 高橋佳之, 中森輝, 山本俊弘, 中島健 SANO TADAFUMI, FUJIHARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, NAKAMORI AKIRA, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN KURの微調整棒に対する粗調整棒の制御棒干渉効果の測定 KURの微調整棒に対する粗調整棒の制御棒干渉効果の測定 KURの微調整棒に対する粗調整棒の制御棒干渉効果の測定 KURRI KR, 176, 51-56 KURRI KR, 176, 51-56 KURRI KR, 176, 51-56 2013/01 日本語 研究論文(研究会、シンポジウム資料等) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Monte Carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations Monte Carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations Monte Carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations Annals of Nuclear Energy, 50, 141-149 Annals of Nuclear Energy, 50, 141-149 Annals of Nuclear Energy, 50, 141-149 2012/12 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Monte Carlo algorithm for buckling search and neutron leakage-corrected calculations Monte Carlo algorithm for buckling search and neutron leakage-corrected calculations Monte Carlo algorithm for buckling search and neutron leakage-corrected calculations Annals of Nuclear Energy, 47, 14-20 Annals of Nuclear Energy, 47, 14-20 Annals of Nuclear Energy, 47, 14-20 2012/09 英語 研究論文(学術雑誌) 公開
藤原靖幸, 佐野忠史, ZHANG Jian, 高橋佳之, 山本俊弘, 中島健 藤原靖幸, 佐野忠史, ZHANG Jian, 高橋佳之, 山本俊弘, 中島健 FUJIWARA YASUYUKI, SANO TADAFUMI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN KUR炉心内照射領域における中性子束測定 KUR炉心内照射領域における中性子束測定 KUR炉心内照射領域における中性子束測定 京都大学原子炉実験所学術講演会報文集, 46th, 73-78 京都大学原子炉実験所学術講演会報文集, 46th, 73-78 京都大学原子炉実験所学術講演会報文集, 46th, 73-78 2012/01 日本語 研究論文(研究会、シンポジウム資料等) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Higher Order α Mode Eigenvalue Calculation by Monte Carlo Power Iteration Higher Order α Mode Eigenvalue Calculation by Monte Carlo Power Iteration Higher Order α Mode Eigenvalue Calculation by Monte Carlo Power Iteration Progress in Nuclear Science and Technology, 2 Progress in Nuclear Science and Technology, 2 Progress in Nuclear Science and Technology, 2 2012 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Non-regionwise weight cancellation for Monte Carlo higher order criticality calculations using kernel density estimator Non-regionwise weight cancellation for Monte Carlo higher order criticality calculations using kernel density estimator Non-regionwise weight cancellation for Monte Carlo higher order criticality calculations using kernel density estimator Annals of Nuclear Energy, 38, 11, 2515-2520 Annals of Nuclear Energy, 38, 11, 2515-2520 Annals of Nuclear Energy, 38, 11, 2515-2520 2011/11 英語 研究論文(学術雑誌) 公開
YAMAMOTO Toshihiro YAMAMOTO Toshihiro Higher Order .ALPHA. Mode Eigenvalue Calculation by Monte Carlo Power Iteration Higher Order .ALPHA. Mode Eigenvalue Calculation by Monte Carlo Power Iteration Prog Nucl Sci Technol (Web), 2, WEB ONLY 826-835 Prog Nucl Sci Technol (Web), 2, WEB ONLY 826-835 , 2, WEB ONLY 826-835 2011/10 英語 研究論文(学術雑誌) 公開
T. Yamamoto T. Yamamoto Toshihiro Yamamoto Higher order mode analyses in Feynman-α method Higher order mode analyses in Feynman-α method Higher order mode analyses in Feynman-α method Annals of Nuclear Energy, 38, 6, 1231-1237 Annals of Nuclear Energy, 38, 6, 1231-1237 Annals of Nuclear Energy, 38, 6, 1231-1237 2011/06 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Applicability of non-analog Monte Carlo technique to reactor noise simulation Applicability of non-analog Monte Carlo technique to reactor noise simulation Applicability of non-analog Monte Carlo technique to reactor noise simulation Annals of Nuclear Energy, 38, 2-3, 647-655 Annals of Nuclear Energy, 38, 2-3, 647-655 Annals of Nuclear Energy, 38, 2-3, 647-655 2011/02 英語 研究論文(学術雑誌) 公開
佐野忠史, 藤原靖幸, ZHANG Jian, 高橋佳之, 大野和臣, 丸山直矢, 山本俊弘, 中島健 佐野忠史, 藤原靖幸, ZHANG Jian, 高橋佳之, 大野和臣, 丸山直矢, 山本俊弘, 中島健 SANO TADAFUMI, FUJIHARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, MARUYAMA NAOYA, YAMAMOTO TOSHIHIRO, NAKAJIMA KEN 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(2)各種反応度測定 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(2)各種反応度測定 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(2)各種反応度測定 京都大学原子炉実験所学術講演会報文集, 45th, 82-87 京都大学原子炉実験所学術講演会報文集, 45th, 82-87 京都大学原子炉実験所学術講演会報文集, 45th, 82-87 2011/01 日本語 研究論文(研究会、シンポジウム資料等) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Study on double heterogeneity effect of Pu-rich agglomerates in mixed oxide fuel using cross section homogenization method for particle-dispersed media Study on double heterogeneity effect of Pu-rich agglomerates in mixed oxide fuel using cross section homogenization method for particle-dispersed media Study on double heterogeneity effect of Pu-rich agglomerates in mixed oxide fuel using cross section homogenization method for particle-dispersed media Annals of Nuclear Energy, 37, 3, 398-405 Annals of Nuclear Energy, 37, 3, 398-405 Annals of Nuclear Energy, 37, 3, 398-405 2010/03 英語 研究論文(学術雑誌) 公開
Kotaro Tonoike, Toshihiro Yamamoto, Yoshinori Miyoshi, Gunzo Uchiyama, Shouichi Watanabey Kotaro Tonoike, Toshihiro Yamamoto, Yoshinori Miyoshi, Gunzo Uchiyama, Shouichi Watanabey Kotaro Tonoike, Toshihiro Yamamoto, Yoshinori Miyoshi, Gunzo Uchiyama, Shouichi Watanabey Benchmarkcritical experiments and FP worth evaluation fora heterogeneous system of uranium fuel rods and uranium solution poisoned with pseudo-fission-product elements Benchmarkcritical experiments and FP worth evaluation fora heterogeneous system of uranium fuel rods and uranium solution poisoned with pseudo-fission-product elements Benchmarkcritical experiments and FP worth evaluation fora heterogeneous system of uranium fuel rods and uranium solution poisoned with pseudo-fission-product elements Journal of Nuclear Science and Technology, 46, 4, 354-365 Journal of Nuclear Science and Technology, 46, 4, 354-365 Journal of Nuclear Science and Technology, 46, 4, 354-365 2009/04 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Convergence of the second eigenfunction in Monte Carlo power iteration Convergence of the second eigenfunction in Monte Carlo power iteration Convergence of the second eigenfunction in Monte Carlo power iteration ANNALS OF NUCLEAR ENERGY, 36, 1, 7-14 ANNALS OF NUCLEAR ENERGY, 36, 1, 7-14 ANNALS OF NUCLEAR ENERGY, 36, 1, 7-14 2009/01 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Extension of cross section homogenization method for particle-dispersed media to layered particles Extension of cross section homogenization method for particle-dispersed media to layered particles Extension of cross section homogenization method for particle-dispersed media to layered particles Annals of Nuclear Energy, 33, 9, 804-812 Annals of Nuclear Energy, 33, 9, 804-812 Annals of Nuclear Energy, 33, 9, 804-812 2006/06 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Yoshinori Miyoshi, Toshikazu Takeda Toshihiro Yamamoto, Yoshinori Miyoshi, Toshikazu Takeda Toshihiro Yamamoto, Yoshinori Miyoshi, Toshikazu Takeda Extension of effective cross section calculation method for neutron transport calculations in particle-dispersed media Extension of effective cross section calculation method for neutron transport calculations in particle-dispersed media Extension of effective cross section calculation method for neutron transport calculations in particle-dispersed media Journal of Nuclear Science and Technology, 43, 1, 77-87 Journal of Nuclear Science and Technology, 43, 1, 77-87 Journal of Nuclear Science and Technology, 43, 1, 77-87 2006/01 英語 研究論文(学術雑誌) 公開
K. Sakurai, T. Yamamoto K. Sakurai, T. Yamamoto K. Sakurai, T. Yamamoto Education method on monte carlo analysis in atomic energy Education method on monte carlo analysis in atomic energy Education method on monte carlo analysis in atomic energy Transactions of the Atomic Energy Society of Japan, 4, 4, 248-258 Transactions of the Atomic Energy Society of Japan, 4, 4, 248-258 Transactions of the Atomic Energy Society of Japan, 4, 4, 248-258 2005 日本語 公開
K. Sakurai, T. Yamamoto K. Sakurai, T. Yamamoto K. Sakurai, T. Yamamoto A logic of Monte Carlo calculation =from experience to science A logic of Monte Carlo calculation =from experience to science A logic of Monte Carlo calculation =from experience to science Transactions of the Atomic Energy Society of Japan, 4, 3, 219-226 Transactions of the Atomic Energy Society of Japan, 4, 3, 219-226 Transactions of the Atomic Energy Society of Japan, 4, 3, 219-226 2005 日本語 公開
K. Sakurai, T. Yamamoto K. Sakurai, T. Yamamoto K. Sakurai, T. Yamamoto A estimation methods of lower weight bound on neutron deep penetration problem with Monte Carlo method A estimation methods of lower weight bound on neutron deep penetration problem with Monte Carlo method A estimation methods of lower weight bound on neutron deep penetration problem with Monte Carlo method Transactions of the Atomic Energy Society of Japan, 4, 2, 172-176 Transactions of the Atomic Energy Society of Japan, 4, 2, 172-176 Transactions of the Atomic Energy Society of Japan, 4, 2, 172-176 2005 日本語 公開
Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Reliable method for fission source convergence of monte carlo criticality calculation with wielandt’s method Reliable method for fission source convergence of monte carlo criticality calculation with wielandt’s method Reliable method for fission source convergence of monte carlo criticality calculation with wielandt’s method Journal of Nuclear Science and Technology, 41, 2, 99-107 Journal of Nuclear Science and Technology, 41, 2, 99-107 Journal of Nuclear Science and Technology, 41, 2, 99-107 2004/02 英語 研究論文(学術雑誌) 公開
Kotaro Tonoike, Toshihiro Yamamoto, Shoichi Watanabe, Yoshinori Miyoshi Kotaro Tonoike, Toshihiro Yamamoto, Shoichi Watanabe, Yoshinori Miyoshi Kotaro Tonoike, Toshihiro Yamamoto, Shoichi Watanabe, Yoshinori Miyoshi Real time a value measurement with feynman-α method utilizing time series data acquisition on low enriched uranium system Real time a value measurement with feynman-α method utilizing time series data acquisition on low enriched uranium system Real time a value measurement with feynman-α method utilizing time series data acquisition on low enriched uranium system Journal of Nuclear Science and Technology, 41, 2, 177-182 Journal of Nuclear Science and Technology, 41, 2, 177-182 Journal of Nuclear Science and Technology, 41, 2, 177-182 2004/02 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Effect of mixing condition of MOX powder and additives on criticality safety Effect of mixing condition of MOX powder and additives on criticality safety Effect of mixing condition of MOX powder and additives on criticality safety Transactions of the American Nuclear Society, 91, 583-584 Transactions of the American Nuclear Society, 91, 583-584 Transactions of the American Nuclear Society, 91, 583-584 2004 英語 研究論文(国際会議プロシーディングス) 公開
M. Sakai, T. Yamamoto, M. Murazaki, Y. Miyoshi M. Sakai, T. Yamamoto, M. Murazaki, Y. Miyoshi M. Sakai, T. Yamamoto, M. Murazaki, Y. Miyoshi Effect of particulate behavior on criticality evaluation in agitating powder of nuclear fuel Effect of particulate behavior on criticality evaluation in agitating powder of nuclear fuel Effect of particulate behavior on criticality evaluation in agitating powder of nuclear fuel Powder Technology, 148, 1, 67-71 Powder Technology, 148, 1, 67-71 Powder Technology, 148, 1, 67-71 2004 英語 公開
Toshihiro Yamamoto, Yoshinori Miyoshi, Takehide Kiyosumi Toshihiro Yamamoto, Yoshinori Miyoshi, Takehide Kiyosumi Toshihiro Yamamoto, Yoshinori Miyoshi, Takehide Kiyosumi Validating JENDL-3.3 for water-reflected low-enriched uranium solution systems using STACY ICSBEP benchmark models Validating JENDL-3.3 for water-reflected low-enriched uranium solution systems using STACY ICSBEP benchmark models Validating JENDL-3.3 for water-reflected low-enriched uranium solution systems using STACY ICSBEP benchmark models Nuclear Science and Engineering, 145, 1, 132-144 Nuclear Science and Engineering, 145, 1, 132-144 Nuclear Science and Engineering, 145, 1, 132-144 2003/09 英語 研究論文(学術雑誌) 公開
Yuichi Yamane, Yoshinori Miyoshi, Shouichi Watanabe, Toshihiro Yamamoto Yuichi Yamane, Yoshinori Miyoshi, Shouichi Watanabe, Toshihiro Yamamoto Yuichi Yamane, Yoshinori Miyoshi, Shouichi Watanabe, Toshihiro Yamamoto Critical experiments on 10% enriched uranyl nitrate solution using an 80-cm-diameter cylindrical core Critical experiments on 10% enriched uranyl nitrate solution using an 80-cm-diameter cylindrical core Critical experiments on 10% enriched uranyl nitrate solution using an 80-cm-diameter cylindrical core Nuclear Technology, 141, 3, 221-232 Nuclear Technology, 141, 3, 221-232 Nuclear Technology, 141, 3, 221-232 2003/03 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Yoshinori Miyoshi, Kotaro Tonoike, Hajime Okamoto, Toshikazu Ida, Shigeaki Aoki Toshihiro Yamamoto, Yoshinori Miyoshi, Kotaro Tonoike, Hajime Okamoto, Toshikazu Ida, Shigeaki Aoki Toshihiro Yamamoto, Yoshinori Miyoshi, Kotaro Tonoike, Hajime Okamoto, Toshikazu Ida, Shigeaki Aoki Effect of higher-harmonic flux in exponential experiment for subcriticality measurement Effect of higher-harmonic flux in exponential experiment for subcriticality measurement Effect of higher-harmonic flux in exponential experiment for subcriticality measurement Journal of Nuclear Science and Technology, 40, 2, 77-83 Journal of Nuclear Science and Technology, 40, 2, 77-83 Journal of Nuclear Science and Technology, 40, 2, 77-83 2003/02 英語 研究論文(学術雑誌) 公開
三好慶典, 山本俊弘, 中島健 三好慶典, 山本俊弘, 中島健 MOX粉体燃料の臨界事故の簡易評価 MOX粉体燃料の臨界事故の簡易評価 JAERI-Research 2002-002, 0-0 JAERI-Research 2002-002, 0-0 , 0-0 2003 日本語 公開
Y. Miyoshi, T. Yamamoto, K. Tonoike, Y. Yamane Y. Miyoshi, T. Yamamoto, K. Tonoike, Y. Yamane Y. Miyoshi, T. Yamamoto, K. Tonoike, Y. Yamane Critical experiments of STACY homogeneous cores containing 10% enriched uranyl nitrate solution Critical experiments of STACY homogeneous cores containing 10% enriched uranyl nitrate solution Critical experiments of STACY homogeneous cores containing 10% enriched uranyl nitrate solution Proc. Int. Conf. on Nuclear Criticality Safety ICNC2003 Proc. Int. Conf. on Nuclear Criticality Safety ICNC2003 Proc. Int. Conf. on Nuclear Criticality Safety ICNC2003 2003 英語 研究論文(国際会議プロシーディングス) 公開
Ken Nakajima, Toshihiro Yamamoto, Yoshinori Miyoshi Ken Nakajima, Toshihiro Yamamoto, Yoshinori Miyoshi Ken Nakajima, Toshihiro Yamamoto, Yoshinori Miyoshi Modified quasi-steady-state method to evaluate the mean power profiles of nuclear excursions in fissile solution Modified quasi-steady-state method to evaluate the mean power profiles of nuclear excursions in fissile solution Modified quasi-steady-state method to evaluate the mean power profiles of nuclear excursions in fissile solution Journal of Nuclear Science and Technology, 39, 11, 1162-1168 Journal of Nuclear Science and Technology, 39, 11, 1162-1168 Journal of Nuclear Science and Technology, 39, 11, 1162-1168 2002/11 英語 研究論文(学術雑誌) 公開
Kotaro Tonoike, Yoshinori Miyoshi, Tsukasa Kikuchi, Toshihiro Yamamoto Kotaro Tonoike, Yoshinori Miyoshi, Tsukasa Kikuchi, Toshihiro Yamamoto Kotaro Tonoike, Yoshinori Miyoshi, Tsukasa Kikuchi, Toshihiro Yamamoto Kinetic parameter β<inf>eff</inf>/ℓ measurement on low enriched uranyl nitrate solution with single unit cores (600훗;, 280T, 800훗;)of STACY Kinetic parameter β<inf>eff</inf>/ℓ measurement on low enriched uranyl nitrate solution with single unit cores (600훗;, 280T, 800훗;)of STACY Kinetic parameter β<inf>eff</inf>/ℓ measurement on low enriched uranyl nitrate solution with single unit cores (600훗;, 280T, 800훗;)of STACY Journal of Nuclear Science and Technology, 39, 11, 1227-1236 Journal of Nuclear Science and Technology, 39, 11, 1227-1236 Journal of Nuclear Science and Technology, 39, 11, 1227-1236 2002/11 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Mechanisms of positive temperature reactivity coefficients of dilute plutonium solutions Mechanisms of positive temperature reactivity coefficients of dilute plutonium solutions Mechanisms of positive temperature reactivity coefficients of dilute plutonium solutions Nuclear Science and Engineering, 142, 3, 305-314 Nuclear Science and Engineering, 142, 3, 305-314 Nuclear Science and Engineering, 142, 3, 305-314 2002/11 英語 研究論文(学術雑誌) 公開
Yoshinori Miyoshi, Toshihiro Yamamoto, Shouichi Watanabe Yoshinori Miyoshi, Toshihiro Yamamoto, Shouichi Watanabe Yoshinori Miyoshi, Toshihiro Yamamoto, Shouichi Watanabe Benchmark evaluation on single core system composed of 10% enriched uranyl nitrate solution at stacy Benchmark evaluation on single core system composed of 10% enriched uranyl nitrate solution at stacy Benchmark evaluation on single core system composed of 10% enriched uranyl nitrate solution at stacy Journal of Nuclear Science and Technology, 39, 971-973 Journal of Nuclear Science and Technology, 39, 971-973 Journal of Nuclear Science and Technology, 39, 971-973 2002/08 研究論文(学術雑誌) 公開
Kiyoshi Sakurai, Toshihiro Yamamoto Kiyoshi Sakurai, Toshihiro Yamamoto Kiyoshi Sakurai, Toshihiro Yamamoto Reactivity measurements of erbium at tank-type critical assembly and analyses using endf/b-vi, JEF-2.2 and preliminary JENDL-3.3 Libraries Reactivity measurements of erbium at tank-type critical assembly and analyses using endf/b-vi, JEF-2.2 and preliminary JENDL-3.3 Libraries Reactivity measurements of erbium at tank-type critical assembly and analyses using endf/b-vi, JEF-2.2 and preliminary JENDL-3.3 Libraries Journal of Nuclear Science and Technology, 39, 959-962 Journal of Nuclear Science and Technology, 39, 959-962 Journal of Nuclear Science and Technology, 39, 959-962 2002/08 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Yoshinori Miyoshi, Tsukasa Kikuchi, Shouichi Watanabe Toshihiro Yamamoto, Yoshinori Miyoshi, Tsukasa Kikuchi, Shouichi Watanabe Toshihiro Yamamoto, Yoshinori Miyoshi, Tsukasa Kikuchi, Shouichi Watanabe Criticality safety benchmark experiment on 10% enriched uranyl nitrate solution using a 28-cm-thickness slab core Criticality safety benchmark experiment on 10% enriched uranyl nitrate solution using a 28-cm-thickness slab core Criticality safety benchmark experiment on 10% enriched uranyl nitrate solution using a 28-cm-thickness slab core Journal of Nuclear Science and Technology, 39, 7, 789-799 Journal of Nuclear Science and Technology, 39, 7, 789-799 Journal of Nuclear Science and Technology, 39, 7, 789-799 2002/07 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Takemi Nakamura, Yoshinori Miyoshi Toshihiro Yamamoto, Takemi Nakamura, Yoshinori Miyoshi Toshihiro Yamamoto, Takemi Nakamura, Yoshinori Miyoshi Fission source convergence of monte carlo criticality calculations in weakly coupled fissile arrays Fission source convergence of monte carlo criticality calculations in weakly coupled fissile arrays Fission source convergence of monte carlo criticality calculations in weakly coupled fissile arrays Journal of Nuclear Science and Technology, 37, 1, 41-52 Journal of Nuclear Science and Technology, 37, 1, 41-52 Journal of Nuclear Science and Technology, 37, 1, 41-52 2000/01 英語 研究論文(学術雑誌) 公開
中島 健, 山本俊弘, 三好慶典 中島 健, 山本俊弘, 三好慶典 臨界事故解析と核データ 臨界事故解析と核データ 核データニュース\n, 66, 12-19 核データニュース\n, 66, 12-19 , 66, 12-19 2000 日本語 公開
T. Yamamoto, T. Takeda, T. Kitada, A. Imaura, K. Kobayashi, O. Aizawa, K. Maki, S. Sakamoto, J. Ichise, Y. Katagiri, N. Hirakawa, T. Iwasaki, T. Osawa, K. Hashimoto, T. Horiguchi, K. Kanda, S. Shiroya, T. Misawa, H. Unesaki, M. Hayashi, K. Kobayashi, Y. Kitamura, H. Pyeon, Y. Ikeuchi, K. Yamada T. Yamamoto, T. Takeda, T. Kitada, A. Imaura, K. Kobayashi, O. Aizawa, K. Maki, S. Sakamoto, J. Ichise, Y. Katagiri, N. Hirakawa, T. Iwasaki, T. Osawa, K. Hashimoto, T. Horiguchi, K. Kanda, S. Shiroya, T. Misawa, H. Unesaki, M. Hayashi, K. Kobayashi, Y. Kitamura, H. Pyeon, Y. Ikeuchi, K. Yamada T. Yamamoto, T. Takeda, T. Kitada, A. Imaura, K. Kobayashi, O. Aizawa, K. Maki, S. Sakamoto, J. Ichise, Y. Katagiri, N. Hirakawa, T. Iwasaki, T. Osawa, K. Hashimoto, T. Horiguchi, K. Kanda, S. Shiroya, T. Misawa, H. Unesaki, M. Hayashi, K. Kobayashi, Y. Kitamura, H. Pyeon, Y. Ikeuchi, K. Yamada Analyses of Small Sample Reaction Rate Measurements in Critical Assemblies Analyses of Small Sample Reaction Rate Measurements in Critical Assemblies Analyses of Small Sample Reaction Rate Measurements in Critical Assemblies KURRI Prog. Rep., 1999, 52-0 KURRI Prog. Rep., 1999, 52-0 KURRI Prog. Rep., 1999, 52-0 2000 英語 公開
Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Toshihiro Yamamoto, Yoshinori Miyoshi Improvement of neutron source introduction method for absolute measurements of low reactor power Improvement of neutron source introduction method for absolute measurements of low reactor power Improvement of neutron source introduction method for absolute measurements of low reactor power Journal of Nuclear Science and Technology, 36, 11, 1069-1075 Journal of Nuclear Science and Technology, 36, 11, 1069-1075 Journal of Nuclear Science and Technology, 36, 11, 1069-1075 1999/11 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Kiyoshi Sakurai, Yoshitaka Naito Toshihiro Yamamoto, Kiyoshi Sakurai, Yoshitaka Naito Toshihiro Yamamoto, Kiyoshi Sakurai, Yoshitaka Naito Numerical validation of a modified neutron source multiplication method using a calculated eigenvalue Numerical validation of a modified neutron source multiplication method using a calculated eigenvalue Numerical validation of a modified neutron source multiplication method using a calculated eigenvalue Annals of Nuclear Energy, 25, 9, 599-607 Annals of Nuclear Energy, 25, 9, 599-607 Annals of Nuclear Energy, 25, 9, 599-607 1998/06 英語 研究論文(学術雑誌) 公開
K Sakurai, T Yamamoto, T Arakawa, Y Naito K Sakurai, T Yamamoto, T Arakawa, Y Naito K Sakurai, T Yamamoto, T Arakawa, Y Naito Estimation of subcriticality with the computed values analysis using MCNP of experiment on coupled cores Estimation of subcriticality with the computed values analysis using MCNP of experiment on coupled cores Estimation of subcriticality with the computed values analysis using MCNP of experiment on coupled cores JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 40, 5, 380-386 JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 40, 5, 380-386 JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 40, 5, 380-386 1998/05 日本語 研究論文(学術雑誌) 公開
K Sakurai, T Yamamoto K Sakurai, T Yamamoto K Sakurai, T Yamamoto Comparison of subcriticalities evaluated with exponential experiment and Monte Carlo calculation Comparison of subcriticalities evaluated with exponential experiment and Monte Carlo calculation Comparison of subcriticalities evaluated with exponential experiment and Monte Carlo calculation JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 40, 4, 304-311 JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 40, 4, 304-311 JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, 40, 4, 304-311 1998/04 日本語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Kiyoshi Sakurai, Takenori Suzaki, Kazuo Nitta, Yoshio Hoshi, Ohichiro Horiki Toshihiro Yamamoto, Kiyoshi Sakurai, Takenori Suzaki, Kazuo Nitta, Yoshio Hoshi, Ohichiro Horiki Toshihiro Yamamoto, Kiyoshi Sakurai, Takenori Suzaki, Kazuo Nitta, Yoshio Hoshi, Ohichiro Horiki Measurements and Analyses of Reactivity Effect of Fission Product Nuclides in Epithermal Energy Range Measurements and Analyses of Reactivity Effect of Fission Product Nuclides in Epithermal Energy Range Measurements and Analyses of Reactivity Effect of Fission Product Nuclides in Epithermal Energy Range Journal of Nuclear Science and Technology, 34, 12, 1178-1184 Journal of Nuclear Science and Technology, 34, 12, 1178-1184 Journal of Nuclear Science and Technology, 34, 12, 1178-1184 1997/12 英語 研究論文(学術雑誌) 公開
Kiyoshi Sakurai, Toshihiro Yamamoto, Takuya Arakawa, Yoshitaka Naito Kiyoshi Sakurai, Toshihiro Yamamoto, Takuya Arakawa, Yoshitaka Naito Kiyoshi Sakurai, Toshihiro Yamamoto, Takuya Arakawa, Yoshitaka Naito Accurate estimation of subcriticality using indirect bias estimation method, (II) Accurate estimation of subcriticality using indirect bias estimation method, (II) Accurate estimation of subcriticality using indirect bias estimation method, (II) Journal of Nuclear Science and Technology, 34, 6, 544-550 Journal of Nuclear Science and Technology, 34, 6, 544-550 Journal of Nuclear Science and Technology, 34, 6, 544-550 1997/06 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Kiyoshi Sakurai, Takuya Arakawa, Yoshitaka Naito Toshihiro Yamamoto, Kiyoshi Sakurai, Takuya Arakawa, Yoshitaka Naito Toshihiro Yamamoto, Kiyoshi Sakurai, Takuya Arakawa, Yoshitaka Naito Accurate estimation of subcriticality using indirect bias estimation method, (I) Accurate estimation of subcriticality using indirect bias estimation method, (I) Accurate estimation of subcriticality using indirect bias estimation method, (I) Journal of Nuclear Science and Technology, 34, 5, 454-460 Journal of Nuclear Science and Technology, 34, 5, 454-460 Journal of Nuclear Science and Technology, 34, 5, 454-460 1997/04 英語 研究論文(学術雑誌) 公開
Kiyoshi Sakurap, Toshihiro Yamamoto Kiyoshi Sakurap, Toshihiro Yamamoto Kiyoshi Sakurap, Toshihiro Yamamoto Benchmark Model of Critical Experiment at TCA for Integral Evaluation of Fission Product Nuclide Cross Sections Benchmark Model of Critical Experiment at TCA for Integral Evaluation of Fission Product Nuclide Cross Sections Benchmark Model of Critical Experiment at TCA for Integral Evaluation of Fission Product Nuclide Cross Sections Journal of Nuclear Science and Technology, 34, 2, 202-210 Journal of Nuclear Science and Technology, 34, 2, 202-210 Journal of Nuclear Science and Technology, 34, 2, 202-210 1997/02 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Perturbation of general boundary condition for an eigenvalue change in the neutron Boltzmann transport equation Perturbation of general boundary condition for an eigenvalue change in the neutron Boltzmann transport equation Perturbation of general boundary condition for an eigenvalue change in the neutron Boltzmann transport equation Nuclear Science and Engineering, 125, 1, 19-23 Nuclear Science and Engineering, 125, 1, 19-23 Nuclear Science and Engineering, 125, 1, 19-23 1996 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto Toshihiro Yamamoto Toshihiro Yamamoto Most critical geometry of a fuel solution based on the transport boundary perturbation theory Most critical geometry of a fuel solution based on the transport boundary perturbation theory Most critical geometry of a fuel solution based on the transport boundary perturbation theory Journal of Nuclear Science and Technology, 33, 1, 78-82 Journal of Nuclear Science and Technology, 33, 1, 78-82 Journal of Nuclear Science and Technology, 33, 1, 78-82 1996/01 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Benan Basoglu Toshihiro Yamamoto, Benan Basoglu Toshihiro Yamamoto, Benan Basoglu Optimal geometry for fuel solution sloshing based on the boundary perturbation theory Optimal geometry for fuel solution sloshing based on the boundary perturbation theory Optimal geometry for fuel solution sloshing based on the boundary perturbation theory Annals of Nuclear Energy, 22, 10, 649-658 Annals of Nuclear Energy, 22, 10, 649-658 Annals of Nuclear Energy, 22, 10, 649-658 1995/10 英語 研究論文(学術雑誌) 公開
AD WILKINSON, B BASOGLU, CL BENTLEY, ME DUNN, CF HAUGHT, MJ PLASTER, T YAMAMOTO, HL DODDS, CM HOPPER AD WILKINSON, B BASOGLU, CL BENTLEY, ME DUNN, CF HAUGHT, MJ PLASTER, T YAMAMOTO, HL DODDS, CM HOPPER AD WILKINSON, B BASOGLU, CL BENTLEY, ME DUNN, CF HAUGHT, MJ PLASTER, T YAMAMOTO, HL DODDS, CM HOPPER IMPROVED DOSE ESTIMATES FOR NUCLEAR CRITICALITY ACCIDENTS IMPROVED DOSE ESTIMATES FOR NUCLEAR CRITICALITY ACCIDENTS IMPROVED DOSE ESTIMATES FOR NUCLEAR CRITICALITY ACCIDENTS NUCLEAR TECHNOLOGY, 111, 2, 227-240 NUCLEAR TECHNOLOGY, 111, 2, 227-240 NUCLEAR TECHNOLOGY, 111, 2, 227-240 1995/08 英語 公開
MJ PLASTER, B BASOGLU, CL BENTLEY, ME DUNN, AE RUGGLES, AD WILKINSON, T YAMAMOTO, HL DODDS MJ PLASTER, B BASOGLU, CL BENTLEY, ME DUNN, AE RUGGLES, AD WILKINSON, T YAMAMOTO, HL DODDS MJ PLASTER, B BASOGLU, CL BENTLEY, ME DUNN, AE RUGGLES, AD WILKINSON, T YAMAMOTO, HL DODDS ANALYSIS OF A HYPOTHETICAL CRITICALITY ACCIDENT IN A WASTE SUPERCOMPACTOR ANALYSIS OF A HYPOTHETICAL CRITICALITY ACCIDENT IN A WASTE SUPERCOMPACTOR ANALYSIS OF A HYPOTHETICAL CRITICALITY ACCIDENT IN A WASTE SUPERCOMPACTOR NUCLEAR TECHNOLOGY, 111, 2, 219-226 NUCLEAR TECHNOLOGY, 111, 2, 219-226 NUCLEAR TECHNOLOGY, 111, 2, 219-226 1995/08 英語 研究論文(学術雑誌) 公開
ME DUNN, B BASOGLU, CL BENTLEY, C HAUGHT, MJ PLASTER, AD WILKINSON, T YAMAMOTO, HL DODDS ME DUNN, B BASOGLU, CL BENTLEY, C HAUGHT, MJ PLASTER, AD WILKINSON, T YAMAMOTO, HL DODDS ME DUNN, B BASOGLU, CL BENTLEY, C HAUGHT, MJ PLASTER, AD WILKINSON, T YAMAMOTO, HL DODDS VALIDATION OF KENO V.A WITH ENDF/B-V CROSS-SECTIONS FOR U-233 SYSTEMS VALIDATION OF KENO V.A WITH ENDF/B-V CROSS-SECTIONS FOR U-233 SYSTEMS VALIDATION OF KENO V.A WITH ENDF/B-V CROSS-SECTIONS FOR U-233 SYSTEMS NUCLEAR TECHNOLOGY, 111, 2, 183-196 NUCLEAR TECHNOLOGY, 111, 2, 183-196 NUCLEAR TECHNOLOGY, 111, 2, 183-196 1995/08 英語 研究論文(学術雑誌) 公開
Alan D. Wilkinson, B. Basoglu, C. L. Bentley, M. E. Dunn, Chris F. Haught, M. J. Plaster, T. Yamamoto, H. L. Dodds, Calvin M. Hopper Alan D. Wilkinson, B. Basoglu, C. L. Bentley, M. E. Dunn, Chris F. Haught, M. J. Plaster, T. Yamamoto, H. L. Dodds, Calvin M. Hopper Alan D. Wilkinson, B. Basoglu, C. L. Bentley, M. E. Dunn, Chris F. Haught, M. J. Plaster, T. Yamamoto, H. L. Dodds, Calvin M. Hopper Improved dose estimates for nuclear criticality accidents Improved dose estimates for nuclear criticality accidents Improved dose estimates for nuclear criticality accidents Nuclear Technology, 111, 2, 227-240 Nuclear Technology, 111, 2, 227-240 Nuclear Technology, 111, 2, 227-240 1995/02 研究論文(学術雑誌) 公開
M. J. Plaster, B. Basoglu, C. L. Bentley, M. E. Dunn, A. E. Ruggles, A. D. Wilkinson, T. Yamamoto, H. L. Dodds M. J. Plaster, B. Basoglu, C. L. Bentley, M. E. Dunn, A. E. Ruggles, A. D. Wilkinson, T. Yamamoto, H. L. Dodds M. J. Plaster, B. Basoglu, C. L. Bentley, M. E. Dunn, A. E. Ruggles, A. D. Wilkinson, T. Yamamoto, H. L. Dodds Analysis of a hypothetical criticality accident in a waste supercompactor Analysis of a hypothetical criticality accident in a waste supercompactor Analysis of a hypothetical criticality accident in a waste supercompactor Nuclear Technology, 111, 2, 219-226 Nuclear Technology, 111, 2, 219-226 Nuclear Technology, 111, 2, 219-226 1995/02 研究論文(学術雑誌) 公開
M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto M. E. Dunn, B. Basoglu, C. L. Bentley, C. Haught, M. J. Plaster, A. D. Wilkinson, T. Yamamoto Validation of KENO V.a with ENDF/B-V cross sections for <sup>233</sup>U systems Validation of KENO V.a with ENDF/B-V cross sections for <sup>233</sup>U systems Validation of KENO V.a with ENDF/B-V cross sections for <sup>233</sup>U systems Nuclear Technology, 111, 2, 183-196 Nuclear Technology, 111, 2, 183-196 Nuclear Technology, 111, 2, 183-196 1995/02 研究論文(学術雑誌) 公開
Ken Nakajima, Masanori Akai, Toshihiro Yamamoto, Masao Hashimoto, Takenori Suzaki Ken Nakajima, Masanori Akai, Toshihiro Yamamoto, Masao Hashimoto, Takenori Suzaki Ken Nakajima, Masanori Akai, Toshihiro Yamamoto, Masao Hashimoto, Takenori Suzaki Measurements and Analyses of the Ratio of <sup>238</sup>U Captures to <sup>235</sup>U Fission in Low-Enriched UO2 Tight Lattices Measurements and Analyses of the Ratio of <sup>238</sup>U Captures to <sup>235</sup>U Fission in Low-Enriched UO2 Tight Lattices Measurements and Analyses of the Ratio of <sup>238</sup>U Captures to <sup>235</sup>U Fission in Low-Enriched UO2 Tight Lattices Journal of Nuclear Science and Technology, 31, 11, 1160-1170 Journal of Nuclear Science and Technology, 31, 11, 1160-1170 Journal of Nuclear Science and Technology, 31, 11, 1160-1170 1994 英語 研究論文(学術雑誌) 公開
Yoshinori Miyoshi, Toshihiro Yamamoto, Takenori Suzaki, Iwao Kobayashi Yoshinori Miyoshi, Toshihiro Yamamoto, Takenori Suzaki, Iwao Kobayashi Yoshinori Miyoshi, Toshihiro Yamamoto, Takenori Suzaki, Iwao Kobayashi Temperature effects on reactivity in light water moderated UO<inf>2</inf> cores with soluble poisons Temperature effects on reactivity in light water moderated UO<inf>2</inf> cores with soluble poisons Temperature effects on reactivity in light water moderated UO<inf>2</inf> cores with soluble poisons Journal of Nuclear Science and Technology, 29, 12, 1201-1211 Journal of Nuclear Science and Technology, 29, 12, 1201-1211 Journal of Nuclear Science and Technology, 29, 12, 1201-1211 1992/12 英語 研究論文(学術雑誌) 公開
Toshihiro Yamamoto, Toshikazu Takeda, Tamotsu Sekiya, Hisashi Nakamura, Mitsuru Kamei Toshihiro Yamamoto, Toshikazu Takeda, Tamotsu Sekiya, Hisashi Nakamura, Mitsuru Kamei Toshihiro Yamamoto, Toshikazu Takeda, Tamotsu Sekiya, Hisashi Nakamura, Mitsuru Kamei Analysis of temperature noise propagation in fast breeder core by the two-equation model Analysis of temperature noise propagation in fast breeder core by the two-equation model Analysis of temperature noise propagation in fast breeder core by the two-equation model Nuclear Engineering and Design, 117, 2, 169-183 Nuclear Engineering and Design, 117, 2, 169-183 Nuclear Engineering and Design, 117, 2, 169-183 1989/11 英語 研究論文(学術雑誌) 公開

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著者 著者(日本語) 著者(英語) タイトル タイトル(日本語) タイトル(英語) 書誌情報等 書誌情報等(日本語) 書誌情報等(英語) 出版年月 査読の有無 記述言語 掲載種別 公開
高山直毅, 山本俊弘, 佐野忠史, 堀順一, 中島健 高山直毅, 山本俊弘, 佐野忠史, 堀順一, 中島健 高山直毅, 山本俊弘, 佐野忠史, 堀順一, 中島健 時間依存モンテカルロ計算による中性子雑音を用いた軽水炉内ボイド情報の推定 時間依存モンテカルロ計算による中性子雑音を用いた軽水炉内ボイド情報の推定 時間依存モンテカルロ計算による中性子雑音を用いた軽水炉内ボイド情報の推定 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.2H06 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.2H06 日本原子力学会秋の大会予稿集(CD-ROM), 2016, ROMBUNNO.2H06 2016/08/26 日本語 公開
LEE Jaehong, 堀順一, 佐野忠史, 中島健, 高橋佳之, 山本俊弘 LEE Jaehong, 堀順一, 佐野忠史, 中島健, 高橋佳之, 山本俊弘 LEE JAEHONG, HORI JUN'ICHI, SANO TADAFUMI, NAKAJIMA KEN, TAKAHASHI YOSHIYUKI, YAMAMOTO TOSHIHIRO TOF法を用いた中性子捕獲断面積測定に対する自己遮蔽効果の補正方法の検討 TOF法を用いた中性子捕獲断面積測定に対する自己遮蔽効果の補正方法の検討 TOF法を用いた中性子捕獲断面積測定に対する自己遮蔽効果の補正方法の検討 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.O05 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.O05 日本原子力学会秋の大会予稿集(CD-ROM), 2015, ROMBUNNO.O05 2015/08/21 日本語 公開
Tadafumi SANO, Yasuhuki FUJIHARA, Yoshiyuki TAKAHASHI, Jian ZHANG, Toshihiro YAMAMOTO, Ken NAKAJIMA Tadafumi SANO, Yasuhuki FUJIHARA, Yoshiyuki TAKAHASHI, Jian ZHANG, Toshihiro YAMAMOTO, Ken NAKAJIMA Tadafumi SANO, Yasuhuki FUJIHARA, Yoshiyuki TAKAHASHI, Jian ZHANG, Toshihiro YAMAMOTO, Ken NAKAJIMA Current Status and Future Works of Kyoto University Research Reactor Current Status and Future Works of Kyoto University Research Reactor Current Status and Future Works of Kyoto University Research Reactor 2nd Asian Symposium on Material Testing Reactors, 0-0 2nd Asian Symposium on Material Testing Reactors, 0-0 2nd Asian Symposium on Material Testing Reactors, 0-0 2012/10/11 英語 公開
K. Nakajima, T. Yamamoto K. Nakajima, T. Yamamoto K. Nakajima, T. Yamamoto Power Profile Analysis of JCO-TOKAI Criticality Accident i 1999 Power Profile Analysis of JCO-TOKAI Criticality Accident i 1999 Power Profile Analysis of JCO-TOKAI Criticality Accident i 1999 Proc . Int. Conf. on Nuclear Criticality, ICNC2011, Sept. 19-23, 2011, Edinburgh, UK Proc . Int. Conf. on Nuclear Criticality, ICNC2011, Sept. 19-23, 2011, Edinburgh, UK Proc . Int. Conf. on Nuclear Criticality, ICNC2011, Sept. 19-23, 2011, Edinburgh, UK 2011/09 英語 公開
藤原 靖幸, 張 倹, 高橋 佳之, 佐野 忠史, 山本 俊弘, 宇根崎 博信, 中島 健 藤原 靖幸, 張 倹, 高橋 佳之, 佐野 忠史, 山本 俊弘, 宇根崎 博信, 中島 健 平成22年度京都大学研究用原子炉の運転実績及び利用状況 平成22年度京都大学研究用原子炉の運転実績及び利用状況 日本原子力学会 2011年秋の大会 日本原子力学会 2011年秋の大会 2011/09 日本語 公開
T. Yamamoto T. Yamamoto T. Yamamoto Energy Dependence of Feynman-α Method and its Application to Realistic Subcritical Systems Energy Dependence of Feynman-α Method and its Application to Realistic Subcritical Systems Energy Dependence of Feynman-α Method and its Application to Realistic Subcritical Systems Proc. Int. Conf. Nucl. Criticality Safety 2011, 0-0 Proc. Int. Conf. Nucl. Criticality Safety 2011, 0-0 Proc. Int. Conf. Nucl. Criticality Safety 2011, 0-0 2011 英語 公開
中島健, 宇根崎博信, 三澤毅, 佐野忠史, 高橋佳之, 大野和臣, 張倹, 土山辰夫, 中森輝, 長谷川圭, 藤原靖幸, 丸山直矢, 山本俊弘 中島健, 宇根崎博信, 三澤毅, 佐野忠史, 高橋佳之, 大野和臣, 張倹, 土山辰夫, 中森輝, 長谷川圭, 藤原靖幸, 丸山直矢, 山本俊弘 K. Nakajima, H. Unesaki, T. Misawa, T. Sano, Y. Takahashi, K. Oono, J. Zhang, T. Tsutiyama, A. Nakamori, A. Hasegawa, Y. Fujihara, N. Maruyama, T. Yamamoto 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験;(1)概要 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験;(1)概要 Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core 日本原子力学会「2010年秋の大会」 日本原子力学会「2010年秋の大会」 2010/09 日本語 公開
佐野忠史, 藤原靖幸, ZHANG Jian, 高橋佳之, 大野和臣, 丸山直矢, 中島健, 山本俊弘 佐野忠史, 藤原靖幸, ZHANG Jian, 高橋佳之, 大野和臣, 丸山直矢, 中島健, 山本俊弘 SANO TADAFUMI, FUJIWARA YASUYUKI, ZHANG JIAN, TAKAHASHI YOSHIYUKI, ONO KAZUOMI, MARUYAMA NAOYA, NAKAJIMA KEN, YAMAMOTO TOSHIHIRO 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(3)各種反応度測定 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(3)各種反応度測定 京都大学研究用原子炉(KUR)低濃縮ウラン炉心の特性試験(3)各種反応度測定 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O03 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O03 日本原子力学会秋の大会予稿集(CD-ROM), 2010, ROMBUNNO.O03 2010/08/27 日本語 公開
J. Sugimoto, H. Murakam, R. Sakamoto, T. Yamamoto J. Sugimoto, H. Murakam, R. Sakamoto, T. Yamamoto J. Sugimoto, H. Murakam, R. Sakamoto, T. Yamamoto Nuclear human resources development activities for asian countries at JAEA/NuTEC Nuclear human resources development activities for asian countries at JAEA/NuTEC Nuclear human resources development activities for asian countries at JAEA/NuTEC American Nuclear Society - Conference on Nuclear Training and Education, CONTE 2009, 66-67 American Nuclear Society - Conference on Nuclear Training and Education, CONTE 2009, 66-67 American Nuclear Society - Conference on Nuclear Training and Education, CONTE 2009, 66-67 2008 英語 公開
Y. Yamane, K. Nakajima, T. Yamamoto, Y. Miyoshi Y. Yamane, K. Nakajima, T. Yamamoto, Y. Miyoshi Y. Yamane, K. Nakajima, T. Yamamoto, Y. Miyoshi Development of Criticality Accident Analysis Code AGNES Development of Criticality Accident Analysis Code AGNES Development of Criticality Accident Analysis Code AGNES Proc. 7th Int. Conf. Nuclear Criticality Safety、 ICNC2003, 740-745 Proc. 7th Int. Conf. Nuclear Criticality Safety、 ICNC2003, 740-745 Proc. 7th Int. Conf. Nuclear Criticality Safety、 ICNC2003, 740-745 2004/10/20 英語 公開
三好慶典, 山本俊弘, 外池幸太郎, 中島健, 山根祐一 三好慶典, 山本俊弘, 外池幸太郎, 中島健, 山根祐一 MIYOSHI YOSHINORI, YAMAMOTO TOSHIHIRO, TONOIKE KOTARO, NAKAJIMA KEN, YAMANE YUICHI 臨界安全性に関する実験的研究 臨界安全性に関する実験的研究 Experimental Study on Criticality Safety-Study on Criticality Characteristics and Criticality Accident Phenomena of Low Enriched Uranyl Solution System at NUCEF-. 日本原子力研究所JAERI-Conf, 67-68 日本原子力研究所JAERI-Conf, 67-68 日本原子力研究所JAERI-Conf, 67-68 2003/10 日本語 公開
竹下功, 上塚寛, 辻宏和, 石神努, 中島健, 山本俊弘, 大野秋男, 宮内正勝, 安濃田良成 竹下功, 上塚寛, 辻宏和, 石神努, 中島健, 山本俊弘, 大野秋男, 宮内正勝, 安濃田良成 TAKESHITA ISAO, UEZUKA HIROSHI, TSUJI HIROKAZU, ISHIGAMI TSUTOMU, NAKAJIMA TAKESHI, YAMAMOTO TOSHIHIRO, ONO AKIO, MIYAUCHI MASAKATSU, ANODA YOSHINARI 原子力安全性研究の現状 (平成14年) 原子力安全性研究の現状 (平成14年) Progress of Nuclear Safety Research-2002. 日本原子力研究所JAERI-Review, 152P 日本原子力研究所JAERI-Review, 152P 日本原子力研究所JAERI-Review, 152P 2002/11 日本語 公開
Y. Miyoshi, T. Yamamoto, K. Nakajima, Y. Yamane, S. Watanabe Y. Miyoshi, T. Yamamoto, K. Nakajima, Y. Yamane, S. Watanabe Y. Miyoshi, T. Yamamoto, K. Nakajima, Y. Yamane, S. Watanabe Study on Neutronic and Thermal Characteristics of the Precipitaion Vessel in JCO Criticality Accident Study on Neutronic and Thermal Characteristics of the Precipitaion Vessel in JCO Criticality Accident Study on Neutronic and Thermal Characteristics of the Precipitaion Vessel in JCO Criticality Accident 3rd NUCEF International Symposium (NUCEF 2001) (JAERI-Conf 2002-004)\n, 173-179 3rd NUCEF International Symposium (NUCEF 2001) (JAERI-Conf 2002-004)\n, 173-179 3rd NUCEF International Symposium (NUCEF 2001) (JAERI-Conf 2002-004)\n, 173-179 2001/11/30 英語 公開
山根祐一, 中島健, 山本俊弘, 中村剛実, 三好慶典 山根祐一, 中島健, 山本俊弘, 中村剛実, 三好慶典 YAMANE YUICHI, NAKAJIMA KEN, YAMAMOTO TOSHIHIRO, NAKAMURA TAKEMI, MIYOSHI YOSHINORI AGNESコードを用いたTRACY実験及びJCO事故の動特性解析 AGNESコードを用いたTRACY実験及びJCO事故の動特性解析 Analysis of TRACY Experiment and JCO Criticality Accident by Using AGNES Code. 日本原子力研究所JAERI-Conf, 19-20 日本原子力研究所JAERI-Conf, 19-20 日本原子力研究所JAERI-Conf, 19-20 2000/07 日本語 公開
山本俊弘, 中村剛実, 中島健, 三好慶典 山本俊弘, 中村剛実, 中島健, 三好慶典 YAMAMOTO TOSHIHIRO, NAKAMURA TAKEMI, NAKAJIMA KEN, MIYOSHI YOSHINORI JCO事故初動対応における臨界安全解析 JCO事故初動対応における臨界安全解析 Criticality Safety Analyses for Emergency Response Actions of JCO Accident. 日本原子力研究所JAERI-Conf, 13-14 日本原子力研究所JAERI-Conf, 13-14 日本原子力研究所JAERI-Conf, 13-14 2000/07 日本語 公開
中島健, 山根祐一, 山本俊弘, 中村剛実, 三好慶典 中島健, 山根祐一, 山本俊弘, 中村剛実, 三好慶典 JCO臨界事故の特性解析,4; 準定常法を用いた初期バースト部の動特性評価 JCO臨界事故の特性解析,4; 準定常法を用いた初期バースト部の動特性評価 日本原子力学会2000年春の年会 日本原子力学会2000年春の年会 2000 日本語 公開
Okajima K, Hiraoka M, Masunaga S, Mitsumori M, Koishi M, Nishimura Y, Nagata Y, Abe M, Oura K, Yamamoto T, Ebisawa Y, Takahashi W, Yamashita M Okajima K, Hiraoka M, Masunaga S, Mitsumori M, Koishi M, Nishimura Y, Nagata Y, Abe M, Oura K, Yamamoto T, Ebisawa Y, Takahashi W, Yamashita M Okajima K, Hiraoka M, Masunaga S, Mitsumori M, Koishi M, Nishimura Y, Nagata Y, Abe M, Oura K, Yamamoto T, Ebisawa Y, Takahashi W, Yamashita M Assessment of basic characteristics of implant materials for ferromagnetic hyperthermia. Assessment of basic characteristics of implant materials for ferromagnetic hyperthermia. Assessment of basic characteristics of implant materials for ferromagnetic hyperthermia. International Congress of Radiation Oncology 1993 (ICRO ’93), 0-0 International Congress of Radiation Oncology 1993 (ICRO ’93), 0-0 International Congress of Radiation Oncology 1993 (ICRO ’93), 0-0 1993 英語 公開

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タイトル言語:
学術賞等
賞の名称(日本語) 賞の名称(英語) 授与組織名(日本語) 授与組織名(英語) 年月
第39回(平成18年度)日本原子力学会論文賞 Outstanding Paper Award of Atomic Energy Society of Japan 社団法人 日本原子力学会 Atomic Energy Society of Japan 2007/03/27
PHYSOR2014 Best Poster Award International Conference on the Physics of Reactor, 2014 2014/10/02
自ら企画した研究集会
集会名 学会名 年月
Workshop on Advanced Monte Carlo Method 2015/07/21
外部資金:競争的資金 (科学研究費補助金)
種別 代表/分担 テーマ(日本語) テーマ(英語) 期間
科学研究費補助金 代表 炉心異常診断のための中性子輸送理論による高精度炉雑音解析に関する研究 2017/04/01〜2021/03/31
基盤研究(C) 代表 炉心異常診断のための中性子輸送理論による高精度炉雑音解析に関する研究 (平成29年度分) 2017/04/01〜2018/03/31
基盤研究(C) 代表 炉心異常診断のための中性子輸送理論による高精度炉雑音解析に関する研究 (平成30年度分) 2018/04/01〜2019/03/31
基盤研究(C) 代表 炉心異常診断のための中性子輸送理論による高精度炉雑音解析に関する研究 (2019年度分) 2019/04/01〜2020/03/31
担当科目
講義名(日本語) 講義名(英語) 開講期 学部/研究科 年度
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2012/04〜2013/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2013/04〜2014/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2014/04〜2015/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2015/04〜2016/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2016/04〜2017/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2017/04〜2018/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2018/04〜2019/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2019/04〜2020/03
原子力工学応用実験 Nuclear Engineering Application Experiments 通年 工学研究科 2020/04〜2021/03
原子炉安全工学 Nuclear Reactor Safety Engineering 後期 工学研究科 2020/04〜2021/03
全学運営(役職等)
役職名 期間
原子炉用燃料管理小委員会 委員 2010/04/01〜2011/03/31
部局運営(役職等)
役職名 期間
原子炉安全委員会委員 2010/04/01〜
放射線障害防止委員会委員(旧保健物理委員会委員) 2010/04/01〜
学会活動:編集委員歴
学会名(日本語) 学会名(英語) ジャーナル名(日本語) ジャーナル名(英語) 役職名 期間
一般社団法人 日本原子力学会 Atomic Energy Society of Japan 日本原子力学会 Journal of Nuclear Society and Technology 編集委員 2008/07/01〜2012/06/30
国際的機関での活動
活動内容(日本語) 活動内容(英語) 活動機関名 期間
Core monitoring techniques and experimental validation and demonstration European Commission 2017/09/01〜2021/08/31