Yamamoto, Toshihiro(Institute for Integrated Radiation and Nuclear Science (KURNS)) | Activity Database on Education and Research, Kyoto University

Yamamoto, Toshihiro

Institute for Integrated Radiation and Nuclear Science (KURNS) Associate Professor

Last Updated :2025/12/19

Basic Information

Affiliated programs (koza)

Graduate School of Engineering, 原子核工学専攻核システム工学講座, 准教授

Academic Degree

工学修士(大阪大学)

博士（工学）(大阪大学)

ID,URL

J-Global ID
201401064705693672

researchmap URL

https://researchmap.jp/215612

Last Updated :2025/12/19

Research

Research Topics, Overview of the research

Research Topics
Research Reactor Safety
Overview of the research
Research on Safety of Kyoto University Reactor. Research on Calculation Method of Reactor Physics.

Research Areas

Natural sciences, Mathematical physics and basic theory

Papers

Applying the derivative source method to flux derivatives in Monte Carlo fixed source problems caused by interface shifts between spontaneous fission materials
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Feb. 2026, Peer-reviewed, Lead author, Corresponding author
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Mesh-free perturbation source method using the closest point pair method in k-eigenvalue Monte Carlo perturbation calculations
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Jan. 2026, Peer-reviewed, Lead author, Corresponding author
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Two-step Monte Carlo calculation method for sensitivity coefficients of reactor period with respect to kinetics parameters
Toshihiro Yamamoto; Hiroki Sakamoto
Nuclear Science and Engineering, Mar. 2025, Peer-reviewed, Lead author, Corresponding author
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Monte Carlo methods based on “virtual density” theory for calculation of k-eigenvalue sensitivity under nonuniform anisotropic deformation
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Apr. 2025, Peer-reviewed, Lead author, Corresponding author
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A full-flow-range drift-flux model for adiabatic and boiling two-phase flows in vertical narrow rectangular flow channels
Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Takashi Hibiki
International Journal of Thermal Sciences, Aug. 2024, Peer-reviewed

Sensitivity and perturbation analysis of alpha-eigenvalue with time-dependent Monte Carlo perturbation techniques
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Jul. 2024, Peer-reviewed, Lead author, Corresponding author
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Monte Carlo iterative k-source method for fixed-source calculations in nearly critical subcritical systems
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, May 2024, Peer-reviewed, Lead author, Corresponding author
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Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly
Vikrant Siddharudh Chalgeri; Xiuzhong Shen; Toshihiro Yamamoto
Annals of Nuclear Energy, Jun. 2024

Interfacial area concentration in gas-liquid metal two-phase flow
Xiuzhong Shen; Toshihiro Yamamoto; Xu Han; Takashi Hibiki
Experimental and Computational Multiphase Flow, 02 Aug. 2021

Monte Carlo Calculation Method for Reactor Period Utilizing the Differential Operator Sampling Technique
Toshihiro Yamamoto; Hiroki Sakamoto
Nuclear Science and Engineering, 15 Nov. 2023, Peer-reviewed, Lead author, Corresponding author
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Verification of Feynman-α formula including the effect of delayed neutrons
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Dec. 2023, Peer-reviewed, Lead author, Corresponding author
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Modeling noise experiments performed at AKR-2 and CROCUS zero-power reactors
M. Hursin; A. Zoia; A. Rouchon; A. Brighenti; I. Zmijarevic; S. Santandrea; P. Vinai; A. Mylonakis; H. Yi; C. Demazière; V. Lamirand; K. Ambrozic; T. Yamamoto; S. Hübner; A. Knospe; C. Lange; S. Yum; R. Macian; A. Vidal; D. Ginestar; G. Verdú
Annals of Nuclear Energy, Aug. 2023, Peer-reviewed

Monte Carlo perturbation method for optimum surface geometry due to sloshing motion
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, May 2023, Peer-reviewed, Lead author, Corresponding author
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Report of "Monte Carlo Calculation Summer Seminar"
Sakurai, Kiyoshi; Kume, Etsuo; Yatabe, Shigeru; Maekawa, Fujio; Yamamoto, Toshihiro; Nagaya, Yasunobu; Mori, Takamasa; Ueki, Kotaro; Naito, Yoshitaka
JAERI-Review 2000-034, Feb. 2001

Dynamic mode decomposition for subcriticality measurement using measured data at single location
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Jan. 2023, Peer-reviewed, Lead author, Corresponding author
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Generation of group constants and diffusion coefficients by Monte Carlo-based B1 method with complex weight -Application to assembly calculations
YAMAMOTO TOSHIHIRO
Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan, 2012

Flow regime and void fraction predictions in vertical rod bundle flow channels
Xu Han; Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Haomin Sun; Takashi Hibiki
International Journal of Heat and Mass Transfer, Oct. 2021

Monte Carlo sensitivity calculation in fixed source problems with the derivative source method
Toshihiro Yamamoto; Hiroki Sakamoto
Journal of Computational Physics, Jul. 2022, Peer-reviewed, Lead author, Corresponding author
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Dynamic mode decomposition application to dominance ratio assessment in Monte Carlo k-eigenvalue calculation
Toshihiro Yamamoto; Xiuzhong Shen; Hiroki Sakamoto
Annals of Nuclear Energy, Sep. 2022, Peer-reviewed, Lead author, Corresponding author
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Deterministic and stochastic methods for sensitivity analysis of neutron noise
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, Mar. 2022, Peer-reviewed, Lead author, Corresponding author
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Higher harmonic analyses of the Rossi-α method and application of dynamic mode decomposition for time decay constant determination in a 1D subcritical system
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Dec. 2021, Peer-reviewed, Lead author, Corresponding author

Application of dynamic mode decomposition to exponential experiment for spatial decay constant determination
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Nov. 2021, Peer-reviewed, Lead author, Corresponding author
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Advances in time-dependent Monte Carlo simulations for void velocity determination using neutron noise techniques
Toshihiro Yamamoto; Xiuzhong Shen; Hiroki Sakamoto
Progress in Nuclear Energy, Aug. 2021, Peer-reviewed, Lead author, Corresponding author
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Exact Monte Carlo calculation method for K-eigenvalue change using perturbation source method
Toshihiro Yamamoto; Hiroki Sakamoto
Journal of Nuclear Science and Technology, 14 Mar. 2021, Peer-reviewed, Lead author, Corresponding author

Monte Carlo perturbation calculation for geometry change in fixed source problems with the perturbation source method
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, Feb. 2021, Peer-reviewed, Lead author, Corresponding author
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Frequency domain Monte Carlo simulations of void velocity measurements in an actual experimental setup using a neutron noise technique
Toshihiro Yamamoto; Hiroki Sakamoto
Journal of Nuclear Science and Technology, 2021, Peer-reviewed, Lead author, Corresponding author

Drift-flux correlation for upward gas-liquid two-phase flow in vertical rod bundle flow channel
Xu Han; Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Takashi Hibiki
International Journal of Heat and Mass Transfer, Dec. 2020

Convergence characteristics and Wielandt acceleration of the time source method for Monte Carlo alpha eigenvalue calculations
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Oct. 2020, Peer-reviewed, Lead author, Corresponding author
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Monte Carlo sensitivity analysis method for the effective delayed neutron fraction with the differential operator sampling method
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Jun. 2020, Peer-reviewed, Lead author, Corresponding author
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Flow characteristics of upward two-phase flows in a rod bundle geometry
Xu Han; Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima
International Conference on Nuclear Engineering, Proceedings, ICONE, 2020

Experimental study on local interfacial parameters in upward air-water bubbly flow in a vertical 6 × 6 rod bundle
Xu Han; Xiuzhong Shen; Toshihiro Yamamoto; Ken Nakajima; Haomin Sun; Takashi Hibiki
International Journal of Heat and Mass Transfer, Dec. 2019, Peer-reviewed

Decomposition of neutron noise in a reactor into higher-order mode components and investigation of the space and frequency dependence
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, Nov. 2019, Peer-reviewed, Lead author, Corresponding author
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Two-step Monte Carlo sensitivity analysis of alpha- and gamma-eigenvalues with the differential operator sampling method
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Nov. 2019, Peer-reviewed, Lead author, Corresponding author
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Calculation of the cross and auto power spectral densities for low neutron counting from pulse mode detectors
Alberto Talamo; Yoursry Gohar; Toshihiro Yamamoto; Masao Yamanaka; Cheol Ho Pyeon
Annals of Nuclear Energy, Sep. 2019, Peer-reviewed

A Monte Carlo technique for sensitivity analysis of alpha-eigenvalue with the differential operator sampling method
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, May 2019, Peer-reviewed, Lead author, Corresponding author
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Monte Carlo method for solving a B1 equation with complex-valued buckling in asymmetric geometries and generation of directional diffusion coefficients
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Dec. 2018, Peer-reviewed, Lead author, Corresponding author
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Effect of higher harmonics in the area-ratio pulsed neutron source technique
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, Sep. 2018, Peer-reviewed, Lead author, Corresponding author

Monte Carlo perturbation methods using “virtual density” theory for calculating reactivity due to geometry change
Toshihiro Yamamoto
Annals of Nuclear Energy, Sep. 2018, Peer-reviewed, Lead author, Corresponding author

Implementation of a frequency-domain neutron noise analysis method in a production-level continuous energy Monte Carlo code: Verification and application in a BWR
Toshihiro Yamamoto
Annals of Nuclear Energy, May 2018, Peer-reviewed, Lead author, Corresponding author
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ON THE REASSESSMENT OF SAFETY ASSESSMENT REPORTS AND THE RESTART OF UNIVERSITY RESEARCH REACTORS IN JAPAN
Hironobu Unesaki; Tsuyoshi Misawa; Ken Nakajima; Hirotoshi Uebayashi; Jun-Ichi Hori; Toshihiro Yamamoto; Hiroshi Shiga; Katsuhiro Kamae
European Research Reactor Conference RRFM 2018, Mar. 2018, Peer-reviewed

Eigenvalue sensitivity analysis capabilities with the differential operator method in the superhistory Monte Carlo method
Toshihiro Yamamoto
Annals of Nuclear Energy, Feb. 2018, Peer-reviewed, Lead author, Corresponding author
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Time-dependent Monte Carlo simulations for neutron noise in void-containing water flow
Toshihiro Yamamoto
Progress in Nuclear Energy, Nov. 2017, Peer-reviewed, Lead author, Corresponding author

Improvement and performance evaluation of the perturbation source method for an exact Monte Carlo perturbation calculation in fixed source problems
Hiroki Sakamoto; Toshihiro Yamamoto
Journal of Computational Physics, 15 Sep. 2017, Peer-reviewed, Last author, Corresponding author
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New findings on neutron noise propagation properties in void containing water using neutron noise transport calculations
Toshihiro Yamamoto; Hiroki Sakamoto
Progress in Nuclear Energy, 01 Jul. 2016, Peer-reviewed, Lead author, Corresponding author

Frequency domain optical tomography using a Monte Carlo perturbation method
Toshihiro Yamamoto; Hiroki Sakamoto
Optics Communications, Apr. 2016, Peer-reviewed, Lead author, Corresponding author
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Dynamic Monte Carlo calculation method by solving frequency domain transport equation using the complex-valued weight Monte Carlo method
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Nov. 2015, Peer-reviewed, Lead author, Corresponding author

Validation of ²⁴¹Am Capture Cross Section through Integral Test Using Criticality Data of Light-water Moderated MOX Cores
Ken Nakajima; Tadafumi Sano; Toshihiro Yamamoto
Energy Procedia, 01 May 2015, Peer-reviewed
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Experimental study on the safety of Kyoto University Research Reactor at natural circulation cooling mode
Jian Zhang; Xiuzhong Shen; Yasuyuki Fujihara; Tadafumi Sano; Toshihiro Yamamoto; Ken Nakajima
Annals of Nuclear Energy, Feb. 2015, Peer-reviewed

Higher harmonic analyses of the ²⁵²Cf source driven noise analysis method
Toshihiro Yamamoto
Annals of Nuclear Energy, Feb. 2015, Peer-reviewed, Lead author, Corresponding author
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Theory of power spectral density and feynman-alpha method in accelerator-driven system and their higher-order mode effects
Toshihiro Yamamoto
Nuclear Back-End and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident, 01 Jan. 2015, Peer-reviewed, Lead author, Corresponding author

A new concept of Monte Carlo kinetics parameter calculation using complex-valued perturbation
Toshihiro Yamamoto; Hiroki Sakamoto
Annals of Nuclear Energy, Sep. 2014, Peer-reviewed, Lead author, Corresponding author
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Higher order mode analyses of power spectral density and Feynman-α method in accelerator driven system with periodically pulsed spallation neutron source
Toshihiro Yamamoto
Annals of Nuclear Energy, Apr. 2014, Peer-reviewed, Lead author, Corresponding author

Frequency domain Monte Carlo simulation method for cross power spectral density driven by periodically pulsed spallation neutron source using complex-valued weight Monte Carlo
Toshihiro Yamamoto
Annals of Nuclear Energy, 2014, Peer-reviewed, Lead author, Corresponding author

Heterogeneity effect on neutron shielding in borated concrete and Monte Carlo-based cross section homogenization method for particle dispersed media
Toshihiro Yamamoto
Progress in Nuclear Science and Technology, 2014, Peer-reviewed, Lead author, Corresponding author

Review of studies on criticality safety evaluation and criticality experiment methods
Yoshitaka Naito; Toshihiro Yamamoto; Tsuyoshi Misawa; Yuichi Yamane
Journal of Nuclear Science and Technology, 01 Nov. 2013

Monte Carlo method with complex-valued weights for frequency domain analyses of neutron noise
Toshihiro Yamamoto
Annals of Nuclear Energy, 2013, Peer-reviewed, Lead author, Corresponding author

Energy-higher order mode analyses in Feynman-α method
Toshihiro Yamamoto
Annals of Nuclear Energy, 2013, Peer-reviewed, Lead author, Corresponding author

KUR反応度測定システムの開発とその適用
NAKAMORI AKIRA; SANO TADAFUMI; ZHANG JIAN; FUJIHARA YASUYUKI; YAMAMOTO TOSHIHIRO; NAKAJIMA KEN
KURRI KR, Jan. 2013

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
SANO TADAFUMI; FUJIHARA YASUYUKI; ZHANG JIAN; TAKAHASHI YOSHIYUKI; NAKAMORI AKIRA; YAMAMOTO TOSHIHIRO; NAKAJIMA KEN
KURRI KR, Jan. 2013

Monte Carlo method with complex weights for neutron leakage-corrected calculations and anisotropic diffusion coefficient generations
Toshihiro Yamamoto
Annals of Nuclear Energy, Dec. 2012, Peer-reviewed, Lead author, Corresponding author

Monte Carlo algorithm for buckling search and neutron leakage-corrected calculations
Toshihiro Yamamoto
Annals of Nuclear Energy, Sep. 2012, Peer-reviewed, Lead author, Corresponding author

KUR反応度測定システムについて
NAKAMORI TERU; HASEGAWA KEI; TSUCHIYAMA TATSUO; YAMAMOTO TOSHIHIRO; OKUMURA RYO; SANO TADAFUMI
UTNL-R(東京大学大学院工学系研究科原子力専攻), 2012

KUR炉心内照射領域における中性子束測定
FUJIWARA YASUYUKI; SANO TADAFUMI; ZHANG JIAN; TAKAHASHI YOSHIYUKI; YAMAMOTO TOSHIHIRO; NAKAJIMA KEN
京都大学原子炉実験所学術講演会報文集, Jan. 2012

Higher Order α Mode Eigenvalue Calculation by Monte Carlo Power Iteration
Toshihiro Yamamoto
Progress in Nuclear Science and Technology, 2012, Peer-reviewed, Lead author, Corresponding author

Non-regionwise weight cancellation for Monte Carlo higher order criticality calculations using kernel density estimator
Toshihiro Yamamoto
Annals of Nuclear Energy, Nov. 2011, Peer-reviewed, Lead author, Corresponding author

Higher order mode analyses in Feynman-α method
Toshihiro Yamamoto
Annals of Nuclear Energy, Jun. 2011, Peer-reviewed, Lead author, Corresponding author

Applicability of non-analog Monte Carlo technique to reactor noise simulation
Toshihiro Yamamoto
Annals of Nuclear Energy, Feb. 2011, Peer-reviewed, Lead author, Corresponding author

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
SANO TADAFUMI; FUJIHARA YASUYUKI; ZHANG JIAN; TAKAHASHI YOSHIYUKI; ONO KAZUOMI; MARUYAMA NAOYA; YAMAMOTO TOSHIHIRO; NAKAJIMA KEN
京都大学原子炉実験所学術講演会報文集, Jan. 2011

Study on double heterogeneity effect of Pu-rich agglomerates in mixed oxide fuel using cross section homogenization method for particle-dispersed media
Toshihiro Yamamoto
Annals of Nuclear Energy, Mar. 2010, Peer-reviewed, Lead author, Corresponding author

Benchmarkcritical experiments and FP worth evaluation fora heterogeneous system of uranium fuel rods and uranium solution poisoned with pseudo-fission-product elements
Kotaro Tonoike; Toshihiro Yamamoto; Yoshinori Miyoshi; Gunzo Uchiyama; Shouichi Watanabey
Journal of Nuclear Science and Technology, Apr. 2009, Peer-reviewed

Convergence of the second eigenfunction in Monte Carlo power iteration
Toshihiro Yamamoto
ANNALS OF NUCLEAR ENERGY, Jan. 2009, Peer-reviewed, Lead author, Corresponding author

Extension of cross section homogenization method for particle-dispersed media to layered particles
Toshihiro Yamamoto
Annals of Nuclear Energy, Jun. 2006, Peer-reviewed, Lead author, Corresponding author

Extension of effective cross section calculation method for neutron transport calculations in particle-dispersed media
Toshihiro Yamamoto; Yoshinori Miyoshi; Toshikazu Takeda
Journal of Nuclear Science and Technology, Jan. 2006, Peer-reviewed, Lead author, Corresponding author

Education method on monte carlo analysis in atomic energy
K. Sakurai; T. Yamamoto
Transactions of the Atomic Energy Society of Japan, 2005, Peer-reviewed

A logic of Monte Carlo calculation =from experience to science
K. Sakurai; T. Yamamoto
Transactions of the Atomic Energy Society of Japan, 2005, Peer-reviewed

A estimation methods of lower weight bound on neutron deep penetration problem with Monte Carlo method
Kiyoshi Sakurai; Toshihiro Yamamoto
Transactions of the Atomic Energy Society of Japan, 2005, Peer-reviewed

Development of a criticality evaluation method considering the particulate behavior of nuclear fuel
Mikio Sakai; Toshihiro Yamamoto; Minoru Murazaki; Yoshinori Miyoshi
Nuclear Technology, 2005, Peer-reviewed

Effect of particulate behavior on criticality evaluation in agitating powder of nuclear fuel
M. Sakai; T. Yamamoto; M. Murazaki; Y. Miyoshi
Powder Technology, 20 Oct. 2004, Peer-reviewed

Reliable method for fission source convergence of monte carlo criticality calculation with wielandt’s method
Toshihiro Yamamoto; Yoshinori Miyoshi
Journal of Nuclear Science and Technology, Feb. 2004, Peer-reviewed, Lead author, Corresponding author

Real time a value measurement with feynman-α method utilizing time series data acquisition on low enriched uranium system
Kotaro Tonoike; Toshihiro Yamamoto; Shoichi Watanabe; Yoshinori Miyoshi
Journal of Nuclear Science and Technology, Feb. 2004, Peer-reviewed

Effect of mixing condition of MOX powder and additives on criticality safety
Toshihiro Yamamoto; Yoshinori Miyoshi
Transactions of the American Nuclear Society, 2004, Peer-reviewed

Validating JENDL-3.3 for water-reflected low-enriched uranium solution systems using STACY ICSBEP benchmark models
Toshihiro Yamamoto; Yoshinori Miyoshi; Takehide Kiyosumi
Nuclear Science and Engineering, Sep. 2003, Peer-reviewed, Lead author, Corresponding author

Critical experiments on 10% enriched uranyl nitrate solution using an 80-cm-diameter cylindrical core
Yuichi Yamane; Yoshinori Miyoshi; Shouichi Watanabe; Toshihiro Yamamoto
Nuclear Technology, Mar. 2003, Peer-reviewed

Effect of higher-harmonic flux in exponential experiment for subcriticality measurement
Toshihiro Yamamoto; Yoshinori Miyoshi; Kotaro Tonoike; Hajime Okamoto; Toshikazu Ida; Shigeaki Aoki
Journal of Nuclear Science and Technology, Feb. 2003, Peer-reviewed, Lead author, Corresponding author

Simplified Estimation of Criticality Accident of MOX Powder Fuel.
三好慶典; 山本俊弘; 中島健
日本原子力研究所JAERI-Research, 2003

Present Status of Application of Monte Carlo Calculation for Large Nuclear Facilities in Japan
Kiyoshi Sakurai; Toshihiro Yamamoto
Transactions of the Atomic Energy Society of Japan, 2003, Peer-reviewed

Critical experiments of STACY homogeneous cores containing 10% enriched uranyl nitrate solution
Y. Miyoshi; T. Yamamoto; K. Tonoike; Y. Yamane
Proc. Int. Conf. on Nuclear Criticality Safety ICNC2003, 2003, Peer-reviewed

Modified quasi-steady-state method to evaluate the mean power profiles of nuclear excursions in fissile solution
Ken Nakajima; Toshihiro Yamamoto; Yoshinori Miyoshi
Journal of Nuclear Science and Technology, Nov. 2002, Peer-reviewed

Kinetic parameter βeff/ℓ measurement on low enriched uranyl nitrate solution with single unit cores (600훗;, 280T, 800훗;)of STACY
Kotaro Tonoike; Yoshinori Miyoshi; Tsukasa Kikuchi; Toshihiro Yamamoto
Journal of Nuclear Science and Technology, Nov. 2002, Peer-reviewed

Mechanisms of positive temperature reactivity coefficients of dilute plutonium solutions
Toshihiro Yamamoto; Yoshinori Miyoshi
Nuclear Science and Engineering, Nov. 2002, Peer-reviewed, Lead author, Corresponding author

Benchmark evaluation on single core system composed of 10% enriched uranyl nitrate solution at stacy
Yoshinori Miyoshi; Toshihiro Yamamoto; Shouichi Watanabe
Journal of Nuclear Science and Technology, Aug. 2002, Peer-reviewed

Reactivity measurements of erbium at tank-type critical assembly and analyses using endf/b-vi, JEF-2.2 and preliminary JENDL-3.3 Libraries
Kiyoshi Sakurai; Toshihiro Yamamoto
Journal of Nuclear Science and Technology, Aug. 2002, Peer-reviewed

Criticality safety benchmark experiment on 10% enriched uranyl nitrate solution using a 28-cm-thickness slab core
Toshihiro Yamamoto; Yoshinori Miyoshi; Tsukasa Kikuchi; Shouichi Watanabe
Journal of Nuclear Science and Technology, Jul. 2002, Peer-reviewed, Lead author, Corresponding author

Fission source convergence of monte carlo criticality calculations in weakly coupled fissile arrays
Toshihiro Yamamoto; Takemi Nakamura; Yoshinori Miyoshi
Journal of Nuclear Science and Technology, Jan. 2000, Peer-reviewed, Lead author, Corresponding author

臨界事故解析と核データ
中島健; 山本俊弘; 三好慶典
核データニュース\n, 2000

Overview of recent research activities of monte carlo simulation in Japan
Kiyoshi Sakurai; Toshihiro Yamamoto; Kohtaro Ueki; Takamasa Mori; Yasushi Nomura; Yoshitaka Naito
Journal of Nuclear Science and Technology, 2000, Peer-reviewed

Improvement of neutron source introduction method for absolute measurements of low reactor power
Toshihiro Yamamoto; Yoshinori Miyoshi
Journal of Nuclear Science and Technology, Nov. 1999, Peer-reviewed, Lead author, Corresponding author

Numerical validation of a modified neutron source multiplication method using a calculated eigenvalue
Toshihiro Yamamoto; Kiyoshi Sakurai; Yoshitaka Naito
Annals of Nuclear Energy, Jun. 1998, Peer-reviewed, Lead author, Corresponding author

Estimation of subcriticality with the computed values analysis using MCNP of experiment on coupled cores
K Sakurai; T Yamamoto; T Arakawa; Y Naito
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, May 1998, Peer-reviewed

Comparison of subcriticalities evaluated with exponential experiment and Monte Carlo calculation
K Sakurai; T Yamamoto
JOURNAL OF THE ATOMIC ENERGY SOCIETY OF JAPAN, Apr. 1998, Peer-reviewed

Measurements and Analyses of Reactivity Effect of Fission Product Nuclides in Epithermal Energy Range
Toshihiro Yamamoto; Kiyoshi Sakurai; Takenori Suzaki; Kazuo Nitta; Yoshio Hoshi; Ohichiro Horiki
Journal of Nuclear Science and Technology, Dec. 1997, Peer-reviewed, Lead author, Corresponding author

Accurate estimation of subcriticality using indirect bias estimation method, (II)
Kiyoshi Sakurai; Toshihiro Yamamoto; Takuya Arakawa; Yoshitaka Naito
Journal of Nuclear Science and Technology, Jun. 1997, Peer-reviewed

Accurate estimation of subcriticality using indirect bias estimation method, (I)
Toshihiro Yamamoto; Kiyoshi Sakurai; Takuya Arakawa; Yoshitaka Naito
Journal of Nuclear Science and Technology, Apr. 1997, Peer-reviewed, Lead author, Corresponding author

Benchmark Model of Critical Experiment at TCA for Integral Evaluation of Fission Product Nuclide Cross Sections
Kiyoshi Sakurap; Toshihiro Yamamoto
Journal of Nuclear Science and Technology, Feb. 1997, Peer-reviewed

Development of a subcritical benchmark method using the "Indirect Estimation Method for Calculation Error" - Noise analysis method
T Yamamoto; K Sakurai; T Arakawa; Y Naito
PROCEEDINGS OF THE TOPICAL MEETING ON CRITICALITY SAFETY CHALLENGES IN THE NEXT DECADE, 1997, Peer-reviewed

Perturbation of general boundary condition for an eigenvalue change in the neutron Boltzmann transport equation
Toshihiro Yamamoto
Nuclear Science and Engineering, 1996, Peer-reviewed, Lead author, Corresponding author

Most critical geometry of a fuel solution based on the transport boundary perturbation theory
Toshihiro Yamamoto
Journal of Nuclear Science and Technology, Jan. 1996, Peer-reviewed, Lead author, Corresponding author

Optimal geometry for fuel solution sloshing based on the boundary perturbation theory
Toshihiro Yamamoto; Benan Basoglu
Annals of Nuclear Energy, Oct. 1995, Peer-reviewed

IMPROVED DOSE ESTIMATES FOR NUCLEAR CRITICALITY ACCIDENTS
AD WILKINSON; B BASOGLU; CL BENTLEY; ME DUNN; CF HAUGHT; MJ PLASTER; T YAMAMOTO; HL DODDS; CM HOPPER
NUCLEAR TECHNOLOGY, Aug. 1995, Peer-reviewed

ANALYSIS OF A HYPOTHETICAL CRITICALITY ACCIDENT IN A WASTE SUPERCOMPACTOR
MJ PLASTER; B BASOGLU; CL BENTLEY; ME DUNN; AE RUGGLES; AD WILKINSON; T YAMAMOTO; HL DODDS
NUCLEAR TECHNOLOGY, Aug. 1995, Peer-reviewed

VALIDATION OF KENO V.A WITH ENDF/B-V CROSS-SECTIONS FOR U-233 SYSTEMS
ME DUNN; B BASOGLU; CL BENTLEY; C HAUGHT; MJ PLASTER; AD WILKINSON; T YAMAMOTO; HL DODDS
NUCLEAR TECHNOLOGY, Aug. 1995, Peer-reviewed

Improved dose estimates for nuclear criticality accidents
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
Nuclear Technology, Feb. 1995, Peer-reviewed

Analysis of a hypothetical criticality accident in a waste supercompactor
M. J. Plaster; B. Basoglu; C. L. Bentley; M. E. Dunn; A. E. Ruggles; A. D. Wilkinson; T. Yamamoto; H. L. Dodds
Nuclear Technology, Feb. 1995, Peer-reviewed

Validation of KENO V.a with ENDF/B-V cross sections for ²³³U systems
M. E. Dunn; B. Basoglu; C. L. Bentley; C. Haught; M. J. Plaster; A. D. Wilkinson; T. Yamamoto
Nuclear Technology, Feb. 1995, Peer-reviewed

Measurements and Analyses of the Ratio of ²³⁸U Captures to ²³⁵U Fission in Low-Enriched UO2 Tight Lattices
Ken Nakajima; Masanori Akai; Toshihiro Yamamoto; Masao Hashimoto; Takenori Suzaki
Journal of Nuclear Science and Technology, 1994, Peer-reviewed

Temperature effects on reactivity in light water moderated UO2 cores with soluble poisons
Yoshinori Miyoshi; Toshihiro Yamamoto; Takenori Suzaki; Iwao Kobayashi
Journal of Nuclear Science and Technology, Dec. 1992, Peer-reviewed

Analysis of temperature noise propagation in fast breeder core by the two-equation model
Toshihiro Yamamoto; Toshikazu Takeda; Tamotsu Sekiya; Hisashi Nakamura; Mitsuru Kamei
Nuclear Engineering and Design, Nov. 1989, Peer-reviewed, Lead author, Corresponding author

Misc.

Second Version of Data Collection Part of Nuclear Criticality Safety Handbook
奥野浩; 須山賢也; 須山賢也; 外池幸太郎; 山根祐一; 山本俊弘; 三好慶典; 内山軍藏
日本原子力研究開発機構JAEA-Data/Code, 2009

「モンテカルロ計算」夏季セミナー
桜井淳; 久米悦雄; 谷田部茂; 前川藤夫; 山本俊弘; 長家康展; 森貴正; 植木絋太郎; 内藤俶孝
日本原子力学会誌 = Journal of the Atomic Energy Society of Japan, 30 Oct. 2000

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
高山直毅; 山本俊弘; 佐野忠史; 堀順一; 中島健
日本原子力学会秋の大会予稿集(CD-ROM), 26 Aug. 2016

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
LEE JAEHONG; HORI JUN'ICHI; SANO TADAFUMI; NAKAJIMA KEN; TAKAHASHI YOSHIYUKI; YAMAMOTO TOSHIHIRO
日本原子力学会秋の大会予稿集(CD-ROM), 21 Aug. 2015

Current Status and Future Works of Kyoto University Research Reactor
Tadafumi SANO; Yasuhuki FUJIHARA; Yoshiyuki TAKAHASHI; Jian ZHANG; Toshihiro YAMAMOTO; Ken NAKAJIMA
2nd Asian Symposium on Material Testing Reactors, 11 Oct. 2012

Power Profile Analysis of JCO-TOKAI Criticality Accident i 1999
K. Nakajima; T. Yamamoto
Proc . Int. Conf. on Nuclear Criticality, ICNC2011, Sept. 19-23, 2011, Edinburgh, UK, Sep. 2011

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
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
日本原子力学会 2011年秋の大会, Sep. 2011

Energy Dependence of Feynman-α Method and its Application to Realistic Subcritical Systems
T. Yamamoto
Proc. Int. Conf. Nucl. Criticality Safety 2011, 2011

Characteristics Measurements of Kyoto University Research Reactor with Low-Enriched Uranium Core
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
日本原子力学会「2010年秋の大会」, Sep. 2010

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
SANO TADAFUMI; FUJIWARA YASUYUKI; ZHANG JIAN; TAKAHASHI YOSHIYUKI; ONO KAZUOMI; MARUYAMA NAOYA; NAKAJIMA KEN; YAMAMOTO TOSHIHIRO
日本原子力学会秋の大会予稿集(CD-ROM), 27 Aug. 2010

Nuclear human resources development activities for asian countries at JAEA/NuTEC
J. Sugimoto; H. Murakam; R. Sakamoto; T. Yamamoto
American Nuclear Society - Conference on Nuclear Training and Education, CONTE 2009, 2008, Peer-reviewed

Development of Criticality Accident Analysis Code AGNES
Y. Yamane; K. Nakajima; T. Yamamoto; Y. Miyoshi
Proc. 7th Int. Conf. Nuclear Criticality Safety、 ICNC2003, 20 Oct. 2004

Experimental Study on Criticality Safety-Study on Criticality Characteristics and Criticality Accident Phenomena of Low Enriched Uranyl Solution System at NUCEF-.
MIYOSHI YOSHINORI; YAMAMOTO TOSHIHIRO; TONOIKE KOTARO; NAKAJIMA KEN; YAMANE YUICHI
日本原子力研究所JAERI-Conf, Oct. 2003

Progress of Nuclear Safety Research-2002.
TAKESHITA ISAO; UEZUKA HIROSHI; TSUJI HIROKAZU; ISHIGAMI TSUTOMU; NAKAJIMA TAKESHI; YAMAMOTO TOSHIHIRO; ONO AKIO; MIYAUCHI MASAKATSU; ANODA YOSHINARI
日本原子力研究所JAERI-Review, Nov. 2002

Study on Neutronic and Thermal Characteristics of the Precipitaion Vessel in JCO Criticality Accident
Y. Miyoshi; T. Yamamoto; K. Nakajima; Y. Yamane; S. Watanabe
3rd NUCEF International Symposium (NUCEF 2001) (JAERI-Conf 2002-004)\n, 30 Nov. 2001

The Second Symp. on Monte Carlo Simmulation
桜井淳; 長家康展; 山本俊弘; 藪田尚宏
日本原子力学会誌 = Journal of the Atomic Energy Society of Japan, 30 Sep. 2001

Analysis of TRACY Experiment and JCO Criticality Accident by Using AGNES Code.
YAMANE YUICHI; NAKAJIMA KEN; YAMAMOTO TOSHIHIRO; NAKAMURA TAKEMI; MIYOSHI YOSHINORI
日本原子力研究所JAERI-Conf, Jul. 2000

Criticality Safety Analyses for Emergency Response Actions of JCO Accident.
YAMAMOTO TOSHIHIRO; NAKAMURA TAKEMI; NAKAJIMA KEN; MIYOSHI YOSHINORI
日本原子力研究所JAERI-Conf, Jul. 2000

JCO臨界事故の特性解析 (3) AGNES2を用いた初期バースト部の動特性評価
山根祐一; 中島健; 山本俊弘; 中村剛実; 三好慶典
日本原子力学会春の年会要旨集, 2000

JCO臨界事故の特性解析 (3) AGNES2を用いた初期バースト部の動特性評価
山根祐一; 中島健; 山本俊弘; 中村剛実; 三好慶典
日本原子力学会春の年会要旨集, 2000

JCO臨界事故の特性解析 (3) AGNES2を用いた初期バースト部の動特性評価
山根祐一; 中島健; 山本俊弘; 中村剛実; 三好慶典
日本原子力学会春の年会要旨集, 2000

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
中島健; 山根祐一; 山本俊弘; 中村剛実; 三好慶典
日本原子力学会2000年春の年会, 2000

Assessment of basic characteristics of implant materials for ferromagnetic hyperthermia.
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
International Congress of Radiation Oncology 1993 (ICRO ’93), 1993

Critical Experiments for Tight Lattices Using the TCA. (IV). Measurements of Au-wire activation distribution.
中島健; 金子俊幸; 橋本政男; 赤井昌紀; 柳沢宏司; 山本俊弘; 須崎武則
日本原子力学会秋の大会予稿集, 1991

Critical experiments for tight lattices using the TCA. (II). Evaluation of neutron spectrum index.
中島健; 山本俊弘; 須崎武則
日本原子力学会秋の大会予稿集, 1990

Awards

27 Mar. 2007
Atomic Energy Society of Japan, Outstanding Paper Award of Atomic Energy Society of Japan

02 Oct. 2014
International Conference on the Physics of Reactor, 2014, PHYSOR2014 Best Poster Award

External funds: Kakenhi

Research on high precision reactor noise analysis based on neutron transport theory for reactor core diagnosis
Grant-in-Aid for Scientific Research (C)
Kyoto University
Toshihiro Yamamoto
From 01 Apr. 2017, To 31 Mar. 2022, Project Closed
中性子;炉雑音;原子炉;異常診断;輸送理論;モンテカルロ;周波数領域;モンテカルロ法;感度解析;原子炉雑音;中性子輸送
https://kaken.nii.ac.jp/grant/KAKENHI-PROJECT-17K07011/

External funds: others

発電炉炉心健全性診断のための炉内中性子雑音の高精度解析手法の開発
関西原子力懇談会, 学術振興奨学金
From 01 Apr. 2018, To 31 Mar. 2021
Toshihiro Yamamoto

Last Updated :2025/12/19

Education

Teaching subject(s)

From 01 Apr. 2025, To 31 Mar. 2026
Nuclear Reactor Safety Engineering
C080, Fall, Graduate School of Engineering, 2

From 01 Apr. 2025, To 31 Mar. 2026
Nuclear Engineering Application Experiments
C068, Year-long, Graduate School of Engineering, 2

From 01 Apr. 2024, To 31 Mar. 2025
Nuclear Engineering Application Experiments
C068, Year-long, Graduate School of Engineering, 2

From 01 Apr. 2024, To 31 Mar. 2025
Nuclear Reactor Safety Engineering
C080, Fall, Graduate School of Engineering, 2

From 01 Apr. 2023, To 31 Mar. 2024
Nuclear Reactor Safety Engineering
C080, Fall, Graduate School of Engineering, 2

From 01 Apr. 2023, To 31 Mar. 2024
Nuclear Engineering Application Experiments
C068, Year-long, Graduate School of Engineering, 2

From 01 Apr. 2022, To 31 Mar. 2023
Nuclear Engineering Application Experiments
C068, Year-long, Graduate School of Engineering, 2

From 01 Apr. 2022, To 31 Mar. 2023
Nuclear Reactor Safety Engineering
C080, Fall, Graduate School of Engineering, 2

From Apr. 2012, To Mar. 2013
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2013, To Mar. 2014
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2014, To Mar. 2015
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2015, To Mar. 2016
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2016, To Mar. 2017
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2017, To Mar. 2018
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2018, To Mar. 2019
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2019, To Mar. 2020
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2020, To Mar. 2021
Nuclear Engineering Application Experiments
Year-long, 工学研究科

From Apr. 2020, To Mar. 2021
Nuclear Reactor Safety Engineering
Fall, 工学研究科

From Apr. 2021, To Mar. 2022
Nuclear Engineering Application Experiments
Year-long, 工学研究科

From Apr. 2021, To Mar. 2022
Nuclear Reactor Safety Engineering
Fall, 工学研究科

Participation in PhD Defense

FLOW CHARACTERISTICS AND MODELING OF THE UPWARD GAS-LIQUID TWO-PHASE FLOW IN VERTICAL ROD BUNDLE FLOW CHANNELS
HAN, Xu, Graduate School of Engineering, Sub-chief Examiner
24 Sep. 2021

Last Updated :2025/12/19

Administration

School management (title, position)

From 01 Apr. 2010, To 31 Mar. 2011
原子炉用燃料管理小委員会委員

Faculty management (title, position)

From 01 Nov. 2021
臨界装置部副部長

From 01 Apr. 2024
学術公開委員会委員

From 01 Apr. 2017
技術室運営委員会委員

From 01 Apr. 2010
安全管理部室長会議構成員

From 01 Apr. 2010
原子炉安全委員会委員

From 01 Apr. 2010
放射線障害防止委員会委員（旧保健物理委員会委員）

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