論文

• Kodai Fukuda, Toru Obara, Kenya Suyama. Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor, Nuclear Technology, published online, July 2024.
• Alexandru Catalin Stafie, Jun Nishiyama, Toru Obara. Practical Design of a Breed-and-Burn Lead-Cooled Fast Reactor with Rotational Fuel Shuffling Strategy, Nuclear Science and Engineering, published online, May 2024.
• Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara. Small rotational fuel-shuffling breed-and-burn sodium-cooled and nitride-fueled fast reactor with LBE reflectors, Annals of Nuclear Energy, Vol. 201, 110445, Mar. 2024.
• Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara. Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor with Nitride Fuel and Sodium Coolant, Nuclear Science and Engineering, Vol. 197, pp. 711-718, Apr. 2023.
• Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama, Toru Obara. Impact of the Melt-Refining Process on the Performance of Sodium-Cooled Rotational Fuel-Shuffling Breed-and-Burn Reactors, Nuclear Science and Engineering, Vol. 197, pp. 1520-1533, Jan. 2023.
• Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara. Feasibility of breed-and-burn reactor core design with nitride fuel and lead coolant, Annals of Nuclear Energy, Vol. 182, 109583, Nov. 2022.
• Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara. Neutron Balance Features in Breed-and-Burn Fast Reactors, Nuclear Science and Engineering, Vol. 196, pp. 322-341, Mar. 2022.
• Hoang Hai Nguyen, Odmaa Sambuu, Jun Nishiyama, Toru Obara. Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling, Nuclear Science and Engineering, Vol. 196, pp. 109-120, Jan. 2022.
• Kodai Fukuda, Takeshi Muramoto, Jun Nishiyama, Toru Obara. Impact of neutron generation time on released energy in falling fuel debris at supercritical condition, Journal of Nuclear Science and Technology, Vol. 59, No. 2, pp. 230-239, 2022.
• Takeshi Muramoto, Jun Nishiyama, Toru Obara. Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water, Journal of Nuclear Science and Technology, Vol. 59, No. 4, pp. 438-445, 2022.
• Anton Smirnov, Ekaterina Bogdanova, Pavel Pugachev, Ivan Saldikov, Georgy Tikhomirov, Hiroki Takezawa, Jun Nishiyama, Toru Obara. Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis, Journal of Nuclear Science and Technology, Vol. 59, pp. 34-43, 2022.
• Takeshi Muramoto, Jun Nishiyama, Toru Obara. Characteristics of reactivity change as fuel debris falls in water, Progress in Nuclear Energy, Vol. 139, 103857, July 2021.
• Hiroki Takezawa, Delgersaikhan Tuya, Toru Obara. Calculation of Transient Parameters of the Integral Kinetic Model with Delayed Neutrons for Space-dependent Kinetic Analysis of Coupled Reactors, Nuclear Science and Engineering, Vol. 195, pp. 1326-1246, July 2021.
• Hoang Hai Nguyen, Jun Nishiyama, Toru Obara. Optimization of reactor size in the small sodium-cooled CANDLE burning reactor, Annals of Nuclear Energy, Vol. 153, 108040, Jan. 2021.
• Kodai Fukuda, Jun Nishiyama, Toru Obara. Supercritical Transient Analysis for Ramp Reactivity Insertion Using Multiregion Integral Kinetics Code, Nuclear Science and Engineering, Vol. 195, pp. 453-463, Jan. 2021.
• Anton D. Smirnov, Ekaterina V. Bogdanova, Pavel A. Pugachev, Ivan S. Saldikov, Mikhail Yu. Ternovykh, Georgy V. Tikhomirov, Hiroki Takezawa, Takeshi Muramoto, Jun Nishiyama, Toru Obara. Neutronic modeling of a subcritical system with corium particles and water (from international benchmark), Nuclear Energy and Technology, Vol. 6, No. 3, pp. 155-160, Sept. 2020.
• P.A. Pugachev, E.V. Bogdanova, I.S. Saldikov, A.D. Smirnov, M.Y. Ternovykh, G.V. Tikhomirov, H. Takezaw, T. Muramoto, J. Nishiyama, T. Obara. Visualization of neutron characteristics distribution of debris particles, Scientific Visualization, Vol. 12, No. 3, pp. 100-107, Sept. 2020.
• Kodai Fukuda, Jun Nishiyama, Toru Obara. Reactivity Feedback Effect on Supercritical Transient Analysis of Fuel Debris, Nuclear Science and Engineering, Vol. 194, pp. 493-507, July 2020.
• Hoang Hai Nguyen, Jun Nishiyama, Toru Obara. Burnup Performance of CANDLE Burning Reactor Using Sodium Coolant, Nuclear Science and Engineering, Vol. 194, pp. 1128-1142, July 2020.
• Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Evaluation of Discharged Fuel in Preproposed Breed-and-Burn Reactors from Proliferation, Decay Heat, and Radiotoxicity Aspects, Nuclear Science and Engineering, Vol. 194, pp. 405-413, May 2020.
• Kodai Fukuda, Delgersaikhan Tuya, Jun Nishiyama, Toru Obara. Radiation Dose Analysis in Criticality Accident of Fuel Debris in Water, Nuclear Science and Engineering, Vol. 194, pp. 181-189, Mar. 2020.
• Van Khanh Hoang, Jun Nishiyama, Toru Obara. Effects of compensating for fuel losses during the melt-refining process for a small CANDLE reactor, Annals of Nuclear Energy, Vol. 135, 106969, Jan. 2020.
• Delgersaikhan Tuya, Toru Obara. Development of Monte Carlo Neutron Transport Method-Based Supercritical Transient Code with Time-Dependent Feedback Capability, Nuclear Science and Engineering, Vol. 193, pp. 481-494, May 2019.
• Takeshi Muramoto, Jun Nishiyama, Toru Obara. Numerical analysis of criticality of fuel debris falling in water, Annals of Nuclear Energy, Vol. 131, pp. 112-122, Mar. 2019.
• Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Concept of breed and burn reactor with spiral fuel shuffling, Annals of Nuclear Energy, Vol. 127, pp. 130-138, Jan. 2019.
• Hiroki Osato, Jun Nishiyama, Toru Obara. Application of Melt-refining Process to Transition State of CANDLE Burning Fast Reactor, Annals of Nuclear Energy, Vol. 128, pp. 77-83, Jan. 2019.
• Irwan Liapto Simanullang, Jun Nishiyama, Toru Obara. Potential for the use of a liquid activation circulation material to measure the neutron flux in a high gamma-ray background, Nuclear Instruments and Methods in Physics Research, A, Vol. 903, pp. 109-113, July 2018.
• Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Concept of Stationary Wave Reactor with Rotational Fuel Shuffling, Nuclear Science and Engineering, Vol. 191, pp. 178-186, June 2018.
• Van Khanh Hoang, Jun Nishiyama, Toru Obara. Design concepts of small CANDLE reactor with melt-refining process, Progress in Nuclear Energy, Vol. 108, pp. 233-242, June 2018.
• Irwan Liapto Simanullang, Toru Obara. Burnup performance of MOX and Pu-ROX fuels in small pebble bed reactor with accumulative fuel loading scheme, Annals of Nuclear Energy, Vol. 120, pp. 450-460, June 2018.
• Hiroki Osato, Jun Nishiyama, Toru Obara. Initial core design of CANDLE burning fast reactor using plutonium from LWR spent fuel, Annals of Nuclear Energy, Vol. 120, pp. 501-508, June 2018.
• Delgersaikhan Tuya, Toru Obara. Supercritical transient analysis in hypothetical fuel-debris systems by multi-region approach based on integral kinetic model, Annals of Nuclear Energy, Vol. 120, pp. 167-177, May 2018.
• Odmaa Sambuu, Jamyansuren Terbish, Toru Obara, Norov Nanzad, Munkhbat Byambajav. Design parameters in an annular, prismatic HTGR for passive decay heat removal, Annals of Nuclear Energy, Vol. 111, pp. 441-448, Jan. 2018.
• Van Khanh Hoang, Toru Obara. Impact of Neutron Spectrum Shift on Breed and Burn Reactor Concept, Energy Procedia, Vol. 131, pp. 33-44, Dec. 2017.
• Irwan Liapt Simanullang, Toru Obara. Burnup Performance of a PBR with an Accumulative Fuel Loading Scheme Utilizing Burnable Poison Particles in UO2and ROX Fuels, Energy Procedia, Vol. 131, pp. 61-68, Dec. 2017.
• Hiroki Osato, Jun Nishiyama, Toru Obara. Study on CANDLE Burning Fast Reactor with Initial Core Using Plutonium from LWR Spent Fuel, Energy Procedia, Vol. 131, pp. 15-20, Dec. 2017.
• Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara. Improved approach to multi-region supercritical transient analysis based on the integral kinetic model and Monte Carlo method, Nuclear Science and Engineering, Vol. 188, pp. 33-42, July 2017.
• Delgersaikhan Tuya, Toru Obara. Supercritical transient analysis in coupled fuel debris systems of symmetric and asymmetric geometry using integral kinetic model, Annals of Nuclear Energy, Vol. 109, pp. 113-119, May 2017.
• Irwan Liapto Simanullang, Toru Obara. Burnup performance of rock-like oxide (ROX) fuel in small pebble bed reactor with accumulative fuel loading scheme, Annals of Nuclear Energy, Vol. 107, pp. 110-118, May 2017.
• Julia Abdul Karim, Jun Nishiyama, Toru Obara. Effects of cooling interval time in melt and refining process for CANDLE burning, Annals of Nuclear Energy, Vol. 105, pp. 144-149, Mar. 2017.
• Takuya Umano, Kenichi Yoshiioka, Toru Obara. Improvement of the “best representativity” method toward an industrial application, Annals of Nuclear Energy, Vol. 105, pp. 311-328, 2017.
• Hiroki Takezawa, Toru Obara. Passive measure for preventing recriticality of fuel debris dust for defueling at Fukushima Daiichi nuclear power station, Journal of Nuclear Science and Technology, Vol. 53, No. 12, pp. 1960-1967, Apr. 2016.
• Irwan Liapto Simanullang, Toru OBARA. Improvement of core design of small pebble bed reactor with accumulative fuel loading scheme, Annals of Nuclear Energy, Vol. 94, pp. 87-92, Mar. 2016.
• Julia ABDUL KARIM, Jun NISHIYAMA, Toru OBARA. Application of melt and refining procedures in the CANDLE reactor concept, Annals of Nuclear Energy, Vol. 90, pp. 275-283, Jan. 2016.
• Delgersaikhan Tuya, Toru Obara. Supercritical kinetic analysis in simplified system of fuel debris using integral kinetic model, Annals of Nuclear Energy, Vol. 91, pp. 59-64, Jan. 2016.
• Odmaa Sambuu, Toru OBARA. Impact of power density profile on passive decay-heat removal in prismatic HTGR, Annlas of Nuclear Energy, Vol. 87, pp. 23-29, Jan. 2016.
• Odmaa Sambuu, Toru OBARA. Possible design of PBR for passive decay-heat removal, Journal of Nuclear Science and Technology, Vol. 53, No. 9, pp. 1296-1309, 2016.
• Hai Quan Ho, Toru Obara. Design concept for a small pebble bed reactor with ROX fuel, Annals of Nuclear Energy, Vol. 86, pp. 471-478, Oct. 2015.
• Haruka Kikuchi, Toru Obara. Development of Transient Analysis Code for Estimation of Total Released Energy in a Two-Fuel-Solution-Tank System, Annals of Nuclear Energy, Vol. 87, pp. 486-493, Oct. 2015.
• Topan Setiadipura, Toru Obara. Optimization of Start-up Fuel Management for OTTO Cycle Pebble Bed Reactor, Energy Procedia, Vol. 71, pp. 42-51, May 2015.
• Piyatida Trinuruk, Toru Obara. Particle-type Burnable Poisons for Thorium-based Fuel in HTGR, Energy Procedia, Vol. 71, pp. 22-32, May 2015.
• Haruka Kikuchi, Toru Obara. Kinetic Behavior in Criticality Accident of Two Fuel Solution Tanks, Progress in Nuclear Energy, Vol. 82, pp. 96-101, May 2015.
• Odmaa Sambuu, Toru OBARA. Comparative study on HTGR Designs for Passive Decay Heat Removal, Progress in Nuclear Energy, Vol. 82, pp. 37-45, May 2015.
• Takuya Umano, Keinich Yoshioka, Toru Obara. Application of the “best representativity” method to a PWR fuel calculation using the critical experiments at the Toshiba NCA facility, Annals of nuclear energy, Vol. 85, pp. 78-92, May 2015.
• Odmaa Sambuu, Toru OBARA. Above-ground HTGR design for passive decay heat removal, Journal of Nuclear Science and Technology, Vol. 52, No. 6, pp. 857-871, Apr. 2015.
• Hai Quan Ho, Toru OBARA. Burnup performance of OTTO cycle pebble bed reactors with ROX fuel, Annals of Nuclear Energy, Vol. 83, pp. 1-7, Apr. 2015.
• Odmaa Sambuu, Toru OBARA. Neutronic and thermo-hydraulic analyses of a small, long-life HTGR for passive decay-heat removal, Journal of Nuclear Science and Technology, Vol. 52, No. 12, pp. 1519-1529, 2015.
• Hirokazu Ohta, Takanari Ogata, Toru OBARA. Design Study on a Fast Reactor Metal Fuel Attaining Very High Burnup, Nuclear Technology, Vol. 187, pp. 198-207, Aug. 2014.
• Odmaa Sambuu, Toru OBARA. Possible desing of long-life small prismatic HTGR for passive decay heat removal, Nuclear Science and Engineering, American Nuclear Society, Vol. 177, pp. 97-109, May 2014.
• Topan Setiadipura, Toru OBARA. Development of Monte Carlo-based pebble bed reactor fuel management code, Annals of Nuclear Energy, Vol. 71, pp. 313-321, May 2014.
• Takuya Umano, Kenichi Yoshioka, Toru OBARA. Development of a “best representativity” method for experimental data analysis and an application to the critical experiments at the Toshiba NCA facility, Journal of Nuclear Science and Technology, Vol. 41, No. 5, pp. 608-625, Feb. 2014.
• Masao Komeda, Toru OBARA. Core designs based on research reactors for neutron transmutation doping of silicon, Annals of Nuclear Energy, Vol. 65, pp. 338-344, 2014.
• Piyatida Trinuruk, Toru OBARA. Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures, Annals of Nuclear Energy, Vol. 63, pp. 437-445, Sept. 2013.
• Piyatida Trinuruk, Toru OBARA. Small, long-life high temperature gas-cooled reactor free from prompt supercritical accidents by particle-type burnable poisons, Journal of Nuclear Science and Technology, Vol. 50, No. 9, pp. 898-912, July 2013.
• Dwi Irwanto, Toru OBARA. Decay Heat Removal without Forced Cooling on a Small Simplified PBR with an Accumulative Fuel Loading Scheme, Annlas of Nuclear Energy, Vol. 60, pp. 383-395, June 2013.
• Toru OBARA, Taiki Onoe. Flattening of burnup reactivity in long-life prismatic HTGR by particle type burnable poisons, Annlas of Nuclear Energy, Vol. 57, pp. 216-220, Mar. 2013.
• Masao Komeda, Kozo Kawasaki, Toru OBARA. A new irradiation method with a neutron filter for silicon neutron transmutation doping at the Japan research reactor No.3 (JRR-3), Applied Radiation and Isotopes, Vol. 74, pp. 70-77, Feb. 2013.
• Byambajav Munkhbat, Toru OBARA. Conceptual design of a small nuclear reactor for large-diameter NTD-Si using short PWR fuel assemblies, Journal of Nuclear Science and Technology, Vol. 50, No. 1, pp. 46-58, Jan. 2013.
• Masao Komeda, Toru OBARA. Study on the burn-up charactierisitics of a thermal neutron filter containing B4C particles for NTD-Si irradiation, Annlas of Nuclear Energy, Vol. 53, pp. 35-39, 2013.
• Byambajav Munkhbat, Toru Obara. Design simplification of a small nuclear reactor for large-diameter neutron transmutation doping silicon using control rods, Journal of Nuclear Science and Technology, Vol. 49, No. 8, pp. 845-856, July 2012.
• Byambajav Munkhbat, Toru Obara. Design Concept of a Small Nuclear Reactor for Large-Diameter NTD-Si using a Conventional PWR Full-Length Fuel Assembly, Journal of Nuclear Science and Technology, Vol. 49, No. 5, pp. 535-543, May 2012.
• Dwi Irwanto, Toru Obara. Burnup Characteristics and Fuel Cycle Economics of Mixed Uranium-Thorium Fuel in a Simplified Small Pebble Bed Reactor, Journal of Nuclear Science and Technology, Vol. 49, No. 2, pp. 222-229, Feb. 2012.
• Hiroki Takezawa, Toru Obara. New Approach to Space-Dependet Kinetic Analysis by the Integral Kinetic Model, Nuclear Science and Engineering, Vol. 171, pp. 1-12, 2012.
• Odmaa Sambuu, Toru Obara. Conceptual design for a small modular district heating reactor for Mongolia, Annlas of Nuclear Energy, Vol. 47, pp. 210-215, 2012.
• 田川 祐樹, 森 伸介, 鈴木 正昭, 山中 一郎, 小原 徹, 劉 醇一, 加藤 之貴. 誘電体バリア放電反応器と固体酸化物形電気分解セルのハイブリッド化による相乗的CO2分解, 化学工学論文集, Vol. 37, No. 2, pp. 114-119, Apr. 2011.
• Dwi Irwanto, Toru OBARA. Burnup Characteristics of a Peu a` Peu Fuel Loading Scheme in a 110 MWt Simplified Pebble Bed Reactor, Journal of Nuclear Science and Technology, Vol. 48, No. 11, pp. 1385-1395, 2011.
• Toru OBARA, YU YAMAZAWA, Toshinobu Sasa. Polonium Decontamination Performance of Stainless Steel Mesh Filter for Lead Alloy-Cooled Reactors, Progress in Nuclear Energy, Vol. 53, pp. 1056-1060, 2011.
• Toru Obara, Hiroki Takezawa. Kinetic Analysis of Weakly Coupled Systems Using Probability Density Function of Coupling Coefficient Obtained by Monte Carlo Method, Progress in Nuclear Science and Technology, Vol. 2, pp. 263-266, 2011.
• Yukitaka Kato, Toru Obara, Ichiro Yamanaka, Shinsuke Mori, Arnoldus Lambertus Dipu, Junichi Ryu, Yutaka Ujisawa, Masaaki Suzuki. Performance analysis of active carbon recycling energy system, Progress in Nuclear Energy, Vol. 53, pp. 1071-1021, 2011.
• Toru OBARA. Study on Concept of Innovative Nuclear Reactors and Nucler Safety, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 35, p. 65, 2011.
• Hiroki Takezawa, Toru Obara. Calculation of the Integral Kinetic Model Transient Parameters by the Monte Carlo Method for Space-Dependent Kinetic Analysis, Nuclear Science and Engineering, Vol. 164, pp. 1-7, Jan. 2010.
• Toru OBARA, Byambajav MUNKHBAT. Study on Neutron Transmutation Doping for Sillicon Semiconductor using PWR Fuel Core,, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 34, p. 70, 2010.
• Toru OBARA, Dwi Irwanto. Study on Peu-a-Peu Fuel Loading Scheme in Small PBR, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 34, p. 71, 2010.
• Toru OBARA, Hiroki TAKEZAWA. Study on Numerical Simulation of Nuclear Pumped Laser by Coupled Pulse Reactor, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 34, pp. 69, 2010.
• Hiroki Takezawa, Toru Obara, Andrey Gulevich, Oleg Kukharchuk. Criticality Analysis of Pulse Core and Laser Module Coupled Small Reactor with Low Enriched Uranium, Progress in Nuclear Energy, 50, pp. 304-307, 2008.
• Hiroki Takezawa, Toru Obara. Integral Kinetic Model for Weakly Coupled Systems, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 32, p. 63, 2008.
• Toru Obara, Takeru Koga, Terumitsu Miura, Hiroshi Sekimoto. Polonium evaporation and adhesion experiments for the development of polonium filter in lead–bismuth cooled reactors, Progress in Nuclear Energy, Elsevier Ltd., Vol. 50, pp. 556-559, 2008.
• Toru Obara. Future of International Cooperative Activity for Graduate School Eduation in Nuclear Field, Progress in Nuclear Energy, Vol. 50, pp. 126-128, 2008.
• H.Q.Huda, T.Obara. Development and testing of analytical models for the pebble bed type HTRs, Annlas of Nuclear Energy, Vol. 35, No. 11, pp. 1994-2005, 2008.
• Toru Obara, Liem Peng Hong. Concept of Small Reactor for Neutron Transmutation Doping, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 32, p. 61, 2008.
• M.Q. Huda., S.I. Bhuiyan, T. Obara. Burnup alnalysis and in-core fuel management study of the 3MW TRIGA MARK II research reactor, Annals of Nuclear Energy, Vol. 35, No. 1, pp. 141-147, 2008.
• Toru Obara, Hiroki Takezawa. Pulse reactor system for nuclear-pumped laser using low-enriched uranium, Energy Conversion and Management, Vol. 49, pp. 1892-1897, 2008.
• Toru Obara, Hiroki Takezawa. Low Enriched Uranium Pulse Reactor for Nuclear-Pumped Laser, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 31, No. 1, p. 63, 2007.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Experimental verification of thermal decomposition of lead polonide, Annals of Nuclear Energy, Elsevier Ltd., Vol. 34, No. 11, pp. 926-930, 2007.
• Terumitsu MIURA, Toru OBARA, Hiroshi SEKIMOTO. Investigation of polonium decontamination from stainless steel surfaces using the baking method, Nuclear Technology, Vol. 155, pp. 78-89, 2006.
• Toru Obara, Takeru Koga, Terumitsu Miura, Hiroshi Sekimoto. Preliminary Study on Polonium Filter for Lead Alloy Cooled Reactors, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 30, p. 247, 2006.
• T. Obara, T. Mirura, H. Sekimoto. Fundamental Study of Polonium Contamination by Neutron Irradiated Lead-Bismuth Eutectic, Journal of Nuclear Materials, Vol. 343, No. 1-3, pp. 297-301, 2005.
• Minoru Takahashi, Shoji Uchida, Koji Hata, Takaharu Matsuzawa, Hiroo Osada, Yoshiyuki Kasahara, Naoki Sawa, Yoshiyuki Okubo, Toru Obara, Elin Yusibani. Pb-Bi-Cooled Direct Contact Boiling Water Small Reactor, Progress in Nuclear Eneregy, Vol. 47, No. 1-4, pp. 190-201, 2005.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Study on Polonium Contamination Removal by Baking Method, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 29, No. 1, pp. 131, 2005.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Polonium Release in Direct Contact of Lead-Bismuth Eutectic with Water, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 29, No. 2, pp. 161, 2005.
• Terumitsu Miura, Toru OBARA, Hiroshi Sekimoto. Removal of Polonium from Stainless Steel Surface contaminated by Neutron Irradiated Lead-Bismuth, Progress in Nuclear Eneregy, Vol. 47, No. 1-4, pp. 624-631, 2005.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Development of Polonium Surface Contamination Measure in Lead-Bismuth Eutectic Coolant, Progress in Nuclear Eneregy, Vol. 46, No. 1-4, pp. 577-585, 2005.
• Kousuke SAITO, Masayuki IGASHIRA, Jun KAWAKAMI, Toshiro OHSAKI, Toru OBARA, Hiroshi SEKIMOTO. Measurement of keV-Neutron Capture Corss Sections and Capture Gamma-Ray Spectra of 209B, Journal of Nuclear Science and Technology, Vol. 41, No. 4, pp. 406-412, 2004.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Unfolding of polonium distribution in depth of irradiated lead-bismuth eutectic from α-particle pulse-height distribution, Applied Radiation and Isoopes, Vol. 61, pp. 1307-1311, 2004.
• Toru OBARA Terumitsu Miura, Hiroshi SEKIMOTO. Development of Measure for Polonium Contamination on Quartz Glass by neutron Irradiated Lead-Bismuth Eutectic, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 28, pp. 56, 2004.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Development of Electric Furnace for Polonium Removal Experiment, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 28, pp. 117-118, 2004.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Polonium Distribution Analysis by Alpha-ray Spectrum Unfolding Method, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 28, p. 57, 2004.
• Toru OBARA Terumitsu Miura, Hiroshi SEKIMOTO. Polonium Distribution Analysis by Alpha-ray Spectrum Unfoloding Method, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 28, p. 57, 2003.
• Toru Obara, Terumitsu Miura, Yoshiyuki Fujita, Yasuo Ando, Hiroshi Sekimoto. Preliminary Study of the Removal of Polonium Contamination by Neutron-Irradiated Lead-Bismuth Eutectic, Annals of Nuclear Energy, Vol. 30, pp. 497-502, 2003.
• Toru OBARA, Terumitsu Miura, Hiroshi SEKIMOTO. Study of Polonium Contamination Issure by Neutron Irradiated Lead-Bismuth Eutectic, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 27, p. 78, 2003.
• Toru OBARA, Hiroshi SEKIMOTO. Study of Polonium Contamination by Neutron-Irradiated Lead-Bismuth Eutectic, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 26, p. 77, 2002.
• Toru OBARA. Joint Study with State Scientific Centre of Russian Federation, Institute of Physics and Power Engineering on Neutronic Transport Calculation for Nuclear Pumped Laser System, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 24, p. 76, 2000.
• Toru OBARA. Joint Study with Russian Research Center “Kurchatov Institute” on Monte-Carlo Calcualtion Method in Reactor Physics, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 24, p. 74, 2000.
• Toru OBARA. Study on Numerical Analysis Method for Criticality Accidents of Uranium Fuel Solution, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 24, p. 77, 2000.
• Toru OBARA, Hiroshi SEKIMOTO. Study of the “keff of the World” Problem in Monte Carlo Eigenvalue Calculation, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 23, p. 56, 1999.
• T. OBARA. Report on Joint Study in Russian Research Center “Kurchatov Insitite, Russian Resarch Center “Kurchatov Institute” Nuclear Reactors Institute Report, No. 36/21-99, 1999.
• Toru OBARA, Hiroshi SEKIMOTO. Study of Positive Temperature Coefficient Effect on Dilute Plutonium-Water Solution, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 22, p. 82, 1998.
• Toru OBARA, Hiroshi Sekimoto. Effect of Low Energy Resonance Absorber on Positive Neutron Temperature Coefficient of Dilute Plutonium-Water Solution, Nuclear Science and Engineering, Vol. 130, No. 3, pp. 386-390, 1998.
• Toru OBARA, Hiroshi SEKIMOTO. Detection of Reactivity Feedback Effects in Fast Driver In-pile Experimental Reactor, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 21, pp. 84-85, 1997.
• Toru OBARA, Hiroshi SEKIMOTO. Concept and Basic Performance of an In-pile Experimental Reactor for Fast Breeder Reactors using Fast Driver Core, Annals of Nuclear Energy, Vol. 24, No. 18, pp. 1491-1513, 1997.
• Toru OBARA, Hiroshi SEKIMOTO. Study of Particle Bed Fast Driver Core for In-pile Experimental Reactor, Bulletin of the Research Laboratoy for Nuclear Reactors, Vol. 20, pp. 101-102, 1996.
• Toru OBARA, Hiroshi SEKIMOTO. Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles, Journal of Nuclear Science and Technology, Vol. 33, No. 7, pp. 547-554, 1996.
• Toru OBARA, Hiroshi SEKIMOTO. Feasibility of Zero Temperature Coefficient Core with Highly Diluted Fuel and Graphite Moderator, Annals of Nuclear Energy, Vol. 22, No. 6, pp. 331-337, 1995.
• Toru OBARA, Hiroshi SEKIMOTO. New Design Concept for a Fast Neuron Spectrum Pulse Reactor Core, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 19, p. 73, 1995.
• H. Akatsuka, T. Ohsaki, T. Obara, M. Igashira, M. Suzuki, Y. Fujii-e. Scientific Feasibility of Incineration in SCNES, Progress in Nuclear Energy, Vol. 29, pp. 477-484, 1995.
• Toru OBARA, Hiroshi SEKIMOTO. Study of Zero Temperature Coefficient Thermal Core, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 18, p. 78, 1994.
• Toru OBARA, Hiroshi SEKIMOTO. Study of Test Reactor for Reactivity Feedback Effects in FBR Core Damage Accidents, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 18, pp. 77, 1994.
• Toru OBARA, Hiroshi SEKIMOTO. Possibility of Test Reactor for Reactivity Feedback Effects in Core Damage Accident, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 17, p. 63, 1993.
• Toru OBARA, Hiroshi SEKIMOTO. New Numerical Method for Equilibrium Cycles of High Conversion Pebble Bed Reactors, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 16, p. 60, 1992.
• Toru OBARA, Hiroshi SEKIMOTO. New Numerical method for Equilibrium Cycles of High Conversion Pebble Bed Reactors, Journal of Nuclear Science and Technology, Vol. 28, No. 10, pp. 947-957, 1991.
• Yukinori HIROSE, Peng Hong LIEM, Eiichi SUETOMI, Toru OBARA, Hiroshi SEKIMOTO. Fuel Management Effects on Inherent Safety of Modular High Temperature Reactor, Journal of Nuclear Science and Technology, Vol. 26, No. 7, pp. 647-772, 1989.
• Hiroshi SEKIMOTO, Toru OBARA, Shigeru YUKINORI, Eiichi SUETOMI. New Method to Analyze Equilibrium Cycle of Pebble-Bed Reactors, Journal of Nuclear Science and Technology, Vol. 24, No. 10, pp. 765-772, 1987.

著書

• 小原徹. 原子力年鑑2022, 原子力年鑑2022, 日刊工業新聞社, Oct. 2021.
• Toru Obara, Vladimir Artisyuk. OINPE - COE-INES The first International Workshop “Russia-Japan International Research Cooperation and Nuclear Education Toward Innovative Nuclear Energy Systems, ISSN 5-89075-024-0, 2006.
• Toru OBARA, Zaki Su’ud. BOOK OF PRESENTATIONS,Tokyo Tech COE-INES - Indonesia International Symposium 2005 "Prospect of Nuclear Energy in Indonesia", ISBN4-903054-02-0 C3053, 2006.
• Hiroshi Sekimoto, Toru Obara, Georgy I. Toshinsky. Book of Presentations Japan-Russia LBE Coolant Workshop, Bulletion of the Research Laboratory for Nuclear Reactors, Special Issue, No. 4, 2001.

国際会議発表 (査読有り)

• Alexandru Catalin Stafie, Toru Obara. Plutonium vector analysis for optimizing the RFBB strategy applied for a nitride fuel, lead-cooled fast reactor, International Conference on Nuclear Fuel Cycle (GLOBAL2024), Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024), 1C-01-01, Oct. 2024.
• Xucheng Zhao, Toru Obara. Replication of CANDLE Burning Wave in Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor, International Conference on Nuclear Fuel Cycle (GLOBAL2024), Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024), 1C-01-03, Oct. 2024.
• T. Obara, N. Horiike. Fuel Cycle Features of Sodium-Cooled Metal Fuel RFBBs, International Conference on Nuclear Fuel Cycle (GLOBAL2024), Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024), 3C-01-03, Oct. 2024.
• Xucheng Zhao, Toru Obara. Feasibility of Innovative Lead-Bismuth-cooled Fast Reactor Core Design Using Metallic Fuel, Global Symposium on Lead and Lead Alloy Cooled Nuclear Energy Science and Technology 2024 (GLANST 2024), Sept. 2024.
• Odmaa Sambuu, Van Khanh Hoang, Toru Obara. Feasibility of RFBBs with Silicide Fuel and Sodium Coolant, 2023 American Nuclear Society Winter Conference, Transactions of the American Nuclear Society, Vol. 129, pp. 896-899, Nov. 2023.
• Jun Nishiyama, Seiya Manabe, Hideki Harano, Toru Obara. Development of the fuel debris criticality characteristics measurement system, The 12th International Conference on Nuclear Criticality Safety (ICNC2023), SS1, Oct. 2023.
• Hiroki Takezawa, Toru Obara. Preliminary analysis of GODIVA supercritical transient behaviors by using the Multi-region Integral Kinetic code including delayed neutron effect, The 12th International Conference on Nuclear Criticality Safety (ICNC2023), TR8, Oct. 2023.
• Toru Obara, Taro Fumimoto, Takeshi Muramoto, Jun Nishiyama. Criticality Analysis of Fuel Debris Falling in Water Considering Water Surface Oscillation, 2022 American Nuclear Society Winter Meeting, Transactions of the American Nuclear Society, Vol. 125, pp. 740-741, Nov. 2022.
• Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara. Concept of lead-cooled rotational fuel-shuffling breed-and-burn fast reactor, 2022 American Nuclear Society Winter Meeting, Transactions of the American Nuclear Society, Vol. 125, pp. 1052-1054, Nov. 2022.
• T. OBARA, O. SAMBUU, V.K. HOANG, J. NISHIYAMA. IMPACT OF CLADDING MATERIAL ON NEUTRONIC BALANCE IN BREED-AND-BURN FAST REACTORS, International Conference on Fast Reactors and Related Fuel Cycles FR22 (CN291), Internationa Atomic Energy Agency, IAEA-CN-291/397, July 2022.  公式リンク  
  
• O. SAMBUU, J. NISHIYAMA, V.K. HOANG, T. OBARA. Impact of Core Materials on the Fuel Cladding Irradiation Damage in Breed-and-Burn Fast Reactors, International Conference on Fast Reactors and Related Fuel Cycles FR22 (CN291), Internationa Atomic Energy Agency, IAEA-CN-291/393, July 2022.  公式リンク  
  
• Hoang Hai Nguyen, Jun Nishiyama, Toru Obara. Development of a Monte Carlo based code system for CANDLE burning analysis, Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA+MC2020), Proc. of SNA+MC2020, 3238578, Nov. 2020.
• Kodai Fukuda, Jun Nishiyama, Toru Obara. Radiation Dose by Criticality Accidents of Fuel Debris in Water, Reactor Physics Asia Conference 2019 (RPHA19), Proc. of Reactor Physics Asia Conference 2019 (RPHA19), RPHA19-1092, Dec. 2019.
• Takeshi Muramoto, Jun Nishiyama, Toru Obara. Development of Criticality Safety Evaluation Method Based on the Actual Dynamic Behavior of the Fuel Debris in Water, Reactor Physics Asia Conference 2019 (RPHA19), Proc. of Reactor Physics Asia Conference 2019 (RPHA19), RPHA19-1091, Dec. 2019.
• Hoang Hai Nguyen, Jun Nishiyama, Toru Obara. Monte Carlo Based Analysis for CANDLE Burning Reactor, Reactor Physics Asia Conference 2019 (RPHA19), Proc. of Reactor Physics Asia Conference 2019 (RPHA19), RPHA19-1088, Dec. 2019.
• Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Thermal Hydraulic Analysis for a Breed and Burn Core with Spiral Fuel Shuffling, Reactor Physics Asia Conference 2019 (RPHA19), Proc. of Reactor Physics Asia Conference 2019 (RPHA19), RPHA19-1087, Dec. 2019.
• Hiroki Takezawa, Delgersaikhan Tuya, Toru Obara. Development of Integral Kinetic Model with Delayed Neutrons Effect for Criticality Accident Analysis of Fukushima Daiichi NPP Fuel Debris, Reactor Physics Asia Conference 2019 (RPHA19), Proc. of Reactor Physics Asia Conference 2019 (RPHA19), RPHA19-1085, Dec. 2019.
• Kodai Fukuda, Delgersaikhan Tuya, Jun Nishiyama, Toru Obara. Supercritical kinetic analysis in a simple fuel debris system by MIK code, ICNC2019 – 11th International Conference on Nuclear Criticality Safety, Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety, A93242KF, Sept. 2019.
• Takeshi Muramoto, Jun Nishiyama, Toru Obara. Numerical analysis of criticality of fuel debris falling in water by coupling computational fluid dynamics and the continuous energy Monte Carlo code, ICNC2019 – 11th International Conference on Nuclear Criticality Safety, Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety, A93049MT, Sept. 2019.
• Toru Obara, Delgersaikhan Tuya. Development of super critical transient MIK code and its application to GODIVA core, ICNC2019 – 11th International Conference on Nuclear Criticality Safety, Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety, A93237TO, Sept. 2019.
• Van Khanh Hoang, Jun Nishiyama, Toru Obara. Core Design Improvement of Small CANDLE Reactor with the Melt-Refining Process, American Nuclear Society 2018 Winter Meeting, Transactions of the American Nuclear Society, Vol. 119, pp. 1079-1082, Nov. 2018.
• Van Khanh Hoang, Jun Nishiyama, Toru Obara. Effect of Compensating for Fuel Losses in Melt and Refining Process for Small CANDLE Reactor, American Nuclear Society 2017 Winter Meeting, Transactions of the American Nuclear Society, Vol. 117, pp. 1487-1488, Oct. 2017.
• Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Feasibility of Bruning Wave Reactor with Continuous Fuel Movement, American Nuclear Society 2017 Winter Meeting, Transactions of the American Nuclear Society, Vol. 117, pp. 1101-1104, Oct. 2017.
• Toru Obara, Delgersaikhan Tuya. Supercritical Kinetic Analysis of Accumulated Fuel Debirs in the Fukushima-Daiichi NPS, American Nuclear Society 2017 Winter Meeting, Transactions of the American Nuclear Society, Vol. 117, pp. 851-852, Oct. 2017.
• Hiroki Osato, Jun Nishiyama, Toru Obara. Initial Core Design of CANDLE Bruning Fast Reactor Using Plutonium from LWR Spent Fuel, American Nuclear Society 2017 Winter Meeting, Transactions of the American Nuclear Society, Vol. 117, pp. 1485-1486, Oct. 2017.
• Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Preliminary Study of Burning Wave Reactor with Continuous Fuel Movement, Reactor Physics Asia 2017 (RPHA17) Conference, Proc. of the Reactor Physics Asia 2017 (RPHA17) Conference, Aug. 2017.
• Toru Obara, Kazuki Kuwagaki, Jun Nishiyama. Feasibility of Burning Wave Fast Reactor Concept with Rotational Fuel Shuffling, International Conference of Fast Reactors and Related Fuel Cycles: Next Generation Nculear Systems for Sustainable Development (FR17), Proceedings of International Conference of Fast Reactors and Related Fuel Cycles: Next Generation Nculear Systems for Sustainable Development (FR17), IAEA-CN245-051, June 2017.
• Van Khanh Hoang, Jun Nishiyama, Toru Obara. Effect of homogenization of breeding zone in small CANDLE burning reactor with melt and refining process, 2017 International Congress on Advances in Nuclear Power Plants (ICAPP2017), Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP2017), 17696, Apr. 2017.
• Toru Obara, Van Khanh Hoang, Jun Nishiyama. Concept of small CANDLE reactor with melt and refining process, 2017 International Congress on Advances in Nuclear Power Plants (ICAPP2017), Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP2017), 17739, Apr. 2017.
• Hiroki Osato, Jun Nishiyama, Toru Obara. Study on CANDLE Burning Reactor with Initial Core Using Plutonium from LWR Spent Fuel, The fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), Abstracts of the fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), A11-2, Oct. 2016.
• Odmaa Sambuu, Enkhbaatar Ganbold, Jamyansuren Terbish, Toru Obara, Norov Nanzad, Munkhbat Byambajav. Design Parameters in an Annular, Prismatic HTGR for Passive Decay Heat Removal, The fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), Abstracts of the fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), A21-3, Oct. 2016.
• Irwan Liapto Simanullang, Toru Obara. Utilization of Burnable Poison Particles in UO2 and ROX Fuels in Pebble Bed Reactor with Accumulative Fuel Loading Scheme, The fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), Abstracts of the fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), A21-1, Oct. 2016.
• Toru Obara, Kazuki Kuwagaki, Jun Nishiyama. Concept of Burning Wave Reactor with Rotational Fuel Shuffling, The fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), Abstracts of the fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), A13-5, Oct. 2016.
• Van Khanh Hoang, Toru Obara. Impact of Neutron Spectrum Shift on Breed and Burn Reactor Concept, The fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), Abstracts of the fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), A12-5, Oct. 2016.
• Jun Nishiyama, Masato Tanaka, Toru Obara. Study on Optimization of Early Stage CANDLE Burnup Characteristics, The fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), Abstracts of the fifth International Symposiuim on Innovative Nuclear Energy Systems (INES-5), A11-4, Oct. 2016.
• Obara T., Abdul Karim J., Hoang V. K., Nishiyama J.. CANDLE BURNING FAST REACTOR CONCEPT WITH MELT AND REFINING PROCESS, Intenational Scientific and Technical Conference, Innovative Designs and Techologies of Nuclear Power IV (IV ISTC NIKIET-2016), Book of abstracts of Intenational Scientific and Technical Conference, Innovative Designs and Techologies of Nuclear Power IV (IV ISTC NIKIET-2016), pp. 75-76, Sept. 2016.
• Hai Quan Ho, Toru Obara. Composition of ROX Fuel for High-Burnup Pebble Bed Reactor, American Nuclear Society 2015 Winter Meeting, Transactions of the American Nuclear Society, Vol. 113, pp. 922-923, Nov. 2015.
• Delgersaikhan Tuya, Toru Obara, Hiroki Takezawa. Kinetic Analysis of Weakly Coupled Fuel Debris by Integral Kinetic Model, American Nuclear Society 2015 Winter Meeting, Transactions of the American Nuclear Society, Vol. 113, pp. 1158-1160, Nov. 2015.
• Toru Obara, Delgersaikhan Tuya, Hiroki Takezawa. Fission Probability Density Functions for Kinetic Analysis in Weakly Coupled Fuel Debris, American Nuclear Society 2015 Winter Meeting, Transactions of the American Nuclear Society, Vol. 113, pp. 1150-1152, Nov. 2015.
• Julia Abdul Karim, Jun Nishiyama, Toru Obara. Application of the Melt and Refining Procedure to the CANDLE Reactor Concept, American Nuclear Society 2015 Winter Meeting, Transactions of the American Nuclear Society, Vol. 113, pp. 924-926, Nov. 2015.
• Irwan Liapto Simanullang, Toru Obara. Burnup Analysis of Accumulative Fuel Loading Scheme Pebble Bed Reactor with Optimum Fuel Composition, American Nuclear Society 2015 Winter Meeting, Transactions of the American Nuclear Society, Vol. 113, pp. 919-921, Nov. 2015.
• Toru Obara, Hiroki Takezawa, Delgersaikhan Tuya. PROMPT SUPERCRITICAL KINETIC ANALYSIS WITH NEUTRON COUPLING BETWEEN FUEL DEBRIS, International Conference on Nuclear Criticality Safety (ICNC2015), Proceedings of International Conference on Nuclear Criticality Safety (ICNC2015), American Nuclear Society, pp. 1431-1438, Sept. 2015.
• Toru Obara, Dwi Irwanto, Tomonori Nakashima, Taiki Onoe, Piyatida Trinuruk, Topan Setiadipura, Sambuu Odmaa, Hai Quan Ho, Irwan Liapto Simanullang. Design Concept Study for Innovative High Temperature Gas-Cooled Reactors, Reactor Physics Asia 2015 (RPHA15), Proceedings of the Reactor Physics Asia 2015 (RPHA15) Conference, 12DAIR2-1, Sept. 2015.
• Odmaa Sambuu, Toru OBARA. CORE TEMPERATURE COEFFICIENT OF SMALL LONG-LIFE HTGR FOR PASSIVE DECAY-HEAT REMOVAL, ICONE-23, 23th International Conference on Nuclear Engineering, Proceedings of ICONE-23, ICONE23-1625, May 2015.
• Hai Quan Ho, Toru Obara. IMPACT ON BURNUP PERFORMANCE OF COATED PARTICLE FUEL DESIGN IN PEBBLE BED REACTOR WITH ROX FUEL, ICONE-23, 23th International Conference on Nuclear Engineering, Proceedings of ICONE-23, ICONE23-1651, May 2015.
• Irwan Liapt Simanullang, Toru Obara. IMPROVEMENT OF BURNUP ANALYSIS FOR PEBBLE BED REACTORS WITH ANACCUMULATIVE FUEL LOADING SCHEME, ICONE-23, 23th International Conference on Nuclear Engineering, Proceedings of ICONE-23, ICONE23-1627, May 2015.
• Delgersaikhan Tuya, Haruka Kikuchi, Toru OBARA. Application of Integral Kinetic Model to Transient Analysis of Different Types of Weakly Coupled Systems, ICONE-23, 23th International Conference on Nuclear Engineering, Proceedings of ICONE-23, ICONE23-1626, May 2015.
• Toru OBARA, Delgersaikhan Tuya, Haruka Kikuchi. Fission Probability Density Functions for Super Prompt Criticality Accident Analysis in Weakly Coupled Systems by Integral Kinetic Model, ICONE-23, 23th International Conference on Nuclear Engineering, Proceedings of ICONE-23, ICONE23-1618, May 2015.
• Odmaa Sambuu, Toru OBARA. Systematic Study of a Small, Long-life HTGR Design for Passive Decay-Heat Removal, 2014 American Nuclear Soceity Winter Meeting, Transactions of the American Nuclear Society, American Nuclear Society, Vol. 111, pp. 1359-1362, Nov. 2014.
• Haruka Kikuchi, Toru OBARA. Transient Analysis in Super Critical Condition for Several Fuel-Solution Tanks System with Different Layout, PHYSOR 2014, Proc. of PHYSOR 2014, on CD-ROM, Sept. 2014.
• Odmaa Sambuu, Toru OBARA. Suppression of Excess Reactivity of Small Long-Life Prismatic HTGR with Passive Decay-Heat Removal, PHYSOR 2014, Proc. of PHYSOR 2014, on CD-ROM, Sept. 2014.
• Odmaa Sambuu, Toru OBARA. Comparative study on HTGR Designs for Passive Decay Heat Removal, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), A22-4, Nov. 2013.
• Toru Obara, Yosuke Isobe. Population inversion distribution in laser gas medium in Reactor Pumped Laser, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), A13-6, Nov. 2013.
• Toru OBARA, Haruka Kikuchi. Energy Release in Criticality Accidents Involving Two Fuel Solution Tanks, American Nuclear Society 2013 Winter Meeting, Transactions of the American Nuclear Society, Vol. 109, pp. 888-889, Nov. 2013.
• Jun Nishiyama, Toru Obara. Start-up analysis of the CANDLE burn-up reactors by using accelerator neutron sources, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), A13-3, Nov. 2013.
• Topan Setiadipura, Toru OBARA. Development of a Monte Carlo based PBR Fuel Management Code, Americal Nuclear Society 2013 Winter Meeting, Transactions of the American Nuclear Society, Vol. 109, pp. 1431-1433, Nov. 2013.
• Piyatida Trinuruk, Toru OBARA. Particle-type Burnable Poisons for Thorium-based Fuel in HTGR, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), A22-3, Nov. 2013.
• Haruka Kikuchi, Toru OBARA. Development of Transient Analysis Code for Estimation of Total Released Energy in Several Fuel Solution Tanks System, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), C13-1, Nov. 2013.
• Topan Setiadipura, Toru OBARA. Optimization of Start-Up Fuel Management for OTTO Cycle Pebble Bed Reactor, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), A22-5, Nov. 2013.
• Ohta, H., Ogata, T., Obara, T.. High-burnup core design using minor actinide-containing metal fuel, International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads, Proc. of International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads,, Vol. 1, pp. 759-765, 2013.
• Toru OBARA, Taiki Onoe. Effect of Particle Type Burnable Poisons in HTGR, Transactions of the American Nuclear Society, Vol. 107, pp. 1023-1024, Nov. 2012.
• Piyatida Trinuruk, Toru OBARA. Effect of SiC Coating over Graphite Stracture in HTGR, Transactions of the American Nuclear Society, Vol. 107, pp. 1262-1263, Nov. 2012.
• Toru OBARA, Dwi Irwanto. Burnup Performance of Small Pebble Bed Reactor with Accumlative Fuel Loading Scheme, 6th International Topical Meeting on High Temperature Reactor Technology HTR2012, Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology HTR2012, HTR2012-5-019, Oct. 2012.
• Byambajav Munkhbat, Toru OBARA. Conceptual design of a small nuclear reactor for NTD-Si using short PWR fuel assemblies, Transactions of the American Nuclear Society, Vol. 106, pp. 826-829, June 2012.
• Toru OBARA, Hiroki Takezawa. Possibility of nuclear pumped laser experiment using low enriched uranium, The 3rd Internetional Conference on Advances in Nuclear Science and Engineering 2011 ICANSE2011, AIP Conference Proceedings Volume 1448, The 3rd Internetional Conference on Advances in Nuclear Science and Engineering 2011 ICANSE2011, pp. 25-29, 2012.
• Piyatida Trinuruk, Toru Obara. Preliminary Study on the Burnup Improvement of HTGR based on the Spectrum, GLOBAL 2011, Proc. of GLOBAL 2011, 500728, Dec. 2011.
• Byambajav Munkhbat, Toru Obara. Conceptional Design of a Small Nuclear Reactor for Large-Diameter NTD-Si Using a PWR Fuel, Transactions of the American Nuclear Society, Vol. 105, pp. 1123-1124, Nov. 2011.
• Odmaa Sambuu, Toru Obara. Design Concept of Small District Heating Reactor for Mongolia, Transactions of the American Nuclear Societ, Vol. 105, pp. 1160-1161, Nov. 2011.
• Dwi Irwanto, Toru Obara. Burnup Characteristics of Thorium Fuel in a Small PBR with Pea-a-Peu Feul-Loading Scheme, Transactions of the American Nuclear Society, Vol. 105, pp. 1105-1106, Nov. 2011.
• Piyatida Trinuruk, Toru Obara. Spectrum Shift with Silicon Carbide Block in HTGR, Transactions of the American Nuclear Society, Vol. 105, pp. 1103-1104, Nov. 2011.
• Haruka Kikuchi, Toru Obara. Supercritical Transinet Analysis in Weakly Coupling Systems, Transactions of the American Nuclear Society, Vol. 105, pp. 535-536, 2011.
• Toru Obara, Dwi Irwanto. Reduction of Spent Fuel by Optimization of Fuel Composition in Simplified Pebble Bed Reactor, Technical Meeting On Fuel and Fuel Cycle for Small and Medium Range Reactors, 2011.
• Minoru Takahashi, Toru Obara, Hiroshi Sekimoto. Design Concepts of LFRs and Related Studies in CRINES of Tokyo Tech., GLOBAL2011, 2011.
• Toru Obara, Odmaa Sambuu. Preliminary study of small district heating reactor with passive safety feature, ICANSE-2011: International Conference on Advances in Nuclear Science and Engineering 2011, Book of abstracts: ICANSE-2011, 2011.
• Dwi IRWANTO, Toru OBARA, Yukitaka KATO, Ichiro YAMANAKA. 2-dimensional Core Temperature Profile During Opration in Th Small Simplified Pebble Bed Reactor with Peu a Peu Fuel Loading, The Third International Symposium on Innovative Nuclear Energy Systems, INES-3 Book of Abstracts, P-113, Oct. 2010.
• Munkhbat BYAMBAJAV, Toru Obara. Design Concept of Small Reactor for Larger Diameter neutron Transmutation Doping using Conventional PWR Fuel Assemblies, The Third International Symposium on Innovative Nuclear Energy Systems, INES-3 Book of Abstracts, P-108, Oct. 2010.
• Toru Obara, Yu Yamazawa. Decontamination Efficency of Metal Mesh Plonium Filter for Lead Alloy Cooled Reactor, The Third International Symposium on Innovative Nuclear Energy Systems, INES-3 Book of Abstracts, 1B-34, Oct. 2010.
• Dwi Irwanto, Toru Obara. Burnup Anlysis of a Peu a Peu Feul-loading Scheme in a Pebble Bed Reactor Using the Monte Carlo Method, Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010(SNA+MC2010), Proc. of Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010(SNA+MC2010), 10190, Oct. 2010.
• Toru OBARA, Hiroki TAKEZAWA. Kinetic Analysis of Weakly Coupled Systems Using Probability Density Function of Coupleing Coefficient Obtained by Monte Carlo Method, Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010(SNA+MC2010),, Proc. of Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010(SNA+MC2010), 10258, Oct. 2010.
• Dwi Irwanto, Yukikata Kato, Ichiro Yamanaka, Toru Obara. Preliminary Study of Burnup Characteristics for a Simplified Small Pebble Bed Reactor, The 2’nd International Conference on Advances in Nuclear Science and Engineering 2009-ICANSE2009, Proc. of The 2’nd International Conference on Advances in Nuclear Science and Engineering 2009-ICANSE200, pp. 27-30, 2010.
• Toru Obara, Liem Peng Hong. Small Reactor For Semiconductor Production By Neutron Transmutation Doping, The 2’nd International Conference on Advances in Nuclear Science and Engineering 2009-ICANSE2009, The 2’nd International Conference on Advances in Nuclear Science and Engineering 2009-ICANSE200, American Institute of Physics, pp. 15-18, 2010.
• Dwi IRWANTO, Toru OBARA, Yukitaka KATO, Ichiro YAMANAKA. Burnup Characteristics of Peu-a-Peu Fuel Loading Scheme in Small PBR, Transactions of the American Nuclear Society, Vol. 103, p. 791, 2010.
• Byambajav Munkhbat, Toru Obara. Desing Stury on Nuclear Reactor for Large Diameter NTD Using PWR Fuel, Transactions of the American Nuclear Society, Vol. 103, p. 756, 2010.
• Toru Obara, Hiroki Takezawa. Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment, Transactions of the American Nuclear Society, Vol. 103, p. 775, 2010.
• Toru Obara, Liem Peng Hong, Hideki Yagi. Concept of Small Reactor for Neutron Transmutation Doping using PWR Type Fuel Elements, 2009 International Congress on Advances in Nuclear Power Plants (ICAPP’09), Proc. of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP’09), paper 9093, 2009.
• Toru Obara, Junichiro Otani. Fundamental Analysis of Graphite Moderated Reactor for Laser Propulsion by Nuclear-Pumped Laser, 14th Intenational Conference on Emerging Nuclear Energy Systems (ICENES-2009), ICENES-2009 : Book of abstracts, 2009.
• Dwi IRWANTO, Toru OBARA, Go CHIBA. Benchmarking of Effective Delayed Neutron Fraction with Deterministic Method, 2008 Symposium on Nuclear Data, Book of abstracts : 2008 Symposium on Nuclear Data, Nov. 2008.
• T. Obara, M. Ogawa. Present situation of unused uranium fuel in Tokyo Institute of Technology, Return of Research Reactor Spent Fuel ot he Country of Origin: Requirements for Technical and Administrative Preparations and national Experiences, IAEA-TECDOC-1953, 2008.
• Hiroki Takezawa, Toru Obara. Transient Parameters of the Integral Kinetic Model for Weakly Coupled Systems, Transactions of the American Nuclear Society, Vol. 99, p. 762, 2008.
• Toru Obara, Liem Peng Hong, Naoyuki Takaki. Basic Concept of Water Moderated Small Reactor for Neutron Transmutaion Doping, Transactions of the American Nuclear Society, Vol. 99, p. 745, 2008.
• Hiroki Takezawa, Toru Obara. Neutronic Analysis on a Low Enriched Uranium Coupled Reactor Consisting of Pulse Cores and a Laser Moudule, Joint International Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C+SNA2007), Proc. of Joint International Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C+SNA2007), American Nuclear Society, on CD-ROM, Apr. 2007.
• Md. Quamrul Huda, Shafiqul I. Bhuiyan, Toru Obara. Engineering Analysis of the TRIGA Research Reactor using Monte Carlo Technique, The 15th International Conference on Nuclear Engineering (ICONE-15), Proc. of The 15th International Conference on Nuclear Engineering (ICONE-15), ICONE 15-10449, Apr. 2007.
• Toru Obara, Terumitsu Miura, Takeru Koga, Hiroshi Sekimoto. Fundamental Study on Polonium Measure in Lead-Bismuth Eutectic Cooled Reactors, Seventeenth National Symposium on Radiation Physics (NSRP-17), Proc. of Seventeenth National Symposium on Radiation Physics (NSRP-17), on CD-ROM, 2007.
• Toru Obara, Takeru Koga, Terumitsu Miura, Hiroshi Sekimoto. Preliminary Study on Polonium Filter for Lead Alloy Cooled Reactors, Transactions of the American Nuclear Society, Vol. 94, p. 762, 2006.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Poloinium Contamination Removal Experiment For Lead-Bismuth Cooled Fast Reactor, 2005 International Congress on Advances in Nuclear Power Plants (ICAPP’05), Proc. of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP’05), Seoul, KOREA, May 15-19, 2005, Vol. 5088, May 2005.
• Toru Obara, Terumitsu Miura, Toshiro Ohsaki, Masayuki Igashira, Toyohiko Yano, Hiroshi Sekimoto. Development of Measure for Polonium Contamination in Pb-Bi Cooled Direct Contact Water FBR (PBWFR), 2005 International Congress on Advances in Nuclear Power Plants (ICAPP’05), Proc. of 2005 International Congress on Advances in Nuclear Power Plants (ICAPP’05), Seoul, KOREA, May 15-19, 2005, pp. 5089, May 2005.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Chemical Form of Polonium in Lead-Bismuth Eutectic, Transactions of the American Nuclear Society, Vol. 93, pp. 345-346, 2005.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Polonium Release Experiment in Direct Contact of Lead-Bismuth Eutectic with Water, Trans. American Nuclear Society, Transactions of the American Nuclear Society, Vol. 92, pp. 142-143, 2005.
• Minoru Takahashi, Toru Obara, Tatusro Iguchi, Akira Otsubo, Masatoshi Kondo, Y. Qi, Megumi Matsumoto, E. Yusibani, Toyou Akashi, A. Yamada, H. Nei, K. Hata, K. Hara. Design and Experimental Study for Development of Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR),, 2004 international congress on advances in nuclear power plants, Proceedings of ICAPP'04 (CD-ROM), May 2004.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Characteristics of Polonium Contamination from Neutron Irradiated Lead-Bismuth Eutectic, 12th International Conference on Nuclear Engineering, Proc. of 12th International Conference on Nuclear Engineering, ICONE12-49153, 2004.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Polonium Distribution Anaysis by Alpha-Ray Spectrum Unfoldeing Method, Transactions of the American Nuclear Societ, Vol. 90, pp. 354-355, 2004.
• M. Takahashi, T. Obara, T. Iguchi, A .Otsubo, M.Kondo, Y. Qi, M. Matsumoto, E.Yusibani, T. Akashi, A. Yamada, H.Nei, K. Hata, K.Hara, S. Uchida, H. Osada, Y. Kasahara, K. M atsuzawa, N. Sawa, Y.Yamada, K. Kurome, Y. Okubo. Design and Experimental Study for Development of Pb -Bi Cooled Direct Contact Boiling Water Small Fast Reactor (PBWFR), 2004 International Congress on Advances in Nuclear Power Plants (ICAPP’04), Proc. of 2004 International Congress on Advances in Nuclear Power Plants (ICAPP’04, pp. 599-609, 2004.
• Toru Obara, Terumitsu Miura, Hiroshi Sekimoto. Polonium Contamination Removal from Stainless Steel by Baking Method, Transactions of the American Nuclear Society, Vol. 91, pp. 483-484, 2004.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Removal of Polonium Contamination by Lead-Bismuth Eutectic in Nuclear Systems, 11th International Conference on Nuclear Engineering, Proc. of 11th International Conference on Nuclear Engineering, ICONE11-36045, 2003.
• Toru Obara, Terumitsu Mirura, Yoshiyuki Fujita, Hiroshi Sekimoto. Removing Effect of Polonium Contamination by LBE in Various Baking Conditions, Transactions of the American Nuclear Society, Vol. 87, p. 539, 2002.
• Minoru Takahashi, Masayuki Igashira, Toru Obara, Hiroshi Sekimoto, Kenji Kikuchi, Kazumi Aoto, Teruaki Kitano. Studies on Materials for Heavy-Liquid-Metal-Cooled Reactors in Japan, 10th International Conference on Nuclear Engineering, Proc. of ICONE10: Tenth International Conference on Nuclear Engineering,April 14-18, 2002 Arlington, Virginia, USA, ICONE10-22166, 2002.
• Toru Obara, Yoshiyuki Fujita, Yasuo Ando, Hiroshi Sekimoto. Removal of Polonium Contamination on Quartz Glass by Baking, Transactions of the American Nuclear Society, Vol. 85, p. 49, 2001.
• V.B. Polevoy, T. Obara. On the accuracy of calculations of the reactors with U-C fuel using the 26-group ABBN neutron data library, NEUTRONICS-99, Proc. of NEUTRONICS-99, 1999.
• O.B. Tarasova, T. Obara. Calculation of the naked Pu-solution assemblies criticality with different codes and data libraries, NEUTRONICS-99, Proc. of NEUTRONICS-99, 1999.
• Toru OBARA. Advantage of a Fast Driver Core Using Coated Fuel Particles for an In-Pile Experimental Reactor, Proc. of an ENS Class 1 Topical Meeting, Resaerch Facilities for the Future of Nuclear Energy, pp. 281-286, 1996.
• Toru OBARA, Hiroshi SEKIMOTO. Concept of a Fast Driver Core Using Coated Fuel Particles for an In-Pile Experimental Reactor, Proc. of the International Conference on the Physics of Reactors, PHYSOR96, D-86, 1996.
• Hiroshi Sekimoto, Shuichiroh Hoshi, Toru Obara. Conceptual Design Study on Pulse Reactors Using Coated Fuel Particles, Proc. of the Topical Meeting on Physics, Safety, and Applications of Pulse Reactors, pp. 281-283, 1994.
• Toru OBARA, Hiroshi SEKIMOTO. Zero Temperature Coefficient Thermal Core with Diluted Fuel, Transactions of the American Nuclear Society, Vol. 71, pp. 495-496, 1994.
• Toru OBARA, Hiroshi SEKIMOTO. Possibility of a Pulse Reactor for Reactivity Feedback Experiment, Proc. of the Topical Meeting on Physics, Safety, and Applications of Pulse Reactors, pp. 284-291, 1994.
• Toru OBARA, Hiroshi SEKIMOTO. Possibility of Test Reactor for Reactivity Feedback Effects in Core Damage Accident in FBR Core, Proc. of the International Topical Meeting on Advanced Reactors Safety (ARS'94), pp. 49-57, 1994.

国内会議発表 (査読有り)

• Toru Obara, Jun Nishiyama, Hiroki Osato. CANDLE Burning Reactor with Plutonium Fuel Start-up Core, American Nuclear Society 2016 Winter Meeting, Transactions of the American Nuclear Society, Vol. 115, pp. 1319-1320, Nov. 2016.
• 小原徹, 三浦照光, 藤田佳之, 関本博. 鉛ビスマス合金から発生したポロニウムによる表面汚染のベーキングによる除去, 日本機会学会2002年度年次大会講演論文集, p. 1332, 2002.

国際会議発表 (査読なし・不明)

• Alemberti A., Tucek K., Obara T., Masatoshi KONDO, Moiseev A., Simith C., Wu Y., Hwang IllSoon. [Plenary presentation] THE GENERATION-IV LEAD FAST REACTOR ACTIVITIES, Innovative designs and technologies of nuclear power of nuclear power, V International Scientific and Technical Conference, Collection of papers, JSC NIKIET, pp. 1580-1587, Oct. 2018.  公式リンク  
  
• Masatoshi Kondo, Toru Obara. [Pleanary presentation] Status of JAPAN LFR activities, GLANST 2017 (Global Symposium on Lead and Lead Alloy based Nuclear Energy Science and Technology), Proceedings of GLANST-2017, Seoul national university, pp. 39-50, Sept. 2017.  公式リンク  
  
• Toru OBARA. New Approach of Space-dependent Kinetic Analysis, The Reactor Physics Asia 2017 Conference (RPHA17), Booklet of Reactor Physics Asia 2017 (RPHA17), Aug. 2017.
• Minoru TAKAHASHI, Toru OBARA, Akio MINATO, Shoji UCHIDA, Kenji KIKUCHI, Masatoshi KONDO, Akito NAGATA. Activities in CRINES for Generation IV International Forum, Lead-cooled Fast Reactor, The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4), A11-3, Nov. 2013.
• Toru OBARA, Hiroyuki Nakamura, Jun Nishiyama. Preliminary Study for Refueling Scheme in Lead-Bismuth Eutectic Cooled CANDLE Reactor, The forth conference on Heavy Liquid-metal Coolants in Nuclear Technologies (HLMC-2013), The book of abstract in HLMC-2013, Sept. 2013.
• Toru OBARA. Concept of Small Pebble Bed Reactor with Accumulative Fuel Loading Scheme, Third International Ulaanbaatar Conference on Nuclear Physics and Applications UBC2012, Third International Ulaanbaatar Conference on Nuclear Physics and Applications UBC2012, Sept. 2012.
• Toru OBARA. Development of Nucear Reactor, The First International Forum on Multidisciplinary Education and Research for Energy Science, Dec. 2008.
• Toru Obara, Termitsu Miura, Takeru Koga, Hiroshi Sekimoto. Fundamental Study for Polonium Issue in Lead-Bismuth Cooled Reactors, The Third Conference on Heavy Liquid-Metal Coolants in Nuclear Technologies (HLMC-2008), Proc. of The Third Conference on Heavy Liquid-Metal Coolants in Nuclear Technologies (HLMC-2008), Vol. 2, pp. 467-471, 2008.
• Toru Obara, Yu Yamazawa, Takeru Koga, Terumitsu Miura, Hiroshi Sekimoto, Toshinobu Sasa. Polonium Research of LBE Coolant Technology, 2nd MIT- Tokyo Tech Symposium on Innovative Nuclear Energy System (TM-INES2), Abstracts and Presentation materials CD of 2nd MIT- Tokyo Tech Symposium on Innovative Nuclear Energy System (TM-INES2), July 2007.
• Toru Obara, Hiroki Takezawa. Neutronic Analysis of Pulse Core and Laser Module Coupled System for Nuclear Pumped Laser, KNS/AESJ Joint Session on Reactor Physics and Nuclear Data, Transactions of the Korean Nuclear Society Spring Meeting, CD-ROM, May 2007.
• Toru Obara, Hiroki Takezawa. Concept of Low Enriched Uranium Coupled Reactor for Nuclear Pumped Laser, IV Internarional Conference “Physics of Nuclear-Pumped Lasers and Pulsed Nuclear Reactors", Book of Abstracts : IV Internarional Conference “Physics of Nuclear-Pumped Lasers and Pulsed Nuclear Reactors", 2007.
• Hiroki Takezawa, Toru Obara. Transient Analysis of a Low Enriched Uranium Coupled Reactor for Nuclear-Pumped Laser, IV Internarional Conference “Physics of Nuclear-Pumped Lasers and Pulsed Nuclear Reactors", Book of Abstracts : IV Internarional Conference “Physics of Nuclear-Pumped Lasers and Pulsed Nuclear Reactors", 2007.
• Toru Obara, Terumitsu Miura, Takeru Koga, Hiroshi Sekimoto. Recent results of Polonium Research for Pb-Bi Cooled Reactors, MIT- Tokyo Tech Symposium on Innovative Nuclear Energy System, 2-4 November, 2005, Massachusetts Institute of Technology, Royal Sonesta Hotel, Cambridge, Massachusetts 02139 USA (2005), MIT- Tokyo Tech Symposium on Innovative Nuclear Energy System, 2-4 November, 2005, Massachusetts Institute of Technology, Royal Sonesta Hotel, Cambridge, Massachusetts 02139 USA (2005), CD-ROM, Nov. 2005.
• Toru Obara, Terumitsu Miura, Masayuki Igashira, Toshiro Ohsaki, Hiroshi Sekimoto. Development of Polonium Contamination Measure in Pb-Bi Cooled Reactors, The 9-th International Conference “Nuclear Power Safety and Nuclear Education”, October 24-27, 2005, p.125, Obninsk, Russia, The 9-th International Conference “Nuclear Power Safety and Nuclear Education”, October 24-27, 2005, p.125, Obninsk, Russia, (2005), pp. 125, Oct. 2005.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Investigation for removal of polonium contamination by baking method, Book of presentations : Tokyo Tech COE-INES - Indonesia International Symposium 2005 “Prospect of Nuclear Energy in Indonesia”, March 2-4, 2005, Grand Aquila Hotel, Bandung, Indonesia (2005), pp. 27, Mar. 2005.
• Toru Obara, Terumitsu Miura, Masayuki Igashira, Hiroshi Sekimoto. Development of Measure for Polonium Contamination in Lead-Bismuth Eutectic Cooled Reactors, Tokyo Tech COE-INES - Indonesia International Symposium 2005 “Prospect of Nuclear Energy in Indonesia”, March 2-4, 2005, Grand Aquila Hotel, Bandung, Indonesia (2005)., Book of presentations : Tokyo Tech COE-INES - Indonesia International Symposium 2005 “Prospect of Nuclear Energy in Indonesia”, March 2-4, 2005, Grand Aquila Hotel, Bandung, Indonesia (2005)., pp. 19, Mar. 2005.
• Terumitsu Miura, Toru Obara, Sekimoto Hiroshi. Plonium Contamination Removal by formation of H2Po, The 9-th International Conference “Nuclear Power Safety and Nuclear Education”, The 9-th International Conference “Nuclear Power Safety and Nuclear Education”, October 24-27, 2005, Obninsk, Russia, pp. 133, 2005.
• Toru Obara. Experimental Course for graduate school students using nuclear facilities, The 1-st Workshop, Russia-Japan International Research Cooperation and Nuclear Education Toward Innovative Nuclear Energy System, Book of abstracts : The 1-st Workshop, Russia-Japan International Research Cooperation and Nuclear Education Toward Innovative Nuclear Energy System, 2005.
• T. Miura, T. Obara, H. Sekimoto. Polonium Measure for PBWFR (II) : Removal of Polonium Contamination on Stainless Steel –, COE-INES International Workshop on Design and R&D of Pb-Bi Cooled Reactors, (INES-1-WS-PBFR), COE-INES International Workshop on Design and R&D of Pb-Bi Cooled Reactors, (INES-1-WS-PBFR), pp. INES-1-WS-PBFR-18, 2004.
• Toru Obara. Polonium Measure for PBWFR (I) - Outline of Study-, COE-INES International Workshop on Design and R&D of Pb-Bi Cooled Reactors, (INES-1-WS-PBFR, COE-INES International Workshop on Design and R&D of Pb-Bi Cooled Reactors, (INES-1-WS-PBFR), INES-1-WS-PBFR-17, 2004.
• T. Obara, T. Miura, H. Sekimoto. Removal of Polonium Surface Contamination from Irradiated Lead-Bismuth Eutectic by Baking Method, Heavy Liquid Metal Coolants in Nuclear Reactors (HLMC-2003), December 11-12, 2003, Obninsk, Russia (2003), Proc. of Heavy Liquid Metal Coolants in Nuclear Reactors (HLMC-2003), p. 2404, Dec. 2003.
• Toru OBARA. Utilization of Pulse Reactors, ISTC-TITech Japan Workshop on Nuclear Reactors Technologies in Russia/CIS, Proc. of the ISTC-TITech Japan Workshop on Nuclear Reactors Technologies in Russia/CIS, pp. 16-17, 2001.
• Toru OBARA, A.G. MOROZOV, V.V. KEVROLEV, V.V. KUZNETSOV, S.A. TRESCHALIN A.V. LUKIN, V.A. TEREKHIN, Yu.A. SOKOLOV, V.G. KRAVCHENKO. Benchmark Calculations for Critical Experiments at FKBN-M Facility with Uranium-Plutonium-Polyethylene Systems using JENDL-3.2 and MVP Monte-Carlo Code, Proc. of The 4th JAPAN-KOREA Seminar on Advanced Reactors, Bulletin of the Research Laboratoy for Nuclear Reactors, Special Issue, Vol. 3, pp. 62-67, 2000.

国内会議発表 (査読なし・不明)

• 黒﨑 健, 小崎 完, 若林源一郎, 小原 徹. 国際原子力人材育成イニシアティブ事業において見えてきた課題と対応 (5)原子力オープンキャンパス, 日本原子力学会2024年秋の大会, 日本原子力学会2024年秋の大会予稿集, 1L_PL05, Sept. 2024.
• 小原 徹, Odmaa Sambuu. ナトリウム冷却材を使用したシリサイド燃料 RFBB の燃焼特性, 日本原子力学会2024年秋の大会, 日本原子力学会2024年秋の大会予稿集, 1G10, Sept. 2024.
• 堀越 蓮, 小原 徹. 窒化物燃料鉛冷却RFBBの起動炉心特性, 日本原子力学会2024年春の年会, 日本原子力学会2024年春の年会予稿集, 3L13, Mar. 2024.
• 堀池尚輝, 小原 徹. 金属燃料ナトリウム冷却RFBBの起動炉心特性, 日本原子力学会2024年春の年会, 日本原子力学会2024年春の年会予稿集, 3L12, Mar. 2024.
• 竹澤宏樹, 小原 徹. 非接触測定法を用いた燃料デブリ臨界解析技術の高度化（６） 弱結合炉体系を用いた臨界影響解析手法の予備検証, 日本原子力学会2024年春の年会, 日本原子力学会2024年春の年会予稿集, 2L17, Mar. 2024.
• 真鍋 征也, 西山 潤, 原野 英樹, 小原 徹. 非接触測定法を用いた燃料デブリ臨界解析技術の高度化（５）アクティブ中性子法を用いた燃料デブリ臨界特性測定システムの性能試験, 日本原子力学会2024年春の年会, 日本原子力学会2024年春の年会予稿集, 2L16, Mar. 2024.
• 西山 潤, 真鍋 征也, 原野 英樹, 小原 徹. 非接触測定法を用いた燃料デブリ臨界解析技術の高度化（４）アクティブ中性子法を用いた燃料デブリ臨界特性測定システムによる臨界特性評価, 日本原子力学会2024年春の年会, 日本原子力学会2024年春の年会予稿集, 2L15, Mar. 2024.
• Xiaoqing Huang, Toru Obara. Feasibility of silicide fueled RFBB using lead coolant, 2024 annual meeting of Atomic Energy Society of Japan, Proc. of 2024 annual meeting of Atomic Energy Society of Japan, 3L11, Mar. 2024.
• Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara. Small sodium-cooled RFBB with nitride fuel and LBE Reflectors, 2023 autumn meeting of Atomic Energy Society of Japan, Proc. of 2023 autumn meeting of Atomic Energy Society of Japan, 1H14, Sept. 2023.
• Alexandru Catalin Stafie, Jun Nishiyama, Toru Obara. Feasibility of a small RFBB concept with lead coolant and nitride fuel, 2023 autumn meeting of Atomic Energy Society of Japan, Proc. of 2023 autumn meeting of Atomic Energy Society of Japan, 1H13, Sept. 2023.
• 福田 航大, 須山 賢也, 小原 徹. 静的傾斜が生じた場合の海洋浮体式 BWRの核熱的挙動, 日本原子力学会2023年秋の大会, 日本原子力学会2023年秋の大会予稿集, 1H16, Sept. 2023.
• Hiroki Takezawa, Toru Obara. Preliminary verification of criticality impact analysis code applicable to weakly coupled systems including fuel debris particles, The 7th International Forum on Fukushima Daiichi NPS Decommissioning, C03, Aug. 2023.
• 堀越 蓮, 西山 潤, 小原 徹. 回転型燃料シャッフリングブリードバーン高速炉の起動炉心, 日本原子力学会2023年春の年会, 日本原子力学会2023年春の年会予稿集, 2L05, Mar. 2023.
• 竹澤宏樹, 小原徹. 非接触測定法を用いた燃料デブリ臨界解析技術の高度化（３）燃料デブリ弱結合炉体系臨界影響解析手法の高度化, 日本原子力学会2023年春の年会, 日本原子力学会2023年春の年会予稿集, 3K05, Mar. 2023.
• 真鍋 征也, 西山 潤, 原野 英樹, 小原 徹. 非接触測定法を用いた燃料デブリ臨界解析技術の高度化（２）アクティブ中性子法を用いた燃料デブリ臨界特性測定システム開発のための基礎実験, 日本原子力学会2023年春の年会, 日本原子力学会2023年春の年会予稿集, 3K04, Mar. 2023.
• 西山 潤, 真鍋 征也, 原野 英樹, 小原 徹. 非接触測定法を用いた燃料デブリ臨界解析技術の高度化（１）アクティブ中性子法を用いた燃料デブリ臨界特性測定システムの基礎設計, 日本原子力学会2023年春の年会, 日本原子力学会2023年春の年会予稿集, 3K03, Mar. 2023.
• 三浦 拓也, 西山 潤, 小原 徹. 燃料デブリ水中落下時の臨界解析高速化, 日本原子力学会2023年春の年会, 日本原子力学会2023年春の年会予稿集, 3K07, Mar. 2023.
• Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara. Feasibility of rotational shuffling Breed-and-Burn fast reactor with nitride fuel and sodium coolant, 2022 autumn meeting of Atomic Energy Society of Japan, Proc. of 2022 autumn meeting of Atomic Energy Society of Japan, 2F11, Sept. 2022.
• Xucheng Zhao, Jun Nishiyama, Toru Obara. Burnup analysis of Rotational Fuel-shuffling Breed-and-Burn fast reactor with lead-bismuth coolant, 2022 autumn meeting of Atomic Energy Society of Japan, Proc. of 2022 autumn meeting of Atomic Energy Society of Japan, 2F12, Sept. 2022.
• 小原 徹, Odmaa Sambuu, Van Khanh Hoang, 西山 潤. 燃料被覆材デザインがブリードバーン高速炉の中性子バランスと被覆管照射損傷に与える効果, 日本原子力学会2022年秋の大会, 日本原子力学会2022年秋の大会予稿集, 2F10, Sept. 2022.
• 小原 徹. 組織横断的な原子力教育基盤の構築に向けて：国際原子力人材育成イニシアティブ事業の取り組み (3)国際グループ会議の活動, 日本原子力学会2022年春の年会, 日本原子力学会2022年春の年会予稿集, 1L_PL03, Mar. 2022.
• 小原徹, Van Khanh Hoang, Odmaa Sambuu, 西山潤. 回転型燃料シャッフリング鉛冷却ブリードバーン型高速炉の成立性, 日本原子力学会2022年春の年会, 日本原子力学会2022年春の年会予稿集, 1D06, Mar. 2022.
• 小原 徹, Van Khanh Hoang, Odmaa Sambuu, 西山 潤. Conceptual design of rotational fuel shuffling sodium cooled Breed-and-Burn fast reactor, 日本原子力学会2021年秋の大会, 日本原子力学会2021年秋の大会予稿集, 3K13, Sept. 2021.
• 文元 太郎, 村本 武司, 西山 潤, 小原 徹. MPS 法を用いた実機規模での燃料デブリ水中落下シミュレーションによる臨界安全解析, 日本原子力学会2021年春の年会, 日本原子力学会2021年春の年会予稿集, 2B04, Mar. 2021.
• 小原徹, 西山潤, 村本武司, 文元太郎, 竹澤宏樹, Anton D. Smirnov, Ekaterina V. Bogdanova, Pavel A. Pugachev, Ivan S. Saldikov, Mikhail Yu. Ternovykh, Georgy V. Tikhomirov. 日露共同研究による燃料デブリ臨界安全解析, 日本原子力学会2021年春の年会, 日本原子力学会2021年春の年会予稿集, 2B02, Mar. 2021.
• 福田航大, 村本 武司, 西山 潤, 小原 徹. 燃料デブリ水中落下時の即発超臨界過渡解析における中性子世代時間の影響, 日本原子力学会2021年春の年会, 日本原子力学会2021年春の年会予稿集, 2B05, Mar. 2021.
• Hoang Hai Nguyen, Jun Nishiyama, Toru Obara. Design concept of the sodium cooled small CANDLE burning reactor, 2020 Autumn meeting of Atomic Energy Society of Japan, Proc. of 2020 Autumn meeting of Atomic Energy Society of Japan, 1K09, Sept. 2020.
• 福田 航大, 西山 潤, 小原 徹. 空間依存動特性コードMIK を用いたランプ状の反応度印加による臨界事故解析の検討, 日本原子力学会2020年秋の大会, 日本原子力学会2020年秋の大会予稿集, 2H02, Sept. 2020.
• 村本 武司, 西山 潤, 小原 徹. 粒状燃料デブリ水中落下によるデブリベッド形成過程の臨界計算手法の開発 -最適化手法を取り入れた粒子法パラメータ較正による粒状燃料デブリ形状のモデル化の検討-, 日本原子力学会2020年秋の大会, 日本原子力学会2020年秋の大会予稿集, 2H01, Sept. 2020.
• Aronne Travaglia, Kazuki Kuwagaki, Jun Nishiyama, Toru Obara. Possibility of Sodium Cooled Breed and Burn Fast Reactor with Rotational Fuel, 2020 Annual meeting of Atomic Energy Society of Japan, Proc. of 2020 Annual meeting of Atomic Energy Society of Japan, 1H03, Mar. 2020.
• Sergei Ryzhov, Georgy Tikhomirov, Toru Obara. Minor actinides transmutation technology optimization methods, 2020 Annual meeting of Atomic Energy Society of Japan, Proc. of 2020 Annual meeting of Atomic Energy Society of Japan, 3H02, Mar. 2020.
• 桑垣 一紀, 西山 潤, 小原 徹. ブリードアンドバーン型高速炉の使用済燃料特性, 日本原子力学会2020年春の年会, 日本原子力学会2020年春の年会予稿集, 3H06, Mar. 2020.
• 福田 航大, 西山 潤, 小原 徹. 燃料デブリを対象とした即発超臨界過渡解析における放射線分解ガスの影響, 日本原子力学会2020年春の年会, 日本原子力学会2020年春の年会予稿集, 1I04, Mar. 2020.
• 村本 武司, 西山 潤, 小原 徹. DEM法を取り入れた粉体状燃料デブリの臨界安全評価, 日本原子力学会2020年春の年会, 日本原子力学会2020年春の年会予稿集, 1I02, Mar. 2020.
• Anton Smirnov, Ekaterina Bogdanova, Georgy Tikhomirov, Hiroki Takezawa, Jun Nishiyama, Toru Obara. Criticality calculations of fuel debris in various conditions during falling down, 2020 Annual meeting of Atomic Energy Society of Japan, Proc. of 2020 Annual meeting of Atomic Energy Society of Japan, 1I01, Mar. 2020.
• 小原徹. SMR開発における炉物理, 日本原子力学会2019秋の大会, 日本原子力学会2019秋の大会予稿集, 1J_PL01, Sept. 2019.
• Anton Smirnov, Pavel Pugachev, Vladislav Romanenko, Georgy Tikhomirov, Toru Obara. Solution of the neutronic fast reactor benchmark with Serpent-CriMR code system, 2019 annual meeting of Atomic Energy Society of Japan, Proc. of 2019 annual meeting of Atomic Energy Society of Japan, 1K16, Mar. 2019.
• 大里 洋輝, 西山 潤, 小原 徹. メルトリファイニング法のCANDLE 燃焼高速炉の移行過程への適用, 日本原子力学会2019春の大会, 日本原子力学会2019春の大会予稿集, 1K11, Mar. 2019.
• 斉藤 雪子, 西山 潤, 小原 徹. ブリードアンドバーン型高速炉における燃料および冷却材組成が燃焼特性に与える効果, 日本原子力学会2019春の大会, 日本原子力学会2019春の大会予稿集, 1K10, Mar. 2019.
• Van Khanh Hoang, Jun Nishiyama, Toru Obara. Compensation for Fuel Losses in The Melt-Refining Process in Small CANDLE Reactor, 2018 autumn meeting of Atomic Energy Society of Japan, Proc. of 2018 autumn meeting of Atomic Energy Society of Japan, 3L09, Sept. 2018.
• 福田航大, 小原徹, 西山潤. 水中燃料デブリ超臨界時の線量評価, 日本原子力学会2018春の年会, 日本原子力学会2018春の年会予稿集, 2F09, Mar. 2018.
• 村本武司, 西山潤, 小原徹. 燃料デブリの水中落下過程における臨界安全解析, 日本原子力学会2018春の年会, 日本原子力学会2018春の年会予稿集, 2F07, Mar. 2018.
• 桑垣一紀, 西山潤, 小原徹. スパイラル型燃料移動によるブリードバーン型原子炉の成立性, 日本原子力学会2018春の年会, 日本原子力学会2018春の年会予稿集, 3F03, Mar. 2018.
• Jun Nishiyama, Kazuki Kuwagaki, Toru OBARA. Feasibility of Breed and Burn reactor with spiral pattern fuel movement, 2017 fall meeting of Atomic Energy Society of Japan, Proc. of 2017 fall meeting of Atomic Energy Society of Japan, 3H17, Sept. 2017.
• Hoang Hai Nguyen, Jun Nishiyama, Toru Obara. Burnup analysis of CANDLE burning reactor by Monte Carlo based method, 2017 fall meeting of Atomic Energy Society of Japan, Proc. of 2017 fall meeting of Atomic Energy Society of Japan, 3H15, Sept. 2017.
• Irwan Liapto Simanullang, Toru Obara. Introduction of MOX and Pu-ROX fuels in PBR with accumulative fuel loading scheme, 2017 fall meeting of Atomic Energy Society of Japan, Proc. of 2017 fall meeting of Atomic Energy Society of Japan, 3H14, Sept. 2017.
• Delgersaikhan Tuya, Toru Obara. Supercritical transient analysis in hypothetical fuel debris by multi-region based on integral kinetic model, 2017 fall meeting of Atomic Energy Society of Japan, Proc. of 2017 fall meeting of Atomic Energy Society of Japan, 2G05, Sept. 2017.
• 桑垣一紀, 西山 潤, 小原 徹. 連続燃料移動によるブリードバーン型原子炉の成立性, 日本原子力学会2017年春の年会, 日本原子力学会2017年春の年会予稿集, 3F16, Mar. 2017.
• 大里 洋輝, 西山 潤, 小原 徹. 軽水炉プルトニウムを用いた CANDLE燃焼高速炉の初期炉心設計, 日本原子力学会2017年春の年会, 日本原子力学会2017年春の年会予稿集, 3F15, Mar. 2017.
• 佐藤勇, 小原徹, 矢野豊彦, 竹下健二, 加藤之貴, 赤塚洋, 木倉宏成, 塚原剛彦, 吉田克己, 遠藤玄, 鷹尾康一朗, 原田雅幸, 山崎宰春, 岩附信行, 鈴森康一, 浅沼徳子, 新井剛, 川嶋健嗣, 高木直行. 英知を結集した原子力科学技術・人材育成推進事業 廃止措置研究・人材育成等強化プログラムにおける人材育成活動 (2)－東京工業大学「廃止措置工学高度人材育成と基盤研究の深化」実施状況－, 日本原子力学会2016年秋の大会, 日本原子力学会2016年秋の大会予稿集, 日本原子力学会, 3M02, Sept. 2016.
• 小原徹, 岡本孝司, 原信義, 安濃田良成, 佐藤正知, 高貝慶隆, 東畑郁生, 佐藤勇. 英知を結集した原子力科学技術・人材育成推進事業 廃止措置研究・人材育成等強化プログラムにおける人材育成活動(1)－全体概要－, 日本原子力学会2016年秋の大会, 日本原子力学会2016年秋の大会予稿集, 日本原子力学会, 3M01, Sept. 2016.
• Tuya Delgersaikhan, Jun Nishiyama, Toru Obara. Supercritical transient analysis in light water moderated coupled small fuel debris regions using integral kinetic model and point kinetic model, 2016 autumn meeting of Atomic Energy Society of Japan, Proc. of 2016 autumn meeting of Atomic Energy Society of Japan, Atomic Energy Society of Japan, 2H12, Sept. 2016.
• 大里 洋輝, 西山 潤, 小原 徹. 軽水炉取り出しプルトニウムを初期炉心に用いたCANDLE 燃焼炉の熱流動解析, 日本原子力学会2016年秋の大会, 日本原子力学会2016年秋の大会予稿集, 日本原子力学会, 1L12, Sept. 2016.
• 西山潤, 小原徹. 宇宙探査用小型CANDLE燃焼炉の最適化, 日本原子力学会2016年秋の大会, 日本原子力学会2016年秋の大会予稿集, 日本原子力学会, 1L11, Sept. 2016.
• Irwan Liapto Simanullang, Jun Nishiyama, Toru Obara. Introduction of rock-like oxide fuel in PBR with accumulative fuel loading Scheme, 2016 autumn meeting of Atomic Energy Society of Japan, Proc. of 2016 autumn meeting of Atomic Energy Society of Japan, Atomic Energy Society of Japan, 1L08, Sept. 2016.
• 大里 洋輝, 西山 潤, 小原 徹. 軽水炉取り出しプルトニウムを初期炉心に用いたCANDLE燃焼炉に関する研究, 日本原子力学会2016年春の年会, 日本原子力学会2016年春の年会予稿集, 3O13, Mar. 2016.
• 西山 潤, 小原 徹. 宇宙探査用電源としての小型CANDLE燃焼炉の研究, 日本原子力学会2016年春の年会, 日本原子力学会2016年春の年会予稿集, 3O14, Mar. 2016.
• Julia AbdulKarim, Jun Nishiyama, Toru Obara. Application of Melt Refining of Metal Fuel to CANDLE Reactor; (3)Effects of Cooling Time during Melt and Refining Procedures, 2016 annual meeting of Atomic Energy Society of Japan, Proc. of 2016 annual meeting of Atomic Energy Society of Japan, 3O12, Mar. 2016.
• Hai Ho Quan, Toru Obara. OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements; (4)Burnup performance in molten salt coolant, 2016 annual meeting of Atomic Energy Society of Japan, Proc. of 2016 annual meeting of Atomic Energy Society of Japan, 3O11, Mar. 2016.
• Irwan Liapto Simanullang, Toru OBARA. Optimization of initial fuel composition for Small Pebble Bed Reactor with accumulative fuel loading scheme; (2) Use of burnable poison, 2016 annual meeting of Atomic Energy Society of Japan, Proc. of 2016 annual meeting of Atomic Energy Society of Japan, 3O10, Mar. 2016.
• 竹澤 宏樹, 小原 徹. 燃料デブリダストの再臨界をパッシブに抑制する方法, 日本原子力学会2016年春の年会, 日本原子力学会2016年春の年会予稿集, 3E07, Mar. 2016.
• Delgersaikhan Tuya, Toru OBARA. Statistical Uncertainty in Kinetic Analysis using Integral Kinetic Model for Re-criticality Accident in Weakly-Coupled Fuel Debris, 2016 annual meeting of Atomic Energy Society of Japan, Proc. of 2016 annual meeting of Atomic Energy Society of Japan, 1O13, Mar. 2016.
• Hai Quan Ho, Toru Obara. OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements (3) Optimization of the core parameters and analysis of temperature coefficient, 日本原子力学会2015年秋の大会, 日本原子力学会2015年秋の大会予稿集, D24, Sept. 2015.
• Julia ABDULKARIM, Jun NISHIYAMA, Toru OBARA. Application of Melt Refining of Metal Fuel to CANDLE Reactor (2) Effects of noble and reactive fission gasses removal to the burnup performance, 日本原子力学会2015年秋の大会, 日本原子力学会2015年秋の大会予稿集, D21, Sept. 2015.
• Delgersaikhan Tuya, Toru Obara. Kinetic Analysis of Re-criticality Accident in Simplified System of Fuel Debris and Consolidated Fuel, 日本原子力学会2015年秋の大会, 日本原子力学会2015年秋の大会予稿集, A22, Sept. 2015.
• Van Khanh Hoang, Toru Obara. Effects of Neutron Spectrum Shift on Burnup Performance of a Breed and Burn Reactor, 日本原子力学会2015年秋の大会, 日本原子力学会2015年秋の大会予稿集, D28, Sept. 2015.
• Odmaa Sambuu, Toru Obara. Comparison on design parameter criteria of prismatic HTGR and PBR for passive decay heat removal, 日本原子力学会2015年秋の大会, 日本原子力学会2015年秋の大会予稿集, D25, Sept. 2015.
• Irwan Liapto SIMANULLANG, Toru OBARA. Optimization of Initial Fuel Composition for Small Pebble Bed Reactor with Accumulative Fuel Loading Scheme (1)Reduction of Fuel Enrichment, 日本原子力学会2015年秋の大会, 日本原子力学会2015年秋の大会予稿集, D23, Sept. 2015.
• 小原徹, Tuya Delgersaikhan. 積分型動特性モデルを用いた溶融デブリの臨界事故解析 (1)研究概要と解析手法, 日本原子力学会2015春の年会予稿集, J23, Mar. 2015.
• Odmaa Sambuu, Toru OBARA. Design parameter condition of PBR for passive decay heat removal, 日本原子力学会2015春の年会予稿集, J43, Mar. 2015.
• Delgersaikhan Tuya, Toru OBARA. The Criticality Accident Analysis of Melted Debris by Integral Kinetic Model (2) Preliminary Analysis for Two-Unit Systems, 日本原子力学会2015春の年会予稿集, J24, Mar. 2015.
• Hohai Quan, Toru OBARA. OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements (2) Optimization of the fuel composition, 日本原子力学会2015春の年会予稿集, J44, Mar. 2015.
• 菊池遼, 小原徹. 弱結合体系における臨界安全過渡解析に関する研究 (3) 2タンク体系での溶液組成及び幾何形状の効果, 日本原子力学会2015春の年会予稿集, J26, Mar. 2015.
• 西山潤, 小原徹. CANDLE 燃焼実験炉の設計研究, 日本原子力学会2014秋の大会, 日本原子力学会2014秋の大会予稿集, H44, Sept. 2014.
• Hai Quan Ho, Toru OBARA. OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements (1) Burnup analysis in equilibrium condition, Proc. of 2014 Fall Meeting of Atomic Energy Society of Japan, L20, Sept. 2014.
• 菊池遼, 小原徹. 弱結合体系における臨界安全過渡解析に関する研究；(2)放射線分解ガスボイドを考慮した過渡解析, 日本原子力学会2014年春の年会, 日本原子力学会2014年春の年会予稿集, O33, Mar. 2014.
• 田中真人, 小原徹, 西山潤. CANDLE炉における初期燃焼特性の最適化に関する研究, 日本原子力学会2014年春の年会, 日本原子力学会2014年春の年会予稿集, K23, Mar. 2014.
• Topan Setiadipura, Toru OBARA. Optimum Start-up Procedure in OTTO Cycle Pebble Bed Reactor, 日本原子力学会2014年春の年会, 日本原子力学会2014年春の年会予稿集, K17, Mar. 2014.
• Odmaa Sambuu, Toru OBARA. Long-life, small prismatic HTGR designs for passive decay-heat removal, 日本原子力学会2014年春の年会, 日本原子力学会2014年春の年会予稿集, K16, Mar. 2014.
• 西山潤, 小原徹. 加速器中性子源点火型CANDLE燃焼炉における外部中性子源エネルギー特性, 日本原子力学会2013年秋の大会, 日本原子力学会2013年秋の大会予稿集, G04, Sept. 2013.
• Piyatida Trinuruk, Toru OBARA. Preventing the Prompt Critical Accident in Block-type HTGRs by using Particle Type Burnable Poisons, 日本原子力学会2013年秋の大会, 日本原子力学会2013年秋の大会予稿集, G33, Sept. 2013.
• 西山潤, 小原徹. 加速器中性子源点化型CANDLE燃料炉に関する研究, 日本原子力学会2012秋の大会, 日本原子力学会2012秋の大会予稿集, P35, Sept. 2012.
• Piyatida Trinuruk, Toru OBARA. Prismatic HTGR with Silicon Carbide Coated Graphite Block Core（1）Effects on Thermal-Hydraulic Behavior under the Normal Operation, 日本原子力学会2012秋の大会, 日本原子力学会2012秋の大会予稿集, P41, Sept. 2012.
• Byambajav Munkhbat, Toru OBARA. Design Concept of a Small Nuclear Reactor for Large-Diameter NTD-Si using Short PWR Fuel Assemblies, 日本原子力学会2012秋の大会, 日本原子力学会2012秋の大会予稿集, P40, Sept. 2012.
• Piyatida Trinuruk, Toru Obara. Neutronic Analysis of Prismatic HTGR with Silicon Carbide Coated Graphite Block Core, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, D09, Mar. 2012.
• Byambajav Munkhbat, Toru Obara. Design study on a small reactor for silicon semiconductor production using LWR fuel；(4) Uniformity of doping, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, D06, Mar. 2012.
• Topan Setiadipura, Toru Obara. Validation of Depletion Module of Equilibrium Burnup Analysis Code for OTTO Cycle in Pebble Bed Reactor, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, C39, Mar. 2012.
• Dwi Irwanto, Toru Obara. Design Study of Innovative Simplified Small Pebble Bed Reactor;（5）Passive Safety Analysis for Decay Heat Removal without Forced Cooling, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, C38, Mar. 2012.
• 尾上泰基, 小原徹. 粒子状可燃性毒物による高温ガス炉燃焼特性向上に関する研究, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, D08, Mar. 2012.
• 小原 徹. 東京電力福島第一原子力発電所事故と革新的原子炉研究, 第109回触媒討論会, 触媒, Vol. 54, No. 2, p. 70, Mar. 2012.
• 磯部陽介, 小原徹. 原子炉炉心での核励起レーザー発振シミュレーションに関する研究, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, D51, Mar. 2012.
• 友成健人, 小原徹. 慣性核融合炉用原子炉レーザーの設計研究, 日本原子力学会2012春の年会, 日本原子力学会2012春の年会予稿集, D50, Mar. 2012.
• 菊池 遼, 小原 徹. 弱結合体系における臨界安全過渡解析に関する研究；(1) ウラン燃料溶液体系の予備解析, 日本原子力学会2011秋の大会予稿集, N27, Sept. 2011.
• Byambajav Munkhbat, Toru Obara. Design study on small reactor for silicon semiconductor production using LWR fuel; (3) Optimization of burnable poison, 日本原子力学会2011秋の大会予稿集, O43, Sept. 2011.
• Sambuu Odmaa, 小原 徹. モンゴルでの小型地域熱供給用原子炉の予備的解析, 日本原子力学会2011秋の大会予稿集, O41, Sept. 2011.
• Piyatida Trinuruk, Toru Obara. Study of SiC Components to Improve the Neutron Economy in HTGR, 日本原子力学会2011秋の大会予稿集, N31, Sept. 2011.
• Dwi Irwanto, Toru Obar. Design Study of Innovative Simplified Small Pebble Bed Reactor; (4) Analysis of the Thorium Fuel in the Simplified PBR Design with a Pea a Peu Fuel Loading Scheme, 日本原子力学会2011秋の大会予稿集, N31, Sept. 2011.
• 菊池 遼, 小原 徹. 弱結合体系における臨界安全過渡解析に関する基礎的研, 日本原子力学会2011春の年会予稿集, I46, Mar. 2011.
• Byambajav Munkhbat, Toru Obara. Design study on small reactor for silicon semiconductor production using LWR fuel; (2) Reactor optimization, 日本原子力学会2011春の年会予稿集, G27, Mar. 2011.
• Dwi Irwanto, Toru Obara. Design Study of Innovative Simplified Small Pebble Bed reactor; (3) Analysis of the 110MWt Simplified PBR Design with Peu a Peu fuel loading scheme, 日本原子力学会2011春の年会予稿, I34, Mar. 2011.
• Piyatida Trinuruk, Toru Obara. Effect on Burnup Performance in HTGR by Neutron Spectrum Shift, 日本原子力学会2011春の年会予稿集, G19, Mar. 2011.
• Topan Setiadipura, Toru Obara. Development of Equilibrium Burnup Analysis Code for OTTO Cycle in Pebble Bed Reacto, 日本原子力学会2011春の年会予稿集, G20, Mar. 2011.
• Dwi IRWANTO, Toru OBARA. Design Study of Innovative Simplified Small Pebble Bed reactor; (2) Steady State Thermal Hydraulic Analysis of Reference Design, 日本原子力学会2010秋の大会予稿集, Q22, Sept. 2010.
• 田川 祐樹, 森 伸介, 鈴木 正昭, 山中 一郎, 小原 徹, 劉 醇一, 加藤 之貴. 固体酸化物形電解質による酸素分離がプラズマCO2分解に及ぼす影響, 化学工学会第42回秋季大会, 化学工学会第42回秋季大会研究発表講演要旨集, J202, Sept. 2010.
• 竹澤宏樹, 小原 徹. 核励起レーザー発振用原子炉の研究；(XI)低濃縮ウランを用いた結合炉の空間依存動特性解析, 日本原子力学会2010年春の年会予稿集, H31, Mar. 2010.
• Byambajav Munkhbat, Toru Obara. Design study on small reactor for semiconductor production using LWR fuel ; (1) Reactor Concept, 日本原子力学会2010年春の年会予稿集, H01, Mar. 2010.
• Dwi Irwanto, Toru Obara. Design Study of Innovative Simplified Small Pebble Bed Reactor; (1) Design Concept and Sample Design Analysis, 日本原子力学会2009年秋の大会予稿集, F34, Sept. 2009.
• 竹澤宏樹, 小原 徹. 核励起レーザー発振用原子炉の研究；（X）積分型動特性モデルに基づく空間依存動特性解析の検証, 日本原子力学会2009年秋の大会予稿, F36, Sept. 2009.
• 大谷純一朗, 小原 徹. 核励起レーザー発振用原子炉の研究；（IX）レーザー推進用原子炉の概念設計, 日本原子力学会2009年春の年会予稿集, K07, Mar. 2009.
• 竹澤宏樹, 小原 徹. 核励起レーザー発振用原子炉の研究；（VIII）積分型動特性モデルに基づく空間依存動特性解析, 日本原子力学会2009年春の年会予稿集, K06, Mar. 2009.
• Dwi Irwanto, Toru Obara, Go Chiba. Study on Calculation Methods for Effective Delayed Neutron Fraction, 日本原子力学会2009年春の年会予稿集, K30, Mar. 2009.
• Liem Peng Hong, 小原 徹, 八木秀樹. 大口径シリコン半導体素子製造用小型原子炉の研究；（２）熱流動解析及び中性子照射性能解析, 日本原子力学会2009年春の年会予稿集, L49, Mar. 2009.
• 小原 徹, Liem Peng Hong, 八木秀樹. 大口径シリコン半導体素子製造用小型原子炉の研究；（１）研究概要及び核設計, 日本原子力学会2009年春の年会予稿集, L48, Mar. 2009.
• 小原徹, 関本博, 加藤之貴, 山野直樹, 有冨正憲, 赤塚洋. 「東京工業大学21世紀COEプログラム「世界の持続的発展を支える革新的原子力」成果報告」革新的原子力を目指す国際研究ネットワークの構築, 日本原子力学会2008年春の年会予稿集, OV5, Sept. 2008.
• 竹澤宏樹, 小原徹. 核励起レーザー発振用原子炉の研究；(V)パルス炉心レーザーモジュール結合体系時間依存結合係数の検証, 日本原子力学会2008年秋の大会予稿集, C20, Sept. 2008.
• 大谷純一朗, 小原徹. 核励起レーザー発振用原子炉の研究；(VI)レーザー推進用原子炉の臨界解析, 日本原子力学会2008年秋の大会予稿集, C21, Sept. 2008.
• 庄司和生, 小原徹, 冨澤宏光. 核励起レーザー発振用原子炉の研究；(VII)レート方程式を用いたレーザー媒質数密度の時間変化, 日本原子力学会2008年秋の大会予稿集, C22, Sept. 2008.
• 高橋実, 関本博, 小原徹, 加藤之貴, 高木直行. 総合講演・報告１「東京工業大学21世紀COEプログラム「世界の持続的発展を支える革新的原子力」成果報告」(2)革新的原子力技術－持続・安全・廃棄物・核拡散の解決を目指して革新的炉型概念研究と調和型原子力システム研究, 日本原子力学会2008年春の年会, Mar. 2008.
• 小原徹. 鉛ビスマス利用技術」専門委員会報告「高速炉と加速器駆動変換炉の開発における鉛ビスマス利用技術の現状と将来展望」（７）ポロニウム対策技術の進展, 日本原子力学会2007年秋の大会予稿集, OV7, Sept. 2007.
• 竹澤宏樹, 小原徹. 核励起レーザー発振用原子炉の研究（IV）；パルス炉心レーザーモジュール結合体系空間依存動特性方程式の解法, 日本原子力学会2007年秋の大会予稿集, D-16, Sept. 2007.
• 山沢雄, 小原徹, 佐々敏信. ビスマスから生成されるポロニウムの振る舞いに関する研究VIII－ポロニウムフィルターに関する基礎実験－, 日本原子力学会2007年秋の大会予稿集, D-17, Sept. 2007.
• 小原徹, 竹澤宏樹. 核励起レーザー発振用原子炉に関する研究；（III）パルス炉心レーザーモジュール結合体系の動特性解析手法の検討, 日本原子力学会2007年春の年会予稿集, D-4, Mar. 2007.
• 小原徹, 竹澤宏樹. 核励起レーザー発振用原子炉に関する研究；（I）研究の概要, 日本原子力学会2006年秋の大会, 日本原子力学会2006年秋の大会予稿集, O-17, Sept. 2006.
• 竹澤宏樹, 小原徹. 核励起レーザー発振用原子炉に関する研究；（II）金属ウランパルス炉心レーザーモジュール結合体系の臨界解析, 日本原子力学会2006年秋の大会, 日本原子力学会2006年秋の大会予稿集, O-18, Sept. 2006.
• 古賀健, 三浦照光, 小原徹, 関本博. ビスマスから生成されるポロニウムの振る舞いに関する研究VII －ポロニウムのニッケルに対する吸着挙動－, 日本原子力学会2006年度春の年会, 日本原子力学会2006年春の年会予稿集, N-17, Mar. 2006.
• 小原徹, 三浦照光, 関本博. 鉛ビスマス共晶合金中に生成されたポロニウムの蒸発・付着特性, 日本機械学会2006年度年次大会, 日本機械学会2006年度年次大会講演論文集, p. 2643, 2006.
• Terumitsu Miura, Toru Obara, Hiroshi Sekimoto. Chemical Form of Polonium in LBE and Vacuum Sblimation Method, MIT- Tokyo Tech Symposium on Innovative Nuclear Energy System, 2-4 November, 2005, Massachusetts Institute of Technology, Royal Sonesta Hotel, Cambridge, Massachusetts 02139 USA (2005), MIT- Tokyo Tech Symposium on Innovative Nuclear Energy System, 2-4 November, 2005, Massachusetts Institute of Technology, Royal Sonesta Hotel, Cambridge, Massachusetts 02139 USA (2005), CD-ROM, Nov. 2005.
• 三浦照光, 小原徹, 関本博. ビスマスから生成されるポロニウムの振る舞いに関する研究VI －鉛ビスマス中におけるポロニウムの化学形態の検討－, 日本原子力学会2005年度秋の年会, 日本原子力学会2005年度秋の年会予稿集, E-46, 2005.
• 三浦照光, 小原徹, 関本博. Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 III (4) 鉛ビスマス・水直接接触ポロニウム放出・拡散・吸着実験, 日本原子力学会2005年春の年会, 日本原子力学会2005年春の年会予稿集, F-33, 2005.
• 三浦照光, 小原徹, 関本博. 鉛ビスマス冷却炉の構造材表面に対するポロニウムの吸着・脱離特性研究, 日本機械学会2005年度年次大会, 日本機械学会2005年度年次大会講演論文集, p. 3514, 2005.
• 三浦照光, 小原徹, 関本博. Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発(I) (11) ポロニウム対策試験用加熱吸着試験装置の温度校正実験, 日本原子力学会2004年春の年会, 日本原子力学会2004年春の年会予稿集, O-11, 2004.
• 小原徹, 三浦照光, 関本博, 大崎敏郎, 井頭政之, 矢野豊彦. Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発(I) (10) ポロニウム対策技術試験の概要, 日本原子力学会2004年春の年会, 日本原子力学会2004年春の年会予稿集, O-10, 2004.
• 三浦照光, 小原徹, 関本博. Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 II (8) SUS316ポロニウム表面汚染除去実験, 日本原子力学会2004年秋の大会, 日本原子力学会2004年秋の大会予稿集, pp. C-34, 2004.
• 松澤孝治, 内田正治, 高橋実, 小原徹. Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 II (7) PBWFRにおけるポロニウム評価設計, 日本原子力学会2004年秋の大会, 日本原子力学会2004年秋の大会予稿集, C-33, 2004.
• 高橋実, 小原徹, 内田正治, 羽田晃治, 荒邦章. Pb-Bi冷却直接接触沸騰水型小型高速炉に関する技術開発 II (1) PBWFRの技術開発研究の概要, 日本原子力学会2004年秋の大会, 日本原子力学会2004年秋の大会予稿集, C-27, 2004.
• 三浦照光, 小原徹, 関本博. ビスマスから生成されるポロニウムの振る舞い（V）：アルファ線スペクトルによる鉛ビスマス内のポロニウム分布の評価, 日本原子力学会2003年春の年会予稿集, O-61, 2003.
• 三浦照光, 小原徹, 関本博. 鉛ビスマス冷却炉の構造材表面におけるポロニウム汚染の除去検討, 日本機械学会2003年度年次大会講演論文集, p. 2234, 2003.
• 藤田佳之, 三浦照光, 小原徹, 関本博. ビスマスから生成されるポロニウムの振る舞い（III）：溶融鉛ビスマス合金からのポロニウムの放出と石英ガラスへの付着, 日本原子力学会2002年春の年会予稿集, N-15, 2002.
• 三浦照光, 小原徹, 関本博. ビスマスから生成されるポロニウムの振る舞い（IV）：石英ガラスのポロニウム汚染のベーキングによる除去, 日本原子力学会2002年秋の大会予稿集, E-25, 2002.
• 小原徹. 核励起レーザー開発と炉物理, 日本原子力学会2002年秋の大会予稿集、炉物理部会企画セッション「核励起レーザー開発における炉物理研究」, pp. 1, 2002.
• Toru OBARA, Yoshiyuki FUJITA, Yasuo ANDO, Hiroshi SEKIMOTO. Study on Behavior of Polonium from Neutron Irradiated Lead-Bismuth Eutecti, Bulletin of the Research Laboratory for Nuclear Reactors, Vol. 25, p. 83, 2001.
• 藤田佳之, 安東康雄, 小原徹, 関本 博. ビスマスから生成されるポロニウムの振る舞い(II) －石英ガラスへの付着－, 日本原子力学会2001年秋の大会予稿集, G-64, 2001.
• 小原 徹, A.G. Morozov, V.V. Kevrolev, V.V. Kuznetsov, S.A. Treschalin, A.V. Lukin, V.A. Terekhin, Yu.A. Sokolov, V.G. Kravchenko. ロシアで行われた高濃縮ウラン及びプルトニウム体系での臨界実験のモンテカルロ解析, 日本原子力学会2000年秋の大会予稿集, G-46, 2000.
• 小原 徹, 関本 博. モンテカルロ計算におけるkeff of the World問題の検討, 日本原子力学会1998年秋の大会予稿集, D-34, 1998.
• 龍 浩一, 小原 徹, 関本 博. ウランを高効率に利用する原子炉概念, 日本原子力学会1997年春の年会予稿集, H-19, 1997.
• 小原 徹, 関本 博. ErによるPu溶液温度係数補正効果, 日本原子力学会1997年秋の大会予稿集, F-87, 1997.
• SHUNJI TSUJI-IIO, H. TSUTSUI, J. KONDOH, Toru OBARA, TOYOHIKO YANO, Masayuki Igashira, MASANORI ARITOMI, HIROSHI SEKIMOTO, R. TAKAGI, M. OKAMOTO, ryuichi shimada. High-Field Tokamak Reactor with Force-Balanced Coils as a Volumetric Neutron Source, 16th IAEA Fusion Energy Conf., Fusion Energy 1996 (Proc. 16th IAEA Fusion Energy Conf., Montreal, 1996), Proc. Sixteenth Internat. Conf. on Fusion Energy Organized by IAEA and held in Memorial, Vol. 3, pp. 685-692, 1996.
• 小原 徹, 関本 博. 反応度事故実験装置の研究(IX);出力バースト後のテスト炉心の反応度効果の検出, 日本原子力学会1996年秋の大会要旨集, D-23, 1996.
• 小原 徹, 関本 博. 反応度事故実験装置の研究(VIII)パーティクルベッドドライバー炉心の加熱性能, 日本原子力学会1996年春の年会要旨集, E-33, 1996.
• 竹村 一仁, 小原 徹, 関本 博. 出力密度の平坦化, 日本原子力学会1995年秋の大会予稿集, B-64, 1995.
• 星 秀一郎, 小原 徹, 関本 博. 被覆粒子燃料を用いたパルス高速炉の概念設計, 日本原子力学会1995年春の年会要旨集, C-14, 1995.
• 小原 徹, 関本 博. 反応度事故実験装置の研究(VII);ドライバー炉心の最適化, 日本原子力学会1995年春の年会要旨集, C-13, 1995.
• 星 秀一郎, 小原 徹, 関本 博. 被覆粒子燃料を用いたパルス実験炉の概念設計, 日本原子力学会1994年秋の大会予稿集, G-73, 1994.
• 小原 徹, 関本 博. 反応度事故実験装置の研究(VI);稀薄燃料を使用したパーティクルベッドドライバ炉心, 日本原子力学会1994年秋の大会予稿集, G-6, 1994.
• 小原 徹, 関本 博. 反応度事故実験装置の研究(V);高速炉心反応度効果の再現性, 日本原子力学会1994年春の年会要旨集, G-4, 1994.
• 小原 徹, 関本 博. 反応度事故実験装置の研究(IV)ゼロ反応度温度係数炉心の検討, 日本原子力学会1993年春の年会要旨集, A-41, 1993.
• 関本 博, 小原 徹. 反応度事故実験装置の研究，(I) ；研究目的と概要, M-61, June 1992.
• 岩間俊彦, 小原 徹, リンペンホン, 関本 博. 反応度事故実験装置の研究，(III) ；動特性解析方法の比較検討, 日本原子力学会1992年秋の大会予稿集, M-63, 1992.
• 小原 徹, 関本 博. 反応度事故実験装置の研究，(II) ；静的解析, 日本原子力学会1992年秋の大会予稿, M-62, 1992.
• 小原 徹, 関本 博. ペブルベッド型炉における装荷燃料組成と平衡時の燃焼特性の関係評価 (II) ；装荷燃料組成による中性子スペクトルの変化の効果, 日本原子力学会1991年春の年会要旨集, A-16, 1991.
• 小原 徹, 関本 博. ペブルベッド型高温ガス炉燃焼解析コードの開発 III, 日本原子力学会1990年年会, 日本原子力学会1990年年会, B-45, 1990.
• 小原 徹, 関本 博. ペブルベッド型炉における装荷燃料組成と平衡時の燃焼特性の関係評価, 日本原子力学会1990年秋の大会予稿集, D-29, 1990.
• 小原 徹, 末富英一, 廣瀬行徳, 関本 博. ペブルベッド型高温ガス炉燃焼解析コードの開発 II, 日本原子力学会昭和62年年会, 日本原子力学会昭和62年年会, E-8, 1987.
• 小原 徹, 末富英一, 島 望, 小野田崇, 廣瀬行徳, 関本 博. ペブルベッド型高温ガス炉燃焼解析コードの開発, 日本原子力学会昭和61年秋の分科会, 日本原子力学会昭和61年秋の分科会, D-50, 1986.

その他の論文・著書など

• 小原徹. 小型モジュール炉開発の現状と展望, 化学工学, 化学工学会, Vol. 88, No. 5, pp. 207-210, May 2024.
• 小原徹. 小型モジュール型原子炉開発の動向, 日本高圧力技術協会, Vol. 60, No. 3, pp. 34-39, May 2022.  公式リンク  
  
• 小原 徹, 西山 潤, 竹澤宏樹. JAEA-Review 2021-027,  燃料デブリ取出し臨界安全技術の高度化 -令和2年度 英知を結集した原子力科学技術・人材育成推進事業-, 日本原子力研究開発機構, Jan. 2022.  公式リンク  
  
• 小原徹. 先進次世代原子炉の多角的研究, 炉物理の研究, 日本原子力学会炉物理部会, No. 73, Mar. 2021.  公式リンク  
  
• 小原徹. SMR開発の展望, 日本原子力学会誌, 日本原子力学会, Vol. 62, No. 3, pp. 25-26, Mar. 2020.
• 小原徹. 大学における原子力教育の今 -東京工業大学：国際的に通用するリーダーの輩出へ-, エネルギーレビュー, Vol. 39, No. 11, pp. 9-10, Oct. 2019.
• 小原徹. 国内外の原子力教育事情(1) 東京工業大学での原子力教育の取組み, 日本原子力学会誌, Vol. 61, No. 1, pp. 70-72, Jan. 2019.
• Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara. MIK - Multi-region Integral Kinetic code, Version 1.0, MIK-multi-region integral kinetic code, version 1.0, Tokyo Institute of Technology, Dec. 2018.
• 小原徹. 東京工業大学における廃止措置高度人材育成活動と基盤的研究の推進, 原子力バックエンド研究, 日本原子力学会バックエンド部会, Vol. 25, No. 2, pp. 71-78, Dec. 2018.  公式リンク  
  
• 小原徹. 廃炉基盤技術と人材育成, エネルギーレビュー, エネルギーレビューセンター, Vol. 38, No. 10, pp. 16-20, Sept. 2018.
• 小原 徹. 国際原子力派遣教育研究会議調査報告-国際社会で活躍する人材の育成のために-, 原子力eye, Vol. 57, No. 6, pp. 56-59, June 2011.
• 小原 徹. 国際的な原子力教育における日本の役割, 電気協会報, No. 1019, pp. 16-19, Oct. 2009.
• 小原 徹. 世界の持続的発展を支える革新的原子力」(COE-INES)3年目の成果[2]国際活動, 原子力eye, Vol. 52, No. 5, pp. 26-27, 2006.
• 小原徹. 高速中性子減速理論, 第37回炉物理夏期セミナーテキスト「最新炉物理講義」, （社）日本原子力学会，東京工業大学COE-INES, pp. 41-58, 2005.
• 小原 徹, 三浦照光, 関本 博. 鉛ビスマス冷却材のポロニウム対策の研究, 研究炉ひろば, 日本原子力研究所, Vol. 22, No. 1, p. 6, 2005.
• 小原 徹, 中島 健, 三好慶典, 関本 博. TRACY実験におけるフィードバック反応度の空間分布効果 －第１出力ピーク特性の評価－, JAERI-Research, 日本原子力研究所, 2001-37, June 2001.
• 関本 博, 小原 徹, 大谷 暢夫. 原研・動燃施設による東京工業大学大学院生実験授業, 日本原子力学会誌, Vol. 37, No. 8, pp. 681-688, 1995.
• 小原 徹, 堀木欧一郎, 中島照夫, 渡辺終吉, 石島清見, 片西昌司. JRR-4及びNSRRを用いた原子炉物理の基礎実験, JAERI-Review, 95-010, 1995.
• 小原 徹, 中島 健, 井頭政之, 関本 博, 須崎武則. 臨界集合体TCAを用いた原子炉物理の基礎実験, JAERI-M, 日本原子力研究所, 94-004, Feb. 1994.
• Milton C. EDLUND, 小原 徹. 原子力黎明期の思い出 （小原徹訳）, 日本原子力学会誌, Vol. 34, No. 3, 256-258, 1992.

学位論文

• パーティクルベッド高速ドライバー炉心を用いた炉内試験用原子炉に関する研究,  本文,  博士（工学）,  東京工業大学,  1997/10/31, 
• ぺブルベット型高温ガス炉燃焼解析コードの開発,  修士(工学),  東京工業大学,  1987/03/26, 

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