Tokyo Institute of Technology   Head of Founding Preparations of Graduate Major in Nuclear Engineering

2015.4 - 2016.3

Tokyo Institute of Technology   Laboratory for Nuclear Reactors   Professor

2013.6 - 2016.3

Tokyo Institute of Technology   Laboratory for Nuclear Reactors   Associate Professor

2007.4 - 2013.5

Tokyo Institute of Technology   Laboratory for Nuclear Reactor   Associate professor

2002.12 - 2007.3

Japan Society for the Promotion of Science   Researcher Dispatched under the NIS (Former Soviet Union) Countries Researcher Exchange Program (Kurchatov Institute, IPPE; Russsia))

1999.3 - 1999.9

Tokyo Institute of Technology   Labobatory for Nuclear Reactor   Assistant professor

1991.4 - 2002.11

JSPS Research Fellowship for Young Scientists (DC)

1990.4 - 1991.3

NAIG   Research Center   Researcher

1987.4 - 1988.12

Comparison of burnup performance between lead coolant and LBE coolant in Rotational Fuel-shuffling Breed-and-Burn fast reactor Reviewed

Xucheng Zhao, Jun Nishiyama, Toru Obara

Progress in Nuclear Science and Technology   7   9 - 13   2025.3

Coolant void coefficient in a sodium-cooled rotational fuel-shuffling breed-and-burn fast reactor Reviewed

Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara

Progress in Nuclear Science and Technology   7   5 - 8   2025.3

Fuel cycle features of RFBB fast reactor with advanced fuel Reviewed

Odmaa Sambuu, Van Khanh Hoang, Tsendsuren Amarjargal, Toru Obara

Journal of Nuclear Science and Technology   62 ( 6 )   562 - 572   2025.1

Neutronics–Thermal-Hydraulics–Coupled Transient Analysis for Reactor Power Change in an Inclined Offshore Floating Boiling Water Reactor Reviewed

Kodai Fukuda, Toru Obara, Kenya Suyama

Nuclear Technology   211 ( 5 )   963 - 973   2024.7

Small rotational fuel-shuffling breed-and-burn sodium-cooled and nitride-fueled fast reactor with LBE reflectors Reviewed

Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   201   110445 - 110445   2024.6

Practical Design of a Breed-and-Burn Lead-Cooled Fast Reactor with Rotational Fuel Shuffling Strategy Reviewed

Alexandru Catalin Stafie, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   199 ( 2 )   266 - 279   2024.5

Feasibility of breed-and-burn reactor core design with nitride fuel and lead coolant Reviewed

Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   182   109583 - 109583   2023.3

Impact of the Melt-Refining Process on the Performance of Sodium-Cooled Rotational Fuel-Shuffling Breed-and-Burn Reactors Reviewed

Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   197 ( 7 )   1520 - 1533   2023.1

Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor with Nitride Fuel and Sodium Coolant Reviewed

Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   197 ( 4 )   711 - 718   2022.11

Monte Carlo codes benchmarking on sub-critical fuel debris particles system for neutronic analysis Reviewed

Anton Smirnov, Ekaterina Bogdanova, Pavel Pugachev, Mikhail Ternovykh, Ivan Saldikov, Georgy Tikhomirov, Hiroki Takezawa, Jun Nishiyama, Toru Obara

Journal of Nuclear Science and Technology   59 ( 1 )   34 - 43   2022

Granular fuel debris shape modeling in MPS-DEM for the simulation of fuel debris bed formation in water Reviewed

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Journal of Nuclear Science and Technology   59 ( 4 )   438 - 445   2021.10

Neutron Balance Features in Breed-and-Burn Fast Reactors Reviewed

Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   196 ( 3 )   322 - 341   2021.10

Characteristics of reactivity change as fuel debris falls in water Reviewed

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Progress in Nuclear Energy   139   103857 - 103857   2021.9

Impact of neutron generation time on released energy in falling fuel debris at supercritical condition Reviewed

Kodai Fukuda, Takeshi Muramoto, Jun Nishiyama, Toru Obara

Journal of Nuclear Science and Technology   59 ( 2 )   230 - 239   2021.8

Feasibility of Sodium-Cooled Breed-and-Burn Reactor with Rotational Fuel Shuffling Reviewed

Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   196 ( 1 )   109 - 120   2021.7

Optimization of reactor size in the small sodium-cooled CANDLE burning reactor Reviewed

Hoang Hai Nguyen, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   153   108040 - 108040   2021.4

Calculation of Transient Parameters of the Integral Kinetic Model with Delayed Neutrons for Space-Dependent Kinetic Analysis of Coupled Reactors Reviewed

Hiroki Takezawa, Delgersaikhan Tuya, Toru Obara

Nuclear Science and Engineering   195 ( 11 )   1236 - 1246   2021

Supercritical Transient Analysis for Ramp Reactivity Insertion Using Multiregion Integral Kinetics Code Reviewed

Kodai Fukuda, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   195 ( 5 )   453 - 463   2021

Reactivity Feedback Effect on Supercritical Transient Analysis of Fuel Debris Reviewed

Kodai Fukuda, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   194 ( 7 )   493 - 507   2020.7

Neutronic modeling of a subcritical system with corium particles and water from international benchmark Reviewed

A. D. Smirnov, E. V. Bogdanova, P. A. Pugachev, I. S. Saldikov, M. Y. Ternovykh, G. V. Tikhomirov, H. Takezawa, T. Muramoto, J. Nishiyama, T. Obara

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika   2020 ( 2 )   135 - 145   2020.7

Evaluation of Discharged Fuel in Preproposed Breed-and-Burn Reactors from Proliferation, Decay Heat, and Radiotoxicity Aspects Reviewed

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   194 ( 5 )   405 - 413   2020.5

Radiation Dose Analysis in Criticality Accident of Fuel Debris in Water Reviewed

Kodai Fukuda, Delgersaikhan Tuya, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   194 ( 3 )   181 - 189   2020.3

Effects of compensating for fuel losses during the melt-refining process for a small CANDLE reactor Reviewed

Van Khanh Hoang, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   135   106969 - 106969   2020.1

Neutronic modeling of a subcritical system with corium particles and water (from international benchmark) Reviewed

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

Nuclear Energy and Technology   6 ( 3 )   155 - 160   2020

Visualization of neutron characteristics distribution of debris particles Reviewed

P. A. Pugachev, E. V. Bogdanova, I. S. Saldikov, A. D. Smirnov, M. Y. Ternovykh, G. V. Tikhomirov, H. Takezawa, T. Muramoto, J. Nishiyama, T. Obara

Scientific Visualization   12 ( 3 )   100 - 107   2020

Burnup Performance of CANDLE Burning Reactor Using Sodium Coolant Reviewed

Hoang Hai Nguyen, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   Vol. 194   1128 - 1142   2020

Numerical analysis of criticality of fuel debris falling in water Reviewed

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   131   112 - 122   2019.9

Application of melt-refining process to transition state of CANDLE burning fast reactor Reviewed

Hiroki Osato, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   128   77 - 83   2019.6

Development of Monte Carlo Neutron Transport Method-Based Supercritical Transient Code with Time-Dependent Feedback Capability Reviewed

Delgersaikhan Tuya, Toru Obara

Nuclear Science and Engineering   193 ( 5 )   481 - 494   2019.5

Concept of breed and burn reactor with spiral fuel shuffling Reviewed

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   127   130 - 138   2019.5

Supercritical transient analysis in hypothetical fuel-debris systems by multi-region approach based on integral kinetic model Reviewed

Delgersaikhan Tuya, Toru Obara

Annals of Nuclear Energy   120   169 - 177   2018.10

Burnup performance of MOX and Pu-ROX fuels in small pebble bed reactor with accumulative fuel loading scheme Reviewed

Irwan Liapto Simanullang, Toru Obara

Annals of Nuclear Energy   120   450 - 460   2018.10

Initial core design of CANDLE burning fast reactor using plutonium from LWR spent fuel Reviewed

Hiroki Osato, Jun Nishiyama, Toru Obara

Annals of Nuclear Energy   120   501 - 508   2018.10

Potential for the use of a liquid activation circulation material to measure the neutron flux in a high gamma-ray background Reviewed

Irwan Liapto Simanullang, Jun Nishiyama, Toru Obara

Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment   903   109 - 113   2018.9

Design concepts of small CANDLE reactor with melt-refining process Reviewed

Van Khanh Hoang, Jun Nishiyama, Toru Obara

Progress in Nuclear Energy   108   233 - 242   2018.9

Concept of Stationary Wave Reactor with Rotational Fuel Shuffling Reviewed

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Nuclear Science and Engineering   191 ( 2 )   178 - 186   2018.8

Design parameters in an annular, prismatic HTGR for passive decay heat removal Reviewed

Odmaa Sambuu, Jamyansuren Terbish, Toru Obara, Norov Nanzad, Munkhbat Byambajav

ANNALS OF NUCLEAR ENERGY   111   441 - 448   2018.1

Study on CANDLE Burning Fast Reactor with Initial Core Using Plutonium from LWR Spent Fuel Reviewed

Hiroki Osato, Jun Nishiyama, Toru Obara

Energy Procedia   Vol. 131   15 - 20   2017.12

Burnup Performance of a PBR with an Accumulative Fuel Loading Scheme Utilizing Burnable Poison Particles in UO 2 and ROX Fuels Reviewed

Irwan Liapto Simanullang, Toru Obara

Energy Procedia   131   61 - 68   2017.12

Impact of Neutron Spectrum Shift on Breed and Burn Reactor Concept Reviewed

Van Khanh Hoang, Toru Obara

Energy Procedia   131   37 - 44   2017.12

Burnup performance of rock-like oxide (ROX) fuel in small pebble bed reactor with accumulative fuel loading scheme Reviewed

Irwan Liapto Simanullang, Toru Obara

ANNALS OF NUCLEAR ENERGY   107   110 - 118   2017.9

Effects of cooling interval time in melt and refining process for CANDLE burning Reviewed

Julia Abdul Karim, Jun Nishiyama, Toru Obara

ANNALS OF NUCLEAR ENERGY   105   144 - 149   2017.7

Improved Approach to Multiregion Supercritical Transient Analysis Based on the Integral Kinetic Model and Monte Carlo Method Reviewed

Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara

NUCLEAR SCIENCE AND ENGINEERING   188 ( 1 )   33 - 42   2017

Supercritical transient analysis in coupled fuel debris systems of symmetric and asymmetric geometry using integral kinetic model Reviewed

Tuya, D., Obara, T.

Annals of Nuclear Energy   109   113 - 119   2017

Improvement of the “best representativity” method toward an industrial application Reviewed

Umano, T., Yoshioka, K., Obara, T.

Annals of Nuclear Energy   105   311 - 328   2017

Improvement of core design of small pebble bed reactor with accumulative fuel loading scheme Reviewed

Irwan Liapto Simanullang, Toru Obara

ANNALS OF NUCLEAR ENERGY   94   87 - 92   2016.8

Application of melt and refining procedures in the CANDLE reactor concept Reviewed

Julia Abdul Karim, Jun Nishiyama, Toru Obara

ANNALS OF NUCLEAR ENERGY   90   275 - 283   2016.4

The application of transient analysis code to estimation of total released energy in a two-fuel-solution-tank system Reviewed

Haruka Kikuchi, Toru Obara

ANNALS OF NUCLEAR ENERGY   87   486 - 493   2016.1

Design concept for a small pebble bed reactor with ROX fuel Reviewed

Hai Quan Ho, Toru Obara

ANNALS OF NUCLEAR ENERGY   87   471 - 478   2016.1

Impact of power density profile on passive decay heat removal in prismatic HTGR Reviewed

Odmaa Sambuu, Toru Obara

ANNALS OF NUCLEAR ENERGY   87   23 - 29   2016.1

Possible design of PBR for passive decay heat removal Reviewed

Odmaa Sambuu, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   53 ( 9 )   1296 - 1309   2016

Passive measure for preventing recriticality of fuel debris dust for defueling at Fukushima Daiichi nuclear power station Reviewed

Hiroki Takezawa, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   53 ( 12 )   1960 - 1967   2016

Supercritical kinetic analysis in simplified system of fuel debris using integral kinetic model Reviewed

Tuya, Delgersaikhan, Obara, Toru

Annals of Nuclear Energy   91   2016

Neutronic and thermo-hydraulic analyses of a small, long-life HTGR for passive decay-heat removal Reviewed

Odmaa Sambuu, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   52 ( 12 )   1519 - 1529   2015.12

Application of the "best representativity" method to a PWR fuel calculation using the critical experiments at the Toshiba NCA facility Reviewed

Takuya Umano, Kenichi Yoshioka, Toru Obara

ANNALS OF NUCLEAR ENERGY   85   78 - 92   2015.11

Burnup performance of OTTO cycle pebble bed reactors with ROX fuel Reviewed

Hai Quan Ho, Toru Obara

ANNALS OF NUCLEAR ENERGY   83   1 - 7   2015.9

Kinetic behavior in criticality accident of two fuel solution tanks Reviewed

Haruka Kikuchi, Toru Obara

PROGRESS IN NUCLEAR ENERGY   82   98 - 101   2015.7

Comparative study on HTGR designs for passive decay heat removal Reviewed

Odmaa Sambuu, Toru Obara

PROGRESS IN NUCLEAR ENERGY   82   37 - 45   2015.7

Above-ground HTGR design for passive decay heat removal Reviewed

Odmaa Sambuu, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   52 ( 6 )   857 - 871   2015.6

Optimization of Start-up Fuel Management for OTTO Cycle Pebble Bed Reactor Reviewed

Topan Setiadipura, Toru Obara

Energy Procedia   71   42 - 51   2015.5

Particle-type Burnable Poisons for Thorium-based Fuel in HTGR Reviewed

Piyatida Trinuruk, Toru Obara

Energy Procedia   71   22 - 32   2015.5

Development of Monte Carlo-based pebble bed reactor fuel management code Reviewed

Topan Setiadipura, Toru Obara

ANNALS OF NUCLEAR ENERGY   71   313 - 321   2014.9

Development of a "best representativity" method for experimental data analysis and an application to the critical experiments at the Toshiba NCA facility Reviewed

Takuya Umano, Kenichi Yoshioka, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   51 ( 5 )   608 - 625   2014.5

Concept of prismatic high temperature gas-cooled reactor with SiC coating on graphite structures Reviewed

Piyatida Trinuruk, Toru Obara

ANNALS OF NUCLEAR ENERGY   63   437 - 445   2014.1

Core designs based on research reactors for neutron transmutation doping of silicon Reviewed

Masao Komeda, Toru Obara

Annals of Nuclear Energy   65   338 - 344   2014

Possible design of long-life small prismatic HTGR for passive decay heat removal Reviewed

Sambuu, O., Obara, T.

Nuclear Science and Engineering   177 ( 1 )   97 - 109   2014

Design study on a fast reactor metal fuel attaining very high burnup Reviewed

Ohta, H., Ogata, T., Obara, T.

Nuclear Technology   187 ( 2 )   198 - 207   2014

Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme Reviewed

Dwi Irwanto, Toru Obara

ANNALS OF NUCLEAR ENERGY   60   383 - 395   2013.10

Small, long-life high temperature gas-cooled reactor free from prompt supercritical accidents by particle-type burnable poisons Reviewed

Piyatida Trinuruk, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   50 ( 9 )   898 - 912   2013.9

Flattening of burnup reactivity in long-life prismatic HTGR by particle type burnable poisons Reviewed

Toru Obara, Taiki Onoe

ANNALS OF NUCLEAR ENERGY   57   216 - 220   2013.7

Study on the burn-up characteristics of a thermal neutron filter containing B4C particles for NTD-Si irradiation Reviewed

Masao Komeda, Toru Obara

ANNALS OF NUCLEAR ENERGY   53   35 - 39   2013.3

Conceptual design of a small nuclear reactor for large-diameter NTD-Si using short PWR fuel assemblies Reviewed

Byambajav Munkhbat, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   50 ( 1 )   46 - 58   2013.1

A new irradiation method with a neutron filter for silicon neutron transmutation doping at the Japan research reactor no. 3 (JRR-3) Reviewed

Komeda, M., Kawasaki, K., Obara, T.

Applied Radiation and Isotopes   74   70 - 77   2013

Conceptual design for a small modular district heating reactor for Mongolia Reviewed

Odmaa Sambuu, Toru Obara

ANNALS OF NUCLEAR ENERGY   47   210 - 215   2012.9

Design simplification of a small nuclear reactor for large-diameter neutron transmutation doping silicon using control rods Reviewed

Munkhbat Byambajav, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   49 ( 8 )   845 - 856   2012.8

Design concept of a small nuclear reactor for large-diameter NTD-Si using a conventional PWR full-length fuel assembly Reviewed

Byambajav Munkhbat, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   49 ( 5 )   535 - 543   2012.5

New Approach to Space-Dependent Kinetic Analysis by the Integral Kinetic Model Reviewed

Hiroki Takezawa, Toru Obara

NUCLEAR SCIENCE AND ENGINEERING   171 ( 1 )   1 - 12   2012.5

Burnup characteristics and fuel cycle economics of mixed uranium-thorium fuel in a simplified small pebble bed reactor Reviewed

Dwi Irwanto, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   49 ( 1-2 )   222 - 229   2012.1

Burnup Characteristics of a Peu a Peu Fuel Loading Scheme in a 110 MWt Simplified Pebble Bed Reactor Reviewed

Dwi Irwanto, Toru Obara

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   48 ( 11 )   1385 - 1395   2011.11

Kinetic Analysis of Weakly Coupled Systems Using Probability Density Function of Coupling Coefficient Obtained by Monte Carlo Method Reviewed

Toru OBARA, Hiroki TAKEZAWA

Progress in Nuclear Science and Technology   2   263 - 266   2011.10

Polonium decontamination performance of stainless steel mesh filter for lead alloy-cooled reactors Reviewed

Toru Obara, Yu Yamazawa, Toshinobu Sasa

PROGRESS IN NUCLEAR ENERGY   53 ( 7 )   1056 - 1060   2011.9

Performance analysis of active carbon recycling energy system Reviewed

Yukitaka Kato, Toru Obara, Ichiro Yamanaka, Shinsuke Mori, Arnoldus Lambertus Dipu, Junichi Ryu, Yutaka Ujisawa, Masaaki Suzuki

PROGRESS IN NUCLEAR ENERGY   53 ( 7 )   1017 - 1021   2011.9

Synergistic Decomposition of CO2 by Hybridization of a Dielectric Barrier Discharge Reactor and a Solid Oxide Electrolyser Cell Reviewed

Yuki Tagawa, Shinsuke Mori, Masaaki Suzuki, Ichiro Yamanaka, Toru Obara, Junichi Ryu, Yukitaka Kato

KAGAKU KOGAKU RONBUNSHU   37 ( 2 )   114 - 119   2011

Calculation of the Integral Kinetic Model Transient Parameters by the Monte Carlo Method for Space-Dependent Kinetic Analysis Reviewed

Hiroki Takezawa, Toru Obara

NUCLEAR SCIENCE AND ENGINEERING   164 ( 1 )   80 - 86   2010.1

Development and testing of analytical models for the pebble bed type HTRs Reviewed

M. Q. Huda, T. Obara

ANNALS OF NUCLEAR ENERGY   35 ( 11 )   1994 - 2005   2008.11

Pulse reactor system for nuclear-pumped laser using low-enriched uranium Reviewed

Toru Obara, Hiroki Takezawa

ENERGY CONVERSION AND MANAGEMENT   49 ( 7 )   1892 - 1897   2008.7

Burnup analysis and in-core fuel management study of the 3MW TRIGA MARK II research reactor Reviewed

M.Q. Huda, S.I. Bhuiyan, T. Obara

Annals of Nuclear Energy   35 ( 1 )   141 - 147   2008.1

Polonium Evaporation and Adhesion Experiments for the Development of Polonium Filter in Lead-Bismuth Cooled Reactors Reviewed

Toru Obara, Takeru Koga, Terumitsu Miura, Hiroshi Sekimoto

Progress in Nuclear Energy   50   556 - 559   2008

Criticality analysis of pulse core and laser module coupled small reactor with low enriched uranium Reviewed

Hiroki Takezawa, Toru Obara, Andrey Gulevich, Oleg Kukharchuk

PROGRESS IN NUCLEAR ENERGY   50 ( 2-6 )   304 - 307   2008

Future of international cooperative activity for graduate school education in nuclear field Reviewed

Toru Obara

PROGRESS IN NUCLEAR ENERGY   50 ( 2-6 )   126 - 128   2008

Experimental verification of thermal decomposition of lead polonide Reviewed

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

ANNALS OF NUCLEAR ENERGY   34 ( 11 )   926 - 930   2007.11

Investigation of Polonium Decontamination from Stainless Steel Surfaces Using the Baking Method Reviewed

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Nuclear Technology   155 ( 1 )   78 - 89   2006.7

Fundamental study of polonium contamination by neutron irradiated lead–bismuth eutectic Reviewed

T. Obara, T. Miura, H. Sekimoto

Journal of Nuclear Materials   343 ( 1-3 )   297 - 301   2005.8

Development of polonium surface contamination measure in lead-bismuth eutectic coolant Reviewed

Toru Obara, Terumitsu Miura, Hiroshi Sekimoto

Progress in Nuclear Energy   47 ( 1-4 )   577 - 585   2005

Removal of polonium from stainless steel surface contaminated by neutron irradiated lead-bismuth eutectic Reviewed

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Progress in Nuclear Energy   47 ( 1-4 )   624 - 631   2005

Pb-Bi-cooled direct contact boiling water small reactor Reviewed

M Takahashi, S Uchida, K Hata, T Matsuzawa, H Osada, Y Kasahara, N Sawa, Y Okubo, T Obara, E Yusibani

PROGRESS IN NUCLEAR ENERGY   47 ( 1-4 )   190 - 201   2005

Unfolding of polonium distribution in depth of irradiated lead–bismuth eutectic from α-particle pulse-height distribution Reviewed

Terumitsu Miura, Toru Obara, Hiroshi Sekimoto

Applied Radiation and Isotopes   61 ( 6 )   1307 - 1311   2004.12

Measurement of keV-Neutron Capture Cross Sections and Capture Gamma-Ray Spectra of²⁰⁹Bi Reviewed

Kosuke SAITO, Masayuki IGASHIRA, Jun KAWAKAMI, Toshiro OHSAKI, Toru OBARA, Hiroshi SEKIMOTO

Journal of Nuclear Science and Technology   41 ( 4 )   406 - 412   2004.4

Preliminary study of the removal of polonium contamination by neutron-irradiated lead-bismuth eutectic Reviewed

Toru Obara, Terumitsu Miura, Yoshiyuki Fujita, Yasuo Ando, Hiroshi Sekimoto

Annals of Nuclear Energy   30 ( 4 )   497 - 502   2003.3

Effect of Low-Energy Resonance Absorber on Positive Neutron Temperature Coefficient of Dilute Plutonium-Water Solution Reviewed

Toru Obara, Hiroshi Sekimoto

Nuclear Science and Engineering   130 ( 3 )   386 - 390   1998.11

Concept and basic performance of an in-pile experimental reactor for fast breeder reactors using fast driver core Reviewed

Toru Obara, Hiroshi Sekimoto

Annals of Nuclear Energy   24 ( 18 )   1491 - 1513   1997.12

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 Reviewed

小原徹

1997

Design Concept of Fast Spectrum Pulse Reactor with Packed Core of Coated Dilute Fuel Particles Reviewed

Toru OBARA, Hiroshi SEKIMOTO

Journal of Nuclear Science and Technology   33 ( 7 )   547 - 554   1996.7

Feasibility of zero temperature coefficient core with highly diluted fuel and graphite moderator Reviewed

Toru Obara, Hiroshi Sekimoto

Annals of Nuclear Energy   22 ( 6 )   331 - 337   1995.6

Scientific feasibility of incineration in scnes Reviewed

H Akatsuka, T Ohsaki, T Obara, M Igashira, M Suzuki, Y Fujii-e

Progress in Nuclear Energy   29   477 - 484   1995.1

NEW NUMERICAL-METHOD FOR EQUILIBRIUM CYCLES OF HIGH CONVERSION PEBBLE BED REACTORS Reviewed

T OBARA, H SEKIMOTO

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   28 ( 10 )   947 - 957   1991.10

FUEL-MANAGEMENT EFFECTS ON INHERENT SAFETY OF MODULAR HIGH-TEMPERATURE REACTOR Reviewed

Y HIROSE, PH LIEM, E SUETOMI, T OBARA, H SEKIMOTO

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   26 ( 7 )   647 - 654   1989.7

NEW METHOD TO ANALYZE EQUILIBRIUM CYCLE OF PEBBLE-BED REACTORS Reviewed

H SEKIMOTO, T OBARA, S YUKINORI, E SUETOMI

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY   24 ( 10 )   765 - 772   1987.10

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 

BOOK OF PRESENTATIONS,Tokyo Tech COE-INES － Indonesia International Symposium 2005 "Prospect of Nuclear Energy in Indonesia"

ISBN4-903054-02-0 C3053  2006 

Plutonium vector analysis for optimizing the RFBB strategy applied for a nitride fuel, lead-cooled fast reactor Reviewed

Alexandru Catalin Stafie, Toru Obara

Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024)   1C-01-01   2024.10

Replication of CANDLE Burning Wave in Rotational Fuel-Shuffling Breed-and-Burn Fast Reactor Reviewed

Xucheng Zhao, Toru Obara

Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024)   1C-01-03   2024.10

Fuel Cycle Features of Sodium-Cooled Metal Fuel RFBBs Reviewed

T. Obara, N. Horiike

Proc. of International Conference on Nuclear Fuel Cycle (GLOBAL2024)   3C-01-03   2024.10

Feasibility of Innovative Lead-Bismuth-cooled Fast Reactor Core Design Using Metallic Fuel Reviewed

Xucheng Zhao, Toru Obara

Global Symposium on Lead and Lead Alloy Cooled Nuclear Energy Science and Technology 2024 (GLANST 2024)   2024.10

Issues and correspondence in the Global Nuclear Human Resource Development Initiative Project

Ken KUROSAKI, Tamotsu KOZAKI, Genichiro WAKABAYASHI, Toru OBARA

Proc. of 2024 autumn meeting of Atomic Energy Society of Japan   1L_PL05   2024.9

Burnup Characteristics of Silicide Fueled RFBB with Sodium Coolant

Toru Obara, Odmaa Sambuu

Proc. of 2024 autumn meeting of Atomic Energy Society of Japan   1G10   2024.9

小型モジュール炉開発の現状と展望 Reviewed

小原徹

化学工学   88 ( 5 )   207 - 210   2024.5

Start Up Core characteristics of Lead-cooled RFBB with Nitride Fuel

Ren Horikoshi, Toru Obara

Proc. of 2024 annual meeting of Atomic Energy Society of Japan   3L13   2024.3

Improvement of fuel debris criticality analysis technology using non-contact measurement method (4) Evaluation of the fuel debris criticality characteristics by using measurement system with active neutron method

Jun Nishiyama, Seiya Manabe, Hideki Harano, Toru Obara

Proc. of 2024 annual meeting of Atomic Energy Society of Japan   2L15   2024.3

Improvement of fuel debris criticality analysis technology using non-contact measurement method (6) Preliminary verification of a criticality impact analysis method using a fast-thermal weakly coupled reactor system

Hiroki Takezawa, Toru Obara

Proc. of 2024 annual meeting of Atomic Energy Society of Japan   2L17   2024.3

Improvement of fuel debris criticality analysis technology using non-contact measurement method (5) Performance Evaluation for a Fuel Debris Criticality Characterization System Using Active Neutron Method

Seiya Manabe, Jun Nishiyama, Hideki Harano, Toru Obara

Proc. of 2024 annual meeting of Atomic Energy Society of Japan   2L16   2024.3

Core Characteristics of Sodium Cooled RFBB with Metal Fuel

Naoki Horiike, Toru Obara

Proc. of 2024 annual meeting of Atomic Energy Society of Japan   3L12   2024.3

Feasibility of silicide fueled RFBB using lead coolant

Xiaoqing Huang, Toru Obara

Proc. of 202４ annual meeting of Atomic Energy Society of Japan   3L11   2024.3

Feasibility of RFBBs with Silicide Fuel and Sodium Coolant Reviewed

Odmaa Sambuu, HoangVan Khanh, Toru Obara

Transactions of the American Nuclear Society   129 ( 1 )   896 - 899   2023.11

Preliminary analysis of GODIVA supercritical transient behaviors by using the Multi-region Integral Kinetic code including delayed neutron effect Reviewed

Hiroki Takezawa, Toru Obara

The 12th International Conference on Nuclear Criticality Safety (ICNC2023)   TR8   2023.10

Development of the fuel debris criticality characteristics measurement system, Reviewed

Jun Nishiyama, Seiya Manabe, Hideki Harano, Toru Obara

The 12th International Conference on Nuclear Criticality Safety (ICNC2023)   SS1   2023.10

Neutronics - thermal hydraulics behavior of inclined offshore floating BWR

Kodai Fukuda, Kenya Suyama, Toru Obara

Proc. of 2023 autumn meeting of Atomic Energy Society of Japan   1H16   2023.9

Feasibility of a small RFBB concept with lead coolant and nitride fuel

Alexandru Catalin Stafie, Jun Nishiyama, Toru Obara

Proc. of 2023 autumn meeting of Atomic Energy Society of Japan   1H13   2023.9

Small sodium-cooled RFBB with nitride fuel and LBE Reflectors

Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara

Proc. of 2023 autumn meeting of Atomic Energy Society of Japan   1H14   2023.9

Preliminary verification of criticality impact analysis code applicable to weakly coupled systems including fuel debris particles,

Hiroki Takezawa, Toru Obara

The 7th International Forum on Fukushima Daiichi NPS Decommissioning   C03   2023.8

Improvement of criticality calculation speed in fuel debris falling down in water

Takuya Miura, Jun Nishiyama, Toru Obara

Proc. of 2023 annual meeting of Atomic Energy Society of Japan   3K07   2023.3

Improvement of fuel debris criticality analysis technology using non-contact measurement method(2) Fundamental experiment for development of the fuel debris criticality characteristics measurement system

Seiya Manabe, Jun Nishiyama, Hideki Harano, Toru Obara

Proc. of 2023 annual meeting of Atomic Energy Society of Japan   3K04   2023.3

Start Up Core of Rotational Fuel Shuffling Breed-and-Burn Fast Reactor

Ren Horikoshi, Jun Nishiyama, Toru Obara

Proc. of 2023 annual meeting of Atomic Energy Society of Japan   2L05   2023.3

Improvement of fuel debris criticality analysis technology using non-contact measurement method (3) Improvement of criticality impact analysis method for weakly coupled systems of fuel debris

Hiroki Takezawa, Toru Obara

Proc. of 2023 annual meeting of Atomic Energy Society of Japan   3K05   2023.3

Improvement of fuel debris criticality analysis technology using non-contact measurement method(1) Design of the fuel debris criticality characteristics measurement system

Jun Nishiyama, Seiya Manabe, Hideki Harano, Toru Obara

Proc. of 2023 annual meeting of Atomic Energy Society of Japan   3K03   2023.3

Concept of lead-cooled rotational fuel-shuffling breed-and-burn fast reactor Reviewed

Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama, Toru Obara

Transactions of the American Nuclear Society   127   1052 - 1054   2022.11

Criticality Analysis of Fuel Debris Falling in Water Considering Water Surface Oscillation Reviewed

Toru Obara, Taro Fumimoto, Takeshi Muramoto, Jun Nishiyama

Transactions of the American Nuclear Society   127   740 - 741   2022.11

Impact of fuel cladding design on neutron balance and radiation damage of cladding in Breed-and-Burn fast reactor

Toru Obara, Odmaa Sambuu, Van Khanh Hoang, Jun Nishiyama

Proc. of 2022 autumn meeting of Atomic Energy Society of Japan   2F10   2022.9

Burnup analysis of Rotational Fuel-shuffling Breed-and-Burn fast reactor with lead-bismuth coolant

Xucheng Zhao, Jun Nishiyama, Toru Obara

Proc. of 2022 autumn meeting of Atomic Energy Society of Japan   2F12   2022.9

Feasibility of rotational shuffling Breed-and-Burn fast reactor with nitride fuel and sodium coolant

Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara

Proc. of 2022 autumn meeting of Atomic Energy Society of Japan   2F11   2022.9

小型モジュール型原子炉開発の動向 Reviewed

小原徹

圧力技術   60 ( 3 )   34 - 39   2022.5

Impact of Core Materials on the Fuel Cladding Irradiation Damage in Breed-and-Burn Fast Reactors Reviewed

S. ODMAA, J. NISHIYAMA, V.Kh.HOANG, T.OBARA

International Conference on Fast Reactors and Related Fuel Cycles FR22 (CN291), IAEA-CN-291   393   2022.4

IMPACT OF CLADDING MATERIAL ON NEUTRONIC BALANCE IN BREED-AND-BURN FAST REACTORS Reviewed

T. OBARA, O. SAMBUU, V.K. HOANG, J. NISHIYAMA

International Conference on Fast Reactors and Related Fuel Cycles FR22 (CN291), IAEA-CN-291   397   2022.4

Feasibility of rotational fuel shuffling lead cooled Breed-and-Burn fast reactor

Toru Obara, Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama

Proc. of 2022 Annual meeting of Atomic Energy Society of Japan   1D06   2022.3

Toward construction of cross-organizational education system for nuclear engineering: activities of global nuclear human resource development initiative program by MEXT (3) Activity in International Group Meeting

Toru Obara

Proc. of 2022 Annual meeting of Atomic Energy Society of Japan   1L_PL03   2022.3

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-

小原 徹, 西山 潤, 竹澤宏樹

JAEA-Review 2021-027   2022.1

Criticality safety analysis using MPS method for fuel debris falling into water

西山潤, 文元太郎, 村本武司, 竹澤宏樹, 小原徹

KURNS-EKR (Web)   ( 14 )   30 - 39   2022

Conceptual design of rotational fuel shuffling sodium cooled Breed-and-Burn fast reactor

Toru Obara, Van Khanh Hoang, Odmaa Sambuu, Jun Nishiyama

Proc. of 2021 Autumn meeting of Atomic Energy Society of Japan   3K13   2021.9

先進次世代原子炉の多角的研究

小原徹

炉物理の研究   73   2021.3

Effect of neutron Generation Time on Supercritical Transient Analysis in Fuel Debris during Falling Down in Water

Kodai Fukuda, Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of 2021 Annual meeting of Atomic Energy Society of Japan   2B05   2021.3

Criticality safety analysis in fuel debris falling down simulation using MPS in real scale geometry

Taro Fumimoto, Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of 2021 Annual meeting of Atomic Energy Society of Japan   2021.3

Criticality safety analysis of fuel debris by Japan-Russia international joint study

Toru Obara, Jun Nishiyama, Takeshi Muramoto, Taro Fumimoto, Hiroki Takezawa, Anton D. Smirnov, Ekaterina V. Bogdanova, Pavel A. Pugachev, Ivan S. Saldikov, Mikhail Yu. Ternovykh, Georgy V. Tikhomirov

Proc. of 2021 Annual meeting of Atomic Energy Society of Japan   2B02   2021.3

Study on Criticality Accidents Analysis by Ramp Reactivity Insertion using Multi-region Integral Kinetic code

Kodai Fukuda, Jun Nishiyama, Toru Obara

Proc. of 2020 Autumn meeting of Atomic Energy Society of Japan   2H02   2020.9

Design concept of the sodium cooled small CANDLE burning reactor

Hoang Hai Nguyen, Jun Nishiyama, Toru Obara

Proc. of 2020 Autumn meeting of Atomic Energy Society of Japan   1K09   2020.9

Development of Criticality Evaluation Method of Fuel Debris Bed Formation Process by Falling in Water -Modeling of Granular Fuel Debris Shape by Parameter Calibration of Particle Method Applying Optimization Method-

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of 2020 Autumn meeting of Atomic Energy Society of Japan   2H01   2020.9

SMR開発の展望

小原徹

日本原子力学会誌   62 ( 3 )   25 - 26   2020.3

Criticality Safety Evaluation of Powder Fuel Debris using DEM and MPS Method”

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of 2020 Annual meeting of Atomic Energy Society of Japan,   1I02   2020.3

Minor actinides transmutation technology optimization methods

Sergei Ryzhov, Georgy Tikhomirov, Toru Obara

Proc. of 2020 Annual meeting of Atomic Energy Society of Japan   3H02   2020.3

Possibility of Sodium Cooled Breed and Burn Fast Reactor with Rotational Fuel

Aronne Travaglia, Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Proc. of 2020 Annual meeting of Atomic Energy Society of Japan   1H03   2020.3

Criticality calculations of fuel debris in various conditions during falling down

Anton Smirnov, Ekaterina Bogdanova, Georgy Tikhomirov, Hiroki Takezawa, Jun Nishiyama, Toru Obara

Proc. of 2020 Annual meeting of Atomic Energy Society of Japan   1I01   2020.3

Radiolysis gas reactivity feedback effect on prompt supercritical transient analysis of fuel debris

Kodai Fukuda, Jun Nishiyama, Toru Obara

Proc. of 2020 Annual meeting of Atomic Energy Society of Japan   1I04   2020.3

Characteristics of spent fuel from breed and burn fast reactor

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Proc. of 2020 Annual meeting of Atomic Energy Society of Japan   3H06   2020.3

Development of a Monte Carlo based code system for CANDLE burning analysis Reviewed

Hoang Hai Nguyen, Jun Nishiyama, Toru Obara

Proc. of SNA+MC2020   MC03-4, No. 3238578   2020

Monte Carlo Based Analysis for CANDLE Burning Reactor Reviewed

Hoang Hai Nguyen, Jun Nishiyama, Toru Obara

Proc. of Reactor Physics Asia Conference 2019 (RPHA19)   RPHA19-1088   2019.12

Thermal Hydraulic Analysis for a Breed and Burn Core with Spiral Fuel Shuffling Reviewed

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Proc. of Reactor Physics Asia Conference 2019 (RPHA19)   RPHA19-1087   2019.12

Development of Integral Kinetic Model with Delayed Neutrons Effect for Criticality Accident Analysis of Fukushima Daiichi NPP Fuel Debris Reviewed

Hiroki Takezawa, Delgersaikhan Tuya, Toru Obara

Proc. of Reactor Physics Asia Conference 2019 (RPHA19)   RPHA19-1085   2019.12

Development of Criticality Safety Evaluation Method Based on the Actual Dynamic Behavior of the Fuel Debris in Water Reviewed

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of Reactor Physics Asia Conference 2019 (RPHA19)   RPHA19-1091   2019.12

Radiation Dose by Criticality Accidents of Fuel Debris in Water Reviewed

Kodai Fukuda, Jun Nishiyama, Toru Obara

Proc. of Reactor Physics Asia Conference 2019 (RPHA19)   RPHA19-1092   2019.12

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-

小原徹

エネルギーレビュー   39 ( 11 )   9 - 10   2019.10

Reactor Physics in SMR development

Toru Obara

Proc. of 2019 autumn meeting of Atomic Energy Society of Japan   1J_PL01   2019.9

Numerical analysis of criticality of fuel debris falling in water by coupling computational fluid dynamics and the continuous energy Monte Carlo code Reviewed

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety   A93049MT   2019.9

Supercritical kinetic analysis in a simple fuel debris system by MIK code Reviewed

Kodai Fukuda, Delgersaikhan Tuya, Jun Nishiyama, Toru Obara

Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety   A93242KF   2019.9

Development of super critical transient MIK code and its application to GODIVA core Reviewed

Toru Obara, Delgersaikhan Tuya

Proc. of ICNC2019 – 11th International Conference on Nuclear Criticality Safety   A93237TO   2019.9

Impact of Fuel and Coolant Material on Burnup Characteristics in Breed and Burn Fast Reactor

Suzuko Saito, Jun Nishiyama, Toru Obara

Proc. of 2019 annual meeting of Atomic Energy Society of Japan   1K10   2019.3

Solution of the neutronic fast reactor benchmark with Serpent-CriMR code system

Anton Smirnov, Pavel Pugachev, Vladislav Romanenko, Georgy Tikhomirov, Toru Obara

Proc. of 2019 annual meeting of Atomic Energy Society of Japan   1K16   2019.3

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

小原徹

日本原子力学会誌   61 ( 1 )   70 - 72   2019

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

小原徹

原子力バックエンド研究   25 ( 2 )   71 - 78   2018.12

MIK - Multi-region Integral Kinetic code, Version 1.0

Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara

2018.12

Core Design Improvement of Small CANDLE Reactor with the Melt-Refining Process Reviewed

Van Khanh Hoang, Jun Nishiyama, Toru Obara

Transactions of the American Nuclear Society   119   1079 - 1082   2018.11

廃炉基盤技術と人材育成

小原 徹

エネルギーレビュー   38 ( 10 )   16 - 20   2018.10

Compensation for Fuel Losses in The Melt-Refining Process in Small CANDLE Reactor

Van Khanh Hoang, Jun Nishiyama, Toru Obara

Proc. of 2018 autumn meeting of Atomic Energy Society of Japan   3L09   2018.9

巻頭言 炉物理は大事だから

小原徹

炉物理の研究   ( 70 )   2018.3

Radiation Dose by Super Critical Condition of Fuel Debris in Water

Kodai Fukuda, Toru Obara, Jun Nishiyama

Proc. of 2018 annual meeting of Atomic Energy Society of Japan   2F09   2018.3

Criticality safety analysis in falling down of fuel debris in water

Takeshi Muramoto, Jun Nishiyama, Toru Obara

Proc. of 2018 annual meeting of Atomic Energy Society of Japan   2F07   2018.3

Possibility of Breed and Burn Reactor with Spiral Fuel Shuffling

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Proc. of 2018 annual meeting of Atomic Energy Society of Japan,   3F03   2018.3

Initial Core Design of CANDLE Bruning Fast Reactor Using Plutonium from LWR Spent Fuel Reviewed

Hiroki Osato, Jun Nishiyama, Toru Obara

Transactions of the American Nuclear Society   117   1485 - 1486   2017.10

Feasibility of Bruning Wave Reactor with Continuous Fuel Movement Reviewed

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Transactions of the American Nuclear Society   117   1101 - 1104   2017.10

Supercritical Kinetic Analysis of Accumulated Fuel Debirs in the Fukushima-Daiichi NPS Reviewed

Toru Obara, Delgersaikhan Tuya

Transactions of the American Nuclear Society   117   851 - 852   2017.10

Effect of Compensating for Fuel Losses in Melt and Refining Process for Small CANDLE Reactor Reviewed

Van Khanh Hoang, Jun Nishiyama, Toru Obara

Transactions of the American Nuclear Society   117   1487 - 1488   2017.10

Introduction of MOX and Pu-ROX fuels in PBR with accumulative fuel loading scheme

Irwan Liapto Simanullang, Toru Obara

Proc. of 2017 fall meeting of Atomic Energy Society of Japan   3H14   2017.9

Feasibility of Breed and Burn reactor with spiral pattern fuel movement

Jun Nishiyama, Kazuki Kuwagaki, Toru Obara

Proc. of 2017 fall meeting of Atomic Energy Society of Japan   3H17   2017.9

Burnup analysis of CANDLE bruning reactor by Monte Carlo based method

Hoang Hai Nguyen, Jun Nishiyama, Toru Obara

v   2017.9

Preliminary Study of Burning Wave Reactor with Continuous Fuel Movement Reviewed

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Proc. of the Reactor Physics Asia 2017 (RPHA17) Conference   2017.8

New Approach of Space-dependent Kinetic Analysis Invited

Toru Obara

The Reactor Physics Asia 2017 Conference (RPHA17)   2017.8

Feasibility of Burning Wave Fast Reactor Concept with Rotational Fuel Shuffling Reviewed

Toru Obara, Kazuki Kuwagaki, Jun Nishiyama

Proceedings of International Conference of Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17)   IAEA-CN245-051   2017.6

Effect of homogenization of breeding zone in small CANDLE burning reactor with melt and refining process Reviewed

Van Khanh Hoang, Jun Nishiyama, Toru Obara

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP2017)   17696   2017.4

Concept of small CANDLE reactor with melt and refining process Reviewed

Toru Obara, Van Khanh Hoang, Jun Nishiyama

Proceedings of 2017 International Congress on Advances in Nuclear Power Plants (ICAPP2017)   17739   2017.4

Feasibility of Breed and Burn Reactor with Continuous Fuel Moving

Kazuki Kuwagaki, Jun Nishiyama, Toru Obara

Proc. of 2017 annual meeting of Atomic Energy Society of Japan   3F16   2017.3

CANDLE Burning Reactor with Plutonium Fuel Start-up Core Reviewed

Toru Obara, Jun Nishiyama, Hiroki Osato

Transactions of the American Nuclear Society   115   1319 - 1320   2016.11

Study on CANDLE Burning Reactor with Initial Core Using Plutonium from LWR Spent Fuel Reviewed

Hiroki Osato, Jun Nishiyama, Toru Obara

Abstracts of the fifth International symposium on Innovative Nuclear Energy Systems (INES-5)   A11-2   2016.10

Design Parameters in an Annular, Prismatic HTGR for Passive Decay Heat Removal” Abstracts of the fifth International symposium on Innovative Nuclear Energy Systems (INES-5) Reviewed

Odmaa Sambuu, Enkhbaatar Ganbold, Jamyansuren Terbish, Toru Obara, Norov Nanzad, Munkhbat Byambajav

Abstracts of the fifth International symposium on Innovative Nuclear Energy Systems (INES-5)   A21-3   2016.10

Utilization of Burnable Poison Particles in UO2 and ROX Fuels in Pebble Bed Reactor with Accumulative Fuel Loading Scheme Reviewed

Irwan Liapto Simanullang, Toru Obara

Abstracts of the fifth International symposium on Innovative Nuclear Energy Systems (INES-5)   A21-1   2016.10

Concept of Burning Wave Reactor with Rotational Fuel Shuffling Reviewed

Toru Obara, Kazuki Kuwagaki, Jun Nishiyama

Abstracts of the fifth International symposium on Innovative Nuclear Energy Systems (INES-5)   A13-5   2016.10

Impact of Neutron Spectrum Shift on Breed and Burn Reactor Concept Reviewed

Van Khanh Hoang, Toru Obara

Abstracts of the fifth International symposium on Innovative Nuclear Energy Systems (INES-5)   A12-5   2016.10

Study on Optimization of Early Stage CANDLE Burnup Characteristics Reviewed

Jun Nishiyama, Masato Tanaka, Toru Obara

Abstracts of The fifth International Symposium on Innovative Nuclear Energy Systems (INES-5)   A11-4   2016.10

CANDLE BURNING FAST REACTOR CONCEPT WITH MELT AND REFINING PROCESS Reviewed

Obara T., Abdul Karim J., Hoang V. K., Nishiyama J.

Book of abstracts of International Scientific and Technical Conference, Innovative Designs and Technologies of Nuclear Power IV (IV ISTC NIKIET-2016)   75 - 76   2016.9

Optimization of Small CANDLE Burn-up Reactor for Space Nuclear Power

Jun Nishiyama, Toru Obara

Proc. of 2016 autumn meeting of Atomic Energy Society of Japan   1L11   2016.9

Introduction of rock-like oxide fuel in PBR with accumulative fuel loading

Irwan Liapto Simanullang, Jun Nishiyama, Toru Obara

Proc. of 2016 autumn meeting of Atomic Energy Society of Japan   1L08   2016.9

Thermal Hydraulic Analysis on CANDLE Burning Reactor with Initial Core Using Plutonium from LWR Spent Fuel

Hiroki Osato, Jun Nishiyama, Toru Obara

Proc. of 2016 autumn meeting of Atomic Energy Society of Japan   1L12   2016.9

Supercritical transient analysis in light water moderated coupled small fuel debris regions using integral kinetic model and point kinetic model

Tuya Delgersaikhan, Jun Nishiyama, Toru Obara

Proc. of 2016 autumn meeting of Atomic Energy Society of Japan   1H12   2016.9

The Center of World Intelligence Project for Nuclear S&T and Human Resource Development, Human Resource Development and Research Program for Decommissioning of Fukushima Daiichi NPS (Nuclear Power Station) (2)-Tokyo Institute of Technology "Advanced Research and Education Program for Nuclear Decommissioning" Implementation Status –

Isamu Sato, Toru Obara, Toyohiko Yano, Kenji Takeshita, Yukitaka Kato, Hiroshi Akatsuka, Hiroshige Kikura, Takehiko Tsukahara, Katsumi Yoshida, Gen Endo, Koichiro Takao, Masayuki Harada, Saishun Yamazaki, Nobuyuki Iwatsuki, Koichi Suzumori, Noriko Asanuma, Tsuyoshi Arai, Kenji Kawashima, Naoyuki Takaki

Proc. of 2016 autumn meeting of Atomic Energy Society of Japan   3M02   2016.9

The Center of World Intelligence Project for Nuclear S&T and Human Resource Development, Human Resource Development and Research Program for Decommissioning of Fukushima Daiichi NPS (Nuclear Power Station) (1)- Outline of Activity -

Toru Obara, Koji Okamoto, Nobuyoshi Hara, Yoshinari Anoda, Seichi Sato, Yoshitaka Takagai, Ikuo Towhata, Isamu Sato

Proc. of 2016 autumn meeting of Atomic Energy Society of Japan   3M01   2016.9

OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements; (4)Burnup performance in molten salt coolant

Hai Ho Quan, Toru Obara

Proc. of 2016 annual meeting of Atomic Energy Society of Japan   3O11   2016.3

Study on Small CANDLE Burn-up Reactor for Space Nuclear Power

Jun Nishiyama, Toru Obara

Proc. of 2016 annual meeting of Atomic Energy Society of Japan   3O14   2016.3

Application of Melt Refining of Metal Fuel to CANDLE Reactor; (3)Effects of Cooling Time during Melt and Refining Procedures

Julia AbdulKarim, Jun Nishiyama, Toru Obara

Proc. of 2016 annual meeting of Atomic Energy Society of Japan   2016.3

Statistical Uncertainty in Kinetic Analysis using Integral Kinetic Model for Re-criticality Accident in Weakly-Coupled Fuel Debris

Delgersaikhan Tuya, Hiroki Takezawa, Toru Obara

Proc. of 2016 annual meeting of Atomic Energy Society of Japan   1O13   2016.3

A Method for Passive Reduction in Criticality of Fuel Debris Dust

Hiroki Takezawa, Toru Obara

Proc. of 2016 annual meeting of Atomic Energy Society of Japan   3E07   2016.3

Optimization of initial fuel composition for Small Pebble Bed Reactor with accumulative fuel loading scheme; (2) Use of burnable poison

Irwan Liapto Simanullang, Toru Obara

Proc. of 2016 annual meeting of Atomic Energy Society of Japan   3O10   2016.3

PROMPT SUPERCRITICAL KINETIC ANALYSIS WITH NEUTRON COUPLING BETWEEN FUEL DEBRIS Reviewed

Toru Obara, Hiroki Takezawa, Delgersaikhan Tuya

Proceedings of International Conference on Nuclear Criticality Safety (ICNC2015)   1431 - 1438   2015.11

Application of the Melt and Refining Procedure to the CANDLE Reactor Concept Reviewed

Julia Abdul Karim, Jun Nishiyama, Toru Obara

Transactions of the American Nuclear Society   113   924 - 926   2015.11

Composition of ROX Fuel for High-Burnup Pebble Bed Reactor Reviewed

Hai Quan Ho, Toru Obara

Transactions of the American Nuclear Society   113   922 - 923   2015.11

Burnup Analysis of Accumulative Fuel Loading Scheme Pebble Bed Reactor with Optimum Fuel Composition Reviewed

Irwan Liapto Simanullang, Toru Obara

Transactions of the American Nuclear Society   113   919 - 921   2015.11

Kinetic Analysis of Weakly Coupled Fuel Debris by Integral Kinetic Model Reviewed

Delgersaikhan Tuya, Toru Obara, Hiroki Takezawa

Transactions of the American Nuclear Society   113   1158 - 1160   2015.11

Fission Probability Density Functions for Kinetic Analysis in Weakly Coupled Fuel Debris Reviewed

Toru Obara, Delgersaikhan Tuya, Hiroki Takezawa

Transactions of the American Nuclear Society   113   1150 - 1152   2015.11

Kinetic Analysis of Re-criticality Accident in Simplified System of Fuel Debris and Consolidated Fuel

Delgersaikhan Tuya, Toru Obara

Proc. of 2015 autumn meeting of Atomic Energy Society of Japan   A22   2015.9

Application of Melt Refining of Metal Fuel to CANDLE Reactor (2) Effects of noble and reactive fission gasses removal to the burnup performance

Julia ABDULKARIM, Jun NISHIYAMA, Toru OBARA

Proc. of 2015 autumn meeting of Atomic Energy Society of Japan   D21   2015.9

Optimization of Initial Fuel Composition for Small Pebble Bed Reactor with Accumulative Fuel Loading Scheme (1)Reduction of Fuel Enrichment

Irwan Liapto, SIMANULLANG, Toru OBARA

Proc. of 2015 autumn meeting of Atomic Energy Society of Japan   D23   2015.9

OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements (3) Optimization of the core parameters and analysis of temperature coefficient

Hai Quan Ho, Toru Obara

Proc. of 2015 autumn meeting of Atomic Energy Society of Japan   D24   2015.9

Comparison on design parameter criteria of prismatic HTGR and PBR for passive decay heat removal

Odmaa Sambuu, Toru Obara

Proc. of 2015 autumn meeting of Atomic Energy Society of Japan   D25   2015.9

Effects of Neutron Spectrum Shift on Burnup Performance of a Breed and Burn Reactor

Van Khanh Hoang, Toru Obara

Proc. of 2015 autumn meeting of Atomic Energy Society of Japan   D28   2015.9

Design Concept Study for Innovative High Temperature Gas-Cooled Reactors Reviewed

Toru Obara, Dwi Irwanto, Tomonori Nakashima, Taiki Onoe, Piyatida Trinuruk, Topan Setiadipura, Sambuu Odmaa, Hai Quan Ho, Irwan Liapto Simanullang

Proceedings of the Reactor Physics Asia 2015 (RPHA15) Conference   12DAIR2-1   2015.9

IMPACT ON BURNUP PERFORMANCE OF COATED PARTICLE FUEL DESIGN IN PEBBLE BED REACTOR WITH ROX FUEL Reviewed

Hai Quan Ho, Toru Obara

Proceedings of ICONE-23, 23th International Conference on Nuclear Engineering   ICONE23-1651   2015.5

Fission Probability Density Functions for Super Prompt Criticality Accident Analysis in Weakly Coupled Systems by Integral Kinetic Model Reviewed

Toru Obara, Delgersaikhan Tuya, Haruka Kikuchi

Proceedings of ICONE-23, 23th International Conference on Nuclear Engineering   ICONE23-1618   2015.5

Application of Integral Kinetic Model to Transient Analysis of Different Types of Weakly Coupled Systems Reviewed

Delgersaikhan Tuya, Haruka Kikuchi, Toru Obara

Proceedings of ICONE-23, 23th International Conference on Nuclear Engineering   ICONE23-1626   2015.5

CORE TEMPERATURE COEFFICIENT OF SMALL LONG-LIFE HTGR FOR PASSIVE DECAY-HEAT REMOVAL Reviewed

Odmaa Sambuu, Toru Obara

Proceedings of ICONE-23, 23th International Conference on Nuclear Engineering   ICONE23-1625   2015.5

IMPROVEMENT OF BURNUP ANALYSIS FOR PEBBLE BED REACTORS WITHANACCUMULATIVE FUEL LOADING SCHEME Reviewed

Irwan Liapt Simanullang, Toru Obara

Proceedings of ICONE-23, 23th International Conference on Nuclear Engineering   ICONE23-1627   2015.5

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

小原徹, Delgersaikhan Tuya

日本原子力学会2015春の年会予稿集   J23   2015.3

OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements (2) Optimization of the fuel composition

Hai Quan Ho, Toru Obara

Proc. of 2015 annual meeting of Atomic Energy Society of Japan   J44   2015.3

Design parameter condition of PBR for passive decay heat removal

Odmaa Sambuu, Toru Obara

Proc. of 2015 annual meeting of Atomic Energy Society of Japan   J43   2015.3

Study on Criticality Safety Transient Analysis in Weakly Coupling System (3) Effects of fuel composition and geometry on two-tank system

J26   2015.3

The Criticality Accident Analysis of Melted Debris by Integral Kinetic Model (2) Preliminary Analysis for Two-Unit Systems Reviewed

Delgersaikhan Tuya, Toru Obara

Proc. of 2015 annual meeting of Atomic Energy Society of Japan   J24   2015.3

OTTO cycle Small Pebble Bed Reactor with Rock-like fuel elements (1) Burnup analysis in equilibrium condition

Hai Quan Ho, Topan Setiadipura, Toru Obara

Proc. of 2014 autumn meeting of Atomic Energy Society of Japan   L20   2014.9

CANDLE 燃焼実験炉の設計研究 (Design study on experimental CANDLE burn-up reactor)

西山潤, 小原徹

日本原子力学会2014秋の大会予稿集   H44   2014.9

Suppression of Excess Reactivity of Small Long-Life Prismatic HTGR with Passive Decay-Heat Removal Reviewed

Odmaa Sambuu, Toru Obar

Proc. of PHYSOR 2014   2014.9

Transient Analysis in Super Critical Condition for Several Fuel-Solution Tanks System with Different Layout Reviewed

Haruka Kikuchi, Toru Obara

Proc. of PHYSOR 2014   2014.9

Optimum Start-up Procedure in OTTO Cycle Pebble Bed Reactor

Topan Setiadipura, Toru Obara

Proc. of 2014 annual meeting of Atomic Energy Society of Japan   K17   2014.3

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

菊池遼, 小原徹

日本原子力学会2014年春の年会予稿集   O33   2014.3

CANDLE炉における初期燃焼特性の最適化に関する研究

田中真人, 小原徹, 西山潤

日本原子力学会2014年春の年会予稿集   K23   2014.3

Systematic Study of a Small, Long-life HTGR Design for Passive Decay-Heat Removal Reviewed

Odmaa Sambuu, Toru Obara

Transactions of the American Nuclear Society   111   1359 - 1362   2014

Optimization of Start-Up Fuel Management for OTTO Cycle Pebble Bed Reactor Reviewed

Topan Setiadipura, Toru Obara

Abstracts of The fourth International Symposium on Innovative Nuclear Energy Systems (INES-4)   A22-5   2013.11

Comparative study on HTGR Designs for Passive Decay Heat Removal Reviewed

Sambuu Odmaa, Toru Obara

Abstracts of The forth International Symposiuim on Innovative Nuclear Energy Systems (INES-4)   A22-4   2013.11

Activities in CRINES for Generation IV International Forum, Lead-cooled Fast Reactor

Minoru TAKAHASHI, Toru OBARA, Akio MINATO, Shoji UCHIDA, Kenji KIKUCHI, Masatoshi KONDO, Akito NAGATA

Abstracts of The fourth International Symposium on Innovative Nuclear Energy Systems (INES-4)   A11-3   2013.11

Start-up analysis of the CANDLE burn-up reactors by using accelerator neutron sources Reviewed

Jun Nishiyama, Toru Obara

Abstracts of The fourth International Symposium on Innovative Nuclear Energy Systems (INES-4)   A13-3   2013.11

Population inversion distribution in laser gas medium in Reactor Pumped Laser Reviewed

Toru Obara, Yosuke Isobe

Abstracts of The fourth International Symposium on Innovative Nuclear Energy Systems (INES-4)   A13-6   2013.11

“Development of Transient Analysis Code for Estimation of Total Released Energy in Several Fuel Solution Tanks System Reviewed

Haruka Kikuchi, Toru Obara

Abstracts of The fourth International Symposium on Innovative Nuclear Energy Systems (INES-4)   C13-1   2013.11

Particle-type Burnable Poisons for Thorium-based Fuel in HTGR Reviewed

Piyatida Trinuruk, Toru Obara

Abstracts of The fourth International Symposium on Innovative Nuclear Energy Systems (INES-4)   A22-3   2013.11

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

西山潤, 小原徹

日本原子力学会2013秋の大会予稿集   G04   2013.9

Preventing the Prompt Critical Accident in Block-type HTGRs by using Particle Type Burnable Poisons

Piyatida Trinuruk, Toru Obara

Proc. of 2013 autumn meeting of Atomic Energy Society of Japan   G33   2013.9

Preliminary Study for Refueling Scheme in Lead-Bismuth Eutectic Cooled CANDLE Reactor

Toru Obara, Hiroyuki Nakamura, Jun Nishiyama

The fourth conference on Heavy Liquid-metal Coolants in Nuclear Technologies (HLMC-2013)   2013.9

Development of a Monte Carlo based PBR Fuel Management Code Reviewed

Topan Setiadipura, Toru Obara

Transactions of the American Nuclear Society   109   1431 - 1433   2013

Energy Release in Criticality Accidents Involving Two Fuel Solution Tanks Reviewed

Toru Obara, Haruka Kikuchi

Transactions of the American Nuclear Society   109   888 - 889   2013

High-burnup core design using minor actinide-containing metal fuel Reviewed

Ohta, H., Ogata, T., Obara, T.

Proc. of International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads   1   759 - 765   2013

Burnup Performance of Small Pebble Bed Reactor with Accumlative Fuel Loading Scheme Reviewed

Toru Obara, Dwi Irwanto

Proceedings of 6th International Topical Meeting on High Temperature Reactor Technology HTR2012   HTR2012-5-019   2012.10

Prismatic HTGR with Silicon Carbide Coated Graphite Block Core（1）Effects on Thermal-Hydraulic Behavior under the Normal Operation

Piyatida Trinuruk, Toru Obara

Proc. of 2012 autumn meeting of Atomic Energy Society of Japan   P41   2012.9

加速器中性子源点化型CANDLE燃料炉に関する研究

西山潤, 小原徹

日本原子力学会2012秋の大会予稿集   P35   2012.9

Concept of Small Pebble Bed Reactor with Accumulative Fuel Loading Scheme Invited

Toru Obara

Third International Ulaanbaatar Conference on Nuclear Physics and Applications UBC2012   2012.9

Design Study of Innovative Simplified Small Pebble Bed Reactor;（5）Passive Safety Analysis for Decay Heat Removal without Forced Cooling

Dwi Irwanto, Toru Obara

Proc. of 2012 annual meeting of Atomic Energy Society of Japan   C38   2012.3

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

磯部陽介, 小原徹

日本原子力学会2012春の年会予稿集   D51   2012.3

慣性核融合炉用原子炉レーザーの設計研究

友成健人, 小原徹

日本原子力学会2012春の年会予稿集   D50   2012.3

Neutronic Analysis of Prismatic HTGR with Silicon Carbide Coated Graphite Block Core

Piyatida Trinuruk, Toru Obara

Proc. of 2012 annual meeting of Atomic Energy Society of Japan   D09   2012.3

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

尾上泰基, 小原徹

日本原子力学会2012春の年会予稿集   D08   2012.3

Design study on a small reactor for silicon semiconductor production using LWR fuel；(4) Uniformity of doping

Byambajav Munkhba, Toru Obara

Proc. of 2012 annual meeting of Atomic Energy Society of Japan   D06   2012.3

Validation of Depletion Module of Equilibrium Burnup Analysis Code for OTTO Cycle in Pebble Bed Reactor

Topan Setiadipura, Toru Obara

Proc. of 2012 annual meeting of Atomic Energy Society of Japan   C39   2012.3

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 Invited

小原 徹

触媒,第109回触媒討論会,2012年3月28日～29日,東京工業大学, 1A05   54 ( 2 )   70   2012

Effect of SiC Coating over Graphite Structure in HTGR Reviewed

Piyatida Trinuruk, Toru Obara

Transactions of the American Nuclear Society   107   1262 - 1263   2012

Effect of Particle Type Burnable Poisons in HTGR Reviewed

Toru Obara, Taiki Onoe

Transactions of the American Nuclear Society   107   1023 - 1024   2012

Conceptual design of a small nuclear reactor for NTD-Si using short PWR fuel assemblies Reviewed

Byambajav Munkhba, Toru Obara

Transactions of the American Nuclear Society   106   826 - 829   2012

Possibility of nuclear pumped laser experiment using low enriched uranium Reviewed

Toru Obara, Hiroki Takezawa

AIP Conf. Proceedings, The 3rd International Conference on Advance in Nuclear Science and Engineering 2011: ICANSE 2011   25 - 29   2012

Preliminary Study on the Burnup Improvement of HTGR based on the Spectrum Reviewed

Piyatida Trinuruk, Toru Obara

Proc. of GLOBAL 2011   500728   2011.12

Preliminary study of small district heating reactor with passive safety feature Invited

Toru Obara, Odmaa Sambuu

ICANSE-2011: International Conference on Advances in Nuclear Science and Engineering 2011   2011.11

Reduction of Spent Fuel by Optimization of Fuel Composition in Simplified Pebble Bed Reactor Invited

Toru Obara, Dwi Irwanto

Technical Meeting On Fuel and Fuel Cycle for Small and Medium Range Reactors   2011.10

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-

小原 徹

原子力eye   57 ( 6 )   56 - 59   2011.6

Study on Concept of Innovative Nuclear Reactors and Nucler Safety

Toru OBARA

Bulletin of the Research Laboratory for Nuclear Reactors   35   65 - 65   2011

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

菊池 遼, 小原 徹

日本原子力学会2011秋の大会予稿集   N27   2011

Development of Equilibrium Burnup Analysis Code for OTTO Cycle in Pebble Bed Reactor

Topan Setiadipura, Toru Obara

Proc. of 2011 annual meeting of Atomic Energy Society of Japan   G20   2011

Effect on Burnup Performance in HTGR by Neutron Spectrum Shift

Piyatida Trinuruk, Toru Obara

Proc. of 2011 annual meeting of Atomic Energy Society of Japan   G19   2011

Design Study of Innovative Simplified Small Pebble Bed reactor; (3) Analysis of the 110MWt Simplified PBR Design with Peu a Peu fuel loading scheme

Dwi Irwanto, Toru Obara

Proc. of 2011 annual meeting of Atomic Energy Society of Japan   I34   2011

Design study on small reactor for silicon semiconductor production using LWR fuel; (3) Optimization of burnable poison

Byambajav Munkhba, Toru Obara

Proc. of 2011 autumn meeting of Atomic Energy Society of Japan   O43   2011

モンゴルでの小型地域熱供給用原子炉の予備的解析

Sambuu Odmaa, 小原 徹

日本原子力学会2011秋の大会予稿集   O41   2011

Study of SiC Components to Improve the Neutron Economy in HTGR

Piyatida Trinuruk, Toru Obara

Proc. of 2011 autumn meeting of Atomic Energy Society of Japan   N31   2011

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 Schem

Dwi Irwanto, Toru Obara

Proc. of 2011 autumn meeting of Atomic Energy Society of Japan   N30   2011

Design Concept of Small District Heating Reactor for Mongolia Reviewed

Odmaa Sambuu, Toru Obara

Transactions of the American Nuclear Society   105   1160 - 1161   2011

Spectrum Shift with Silicon Carbide Block in HTGR Reviewed

Piyatida Trinuruk, Toru Obara

Transactions of the American Nuclear Society   105   1103 - 1104   2011

Burnup Characteristics of Thorium Fuel in a Small PBR with Pea-a-Peu Feul-Loading Scheme Reviewed

Dwi Irwanto, Toru Obara

Transactions of the American Nuclear Society   105   1105 - 1106   2011

Conceptional Design of a Small Nuclear Reactor for Large-Diameter NTD-Si Using a PWR Fuel Reviewed

Byambajav Munkhba, Toru Obara

Transactions of the American Nuclear Society   105   1123 - 1124   2011

Supercritical Transinet Analysis in Weakly Coupling Systems Reviewed

Haruka Kikuchi, Toru Obara

Transactions of the American Nuclear Society   105   535 - 536   2011

Design study on small reactor for silicon semiconductor production using LWR fuel; (2) Reactor optimization

Byambajav Munkhba, Toru Obara

Proc. of 2011 annual meeting of Atomic Energy Society of Japan   G27   2011

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究

菊池 遼, 小原 徹

日本原子力学会2011春の年会予稿集   I46   2011

Design Concept of Small Reactor for Larger Diameter neutron Transmutation Doping using Conventional PWR Fuel Assemblies Reviewed

Munkhbat BYAMBAJAV, Toru Obara

The Third International Symposium on Innovative Nuclear Energy Systems   P-108   2010.10

2-dimensional Core Temperature Profile During Operation in Th Small Simplified Pebble Bed Reactor with Peu a Peu Fuel Loading Reviewed

Dwi IRWANTO, Toru OBARA, Yukitaka KATO, Ichiro YAMANAKA

The Third International Symposium on Innovative Nuclear Energy Systems   P-113   2010.10

Kinetic Analysis of Weakly Coupled Systems Using Probability Density Function of Coupleing Coefficient Obtained by Monte Carlo Reviewed

Toru OBARA, Hiroki TAKEZAWA

Proc. of Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo Method, 2010(SNA+MC2010)   10258   2010.10

Decontamination Efficency of Metal Mesh Plonium Filter for Lead Alloy Cooled Reactors Reviewed

Toru Obara, Yu Yamazawa

The Third International Symposium on Innovative Nuclear Energy Systems   1B-34   2010.10

Burnup Analysis of a Peu a Peu Feul-loading Scheme in a Pebble Bed Reactor Using the Monte Carlo Method Reviewed

Dwi Irwanto, Toru Obara

Proc. of Joint International Conference on Supercomputing in Nuclear Applications and Monte Carlo 2010(SNA+MC2010)   10190   2010.10

Study on Neutron Transmutation Doping for Sillicon Semiconductor using PWR Fuel Core,

Toru OBARA, Byambajav MUNKHBAT

Bulletin of the Research Laboratory for Nuclear Reactors   34   70 - 70   2010

Study on Numerical Simulation of Nuclear Pumped Laser by Coupled Pulse Reactor

Toru OBARA, Hiroki TAKEZAWA

Bulletin of the Research Laboratory for Nuclear Reactors   34   69 - 69   2010

Study on Peu-a-Peu Fuel Loading Scheme in Small PBR

Toru OBARA, Dwi Irwanto

Bulletin of the Research Laboratory for Nuclear Reactors   34   70 - 70   2010

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

竹澤宏樹, 小原 徹

日本原子力学会2010年春の年会予稿集   H31   2010

Desing Stury on Nuclear Reactor for Large Diameter NTD Using PWR Fuel Reviewed

Byambajav Munkhba, Toru Obara

Transactions of the American Nuclear Society   103   756   2010

Burnup Characteristics of Peu-a-Peu Fuel Loading Scheme in Small PBR Reviewed

Dwi IRWANTO, Toru OBARA, Yukitaka KATO, Ichiro YAMANAKA

Transactions of the American Nuclear Society   103   791   2010

Small Reactor For Semiconductor Production By Neutron Transmutation Doping Reviewed

Toru Obara, Liem Peng Hong

Proc. of The 2’nd International Conference on Advances in Nuclear Science and Engineering 2009-ICANSE2009   15 - 18   2010

Kinetic Analysis of Coupled Pulse Reactor for NPL Experiment Reviewed

Toru Obara, Hiroki Takezawa

Transactions of the American Nuclear Society   103   775   2010

Design study on small reactor for semiconductor production using LWR fuel ; (1) Reactor Concept

Byambajav Munkhba, Toru Obara

Proc. of 2010 annual meeting of Atomic Energy Society of Japan   2010

Design Study of Innovative Simplified Small Pebble Bed reactor; (2) Steady State Thermal Hydraulic Analysis of Reference Design

Dwi IRWANTO, Toru OBARA

Proc. of 2010 autumn meeting of Atomic Energy Society of Japan   Q22   2010

Preliminary Study of Burnup Characteristics for a Simplified Small Pebble Bed Reactor Reviewed

Dwi Irwanto, Yukikata Kato, Ichiro Yamanaka, Toru Obara

Proc. of The 2’nd International Conference on Advances in Nuclear Science and Engineering 2009-ICANSE2009   27 - 30   2010

国際的な原子力教育における日本の役割

小原 徹

電気協会報   ( 1019 )   16 - 19   2009.10

Fundamental Analysis of Graphite Moderated Reactor for Laser Propulsion by Nuclear-Pumped Laser Reviewed

Toru Obara, Junichiro Otani

14th International Conference on Emerging Nuclear Energy Systems (ICENES-2009)   2009.6

Concept of Small Reactor for Neutron Transmutation Doping using PWR Type Fuel Elements Reviewed

Toru Obara, Liem Peng Hong, Hideki Yagi

Proc. of 2009 International Congress on Advances in Nuclear Power Plants (ICAPP’09)   9039   2009.5

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

Liem Peng Hong, 小原 徹, 八木秀樹

本原子力学会2009年春の年会予稿集   L49   2009

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

竹澤宏樹, 小原 徹

日本原子力学会2009年春の年会予稿集   K06   2009

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

竹澤宏樹, 小原 徹

日本原子力学会2009年秋の大会予稿集   F36   2009

Study on Calculation Methods for Effective Delayed Neutron Fraction

Dwi Irwanto, Toru Obara, Go Chiba

Proc. of 2009 annual meeting of Atomic Energy Society of Japan   k30   2009

Design Study of Innovative Simplified Small Pebble Bed Reactor; (1) Design Concept and Sample Design Analysis

Dwi Irwanto, Toru Obara

Proc. of 2009 autumn meeting of Atomic Energy Society of Japan   F34   2009

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

小原 徹, Liem Peng Hong, 八木秀樹

日本原子力学会2009年春の年会予稿集   L48   2009

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

大谷純一朗, 小原 徹

日本原子力学会2009年春の年会予稿集   K07   2009

Integral Kinetic Model for Weakly Coupled Systems

Hiroki Takezawa, Toru Obara

Bulletin of the Research Laboratory for Nuclear Reactors   32   63 - 63   2008.12

Development of Nuclear Reactor

Toru OBARA

The First International Forum on Multidisciplinary Education and Research for Energy Science,   2008.12

Fundamental Study for Polonium Issue in Lead-Bismuth Cooled Reactors

Toru Obara, Termitsu Miura, Takeru Koga, Hiroshi Sekimoto

Proc. of The Third Conference on Heavy Liquid-Metal Coolants in Nuclear Technologies (HLMC-2008)   2   467 - 471   2008.9