| Published Papers |
| No. | Ｔitle | Journal | Vol | No | Start Page | End Page | Publication date | DOI | Referee |
| 1 | Optimal size of beryllium pebbles as a neutron multiplier - helium recoil calculations aiming for swelling reduction and new proposal of neutron multiplier for advanced high-temperature tritium breeding blanket | NUCLEAR MATERIALS AND ENERGY | 47 | | | | Jun. 2026 | https://doi.org/10.1016/j.nme.2026.1021061 | Refereed |
| 2 | Feasibility study on the production of 229Th as a long-life 225Ac generator using the experimental fast reactor Joyo | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 63 | 2 | 154 | 165 | Feb. 1, 2026 | https://doi.org/10.1080/00223131.2025.25582441 | Refereed |
| 3 | Breed and burn reactor concept to maximize uranium utilization without fuel shuffling | Progress in Nuclear Science and Technology | 7 | | 14 | 19 | Mar. 31, 2025 | https://doi.org/10.15669/pnst.7.141 | Refereed |
| 4 | Status of the 226Ra nuclear data library and its impact on the production amount of 225Ac via the 226Ra (n,2n) reaction  | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 61 | 2 | 251 | 260 | Feb. 1, 2024 | https://doi.org/10.1080/00223131.2023.22950181 | Refereed |
| 5 | Semi-Permanent Mass Production of Ac-225 for Cancer Therapy by the (3n,x) Reaction in Pressurized Water Reactor | Processes | 12 | 1 | | | Dec. 29, 2023 | https://doi.org/10.3390/pr120100831 | Refereed |
| 6 | Evaluation of the production amount of 225Ac and its uncertainty through the 226Ra(n,2n) reaction in the experimental fast reactor Joyo | Journal of Nuclear Science and Technology | 61 | 4 | 1 | 12 | Aug. 21, 2023 | https://doi.org/10.1080/00223131.2023.22439411 | Refereed |
| 7 | Study on Improvement of Burnup Performance of SMR by Using Thorium | Prod. of International Congress on Advances in Nuclear Power Plants (ICAPP), April 23–27, 2023 | | | | | Apr. 2023 | | Refereed |
| 8 | Value of advanced reactor development reflecting social trend Values and issues in developing advanced reactors that contribute to solve issues of energy security and radioactive waste | ΑΤΟΜΟΣ | 65 | 6 | 378 | 382 | 2023 | https://doi.org/10.3327/jaesjb.65.6_3781 | Refereed |
| 9 | State of the art and perspective of innovative light water reactors | 配管技術 | 65 | 5 | | | 2023 | | |
| 10 | Neutronic Study on Ac-225 Production for Cancer Therapy by (n,2n) Reaction of Ra-226 or Th-230 Using Fast Reactor Joyo | PROCESSES | 10 | 7 | | | Jul. 2022 | https://doi.org/10.3390/pr100712391 | Refereed |
| 11 | Design study of 208Pb-Bi eutectic-cooled reactor with natural uranium as fuel cycle input with radial fuel shuffling | ANNALS OF NUCLEAR ENERGY | 171 | | | | Jun. 15, 2022 | https://doi.org/10.1016/j.anucene.2022.1090031 | |
| 12 | Design of Cesium target assembly with YH<inf>2</inf> moderator and Gd thermal neutron shielding to produce 135Cs for LLFP transmutation study using the experimental fast reactor Joyo | Annals of Nuclear Energy | 166 | | | | Feb. 2022 | https://doi.org/10.1016/j.anucene.2021.1088301 | Refereed |
| 13 | Performance indices optimization of long-lived fission products transmutation in fast reactors | INTERNATIONAL JOURNAL OF ENERGY RESEARCH | 46 | 2 | 1327 | 1338 | Feb. 2022 | https://doi.org/10.1002/er.72501 | Refereed |
| 14 | Core depletion analysis of long-life CANDLE gas-cooled fast reactor using OpenMC code | AIP Conference Proceedings | 2374 | | | | Jul. 23, 2021 | https://doi.org/10.1063/5.00589061 | Refereed |
| 15 | Initial core design analysis of lead (208) -bismuth eutectic-cooled reactor with radial fuel shuffling | International Journal of Energy Research | 45 | 8 | 12317 | 12324 | Jun. 25, 2021 | https://doi.org/10.1002/er.64761 | Refereed |
| 16 | Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant | Nuclear Engineering and Technology | 53 | 2 | 423 | 429 | Feb. 2021 | https://doi.org/10.1016/j.net.2020.07.0081 | Refereed |
| 17 | Archives after 10 Years since the Nuclear Accident and Resolutions for the Future; What the TEPCO Decommissioning Archive Center Conveys | The Journal of The Institute of Electrical Engineers of Japan | 141 | 1 | 4 | 8 | Jan. 1, 2021 | https://doi.org/10.1541/ieejjournal.141.41 | Not refereed |
| 18 | Preliminary investigation on the sodium fast reactor concave cores with near-zero or negative sodium void reactivity | International Journal of Energy Research | 44 | 10 | 8025 | 8036 | Aug. 1, 2020 | https://doi.org/10.1002/er.49131 | Refereed |
| 19 | A fast reactor transmutation system for 6 LLFP nuclides | Nuclear Engineering and Design | 363 | | | | Jul. 2020 | https://doi.org/10.1016/j.nucengdes.2020.1106671 | Refereed |
| 20 | Feasibility study on oxide/molten salt-fueled CANDU reactor with two regions bundles | GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water Reactor Fuel Performance Conference | | | 264 | 268 | 2020 | | Refereed |
| 21 | Study on method to achieve high transmutation of LLFP using fast reactor | Scientific Reports | 9 | 1 | 19156 | 19156 | Dec. 1, 2019 | https://doi.org/10.1038/s41598-019-55489-w1 | Refereed |
| 22 | Core concept of simultaneous transmutation of six LLFP nuclides using a fast reactor | Nuclear Engineering and Design | 352 | | | | Oct. 2019 | https://doi.org/10.1016/j.nucengdes.2019.1102081 | Refereed |
| 23 | Conceptual design of direct 99mTc production facility at the high temperature engineering test reactor | Nuclear Engineering and Design | 352 | | | | Oct. 2019 | https://doi.org/10.1016/j.nucengdes.2019.1101741 | Refereed |
| 24 | Convex shaped FBR core with graded size pins to prevent re-criticality during Core Disruptive Accident | Annals of Nuclear Energy | 127 | | 364 | 371 | May. 2019 | https://doi.org/10.1016/j.anucene.2018.12.0221 | Refereed |
| 25 | Study on transmutation system of LLFP using fast reactors | Transactions of the American Nuclear Society | 121 | | 1511 | 1513 | 2019 | https://doi.org/10.13182/T307591 | |
| 26 | Conceptual study on recriticality prevention core having duplex pellets with neutron absorber in outer core in a fast reactor | Science and Technology of Nuclear Installations | 2019 | | | | 2019 | https://doi.org/10.1155/2019/27537891 | Refereed |
| 27 | Geometry survey on the convex shaped core for recriticality prevention against CDA in sodium-cooled fast reactor | International Conference on Nuclear Engineering, Proceedings, ICONE | 1 | | | | 2018 | https://doi.org/10.1115/ICONE26-813311 | Refereed |
| 28 | The development status of Generation IV reactor systems(6): Molten salt reactor and thorium reactor | Journal of the Atomic Energy Society of Japan | 60 | 8 | 493 | 498 | 2018 | https://doi.org/10.3327/jaesjb.60.8_4931 | Not refereed |
| 29 | Publisher Correction: Method to Reduce Long-lived Fission Products by Nuclear Transmutations with Fast Spectrum Reactors. | Scientific reports | 7 | 1 | 17270 | 17270 | Dec. 5, 2017 | https://doi.org/10.1038/s41598-017-17100-y1 | Refereed |
| 30 | Role of Multichance Fission in the Description of Fission-Fragment Mass Distributions at High Energies | Physical Review Letters | 119 | 22 | | | Nov. 27, 2017 | https://doi.org/10.1103/PhysRevLett.119.2225011 | Refereed |
| 31 | Thermal-hydraulic Feasibility Study of a Convex shaped Fast Reactor Core | Energy Procedia | 131 | | 86 | 93 | 2017 | https://doi.org/10.1016/j.egypro.2017.09.4531 | Refereed |
| 32 | Core geometry for recriticality prevention against CDA in sodium-cooled fast reactor | Energy Procedia | 131 | | 45 | 52 | 2017 | https://doi.org/10.1016/j.egypro.2017.09.4441 | |
| 33 | Study on the technology for enhancing element value by neutron transmutation in light water reactors | Transactions of the American Nuclear Society | 116 | | 1013 | | 2017 | | |
| 34 | 2B09 Development of a Human Resources for Nuclear Engineering in Tokyo City University:Programs in Safety Engineering and Teaching Effectiveness in Cooperative Major in Nuclear Engineering | Proceedings of Annual Conference of Japanese Society for Engineering Education | 2017 | 0 | 188 | 189 | 2017 | https://doi.org/10.20549/jseeja.2017.0_1881 | Not refereed |
| 35 | Fission fragments mass distributions of nuclei populated by the multinucleon transfer channels of the 18O + 232Th reaction | Physics Letters, Section B: Nuclear, Elementary Particle and High-Energy Physics | 761 | | 125 | 130 | Oct. 10, 2016 | https://doi.org/10.1016/j.physletb.2016.08.0101 | |
| 36 | トクシュウ イマ 、 ナゼ"モ ンジュ"ナ ノ カ : 30ネンゴ ノ エネルギー ノ オオキナ センタクシ ノ ヒトツ | | 36 | 8 | 20 | 24 | 2016 | | |
| 37 | Study on core radius minimization for long life Pb-Bi cooled CANDLE burnup scheme based fast reactor | AIP Conference Proceedings | 1677 | | | | Sep. 30, 2015 | https://doi.org/10.1063/1.49307941 | |
| 38 | Accident analysis of heavy water cooled thorium breeder reactor | AIP Conference Proceedings | 1656 | | | | Apr. 2015 | https://doi.org/10.1063/1.49171331 | |
| 39 | Fission Study of Actinide Nuclei Using Multi-nucleon Transfer Reactions | Physics Procedia | 64 | | 140 | 144 | 2015 | https://doi.org/10.1016/j.phpro.2015.04.0181 | |
| 40 | Post-accident defueling procedure and its criticality safety evaluation of the Fukushima-Daiichi nuclear power plants | Proceedings of the International Conference on Physics of Reactors, PHYSOR 2014 | | | | | 2014 | | |
| 41 | Start-up fuel and power flattening of sodium-cooled candle core | International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads | 1 | | 790 | 797 | 2013 | | |
| 42 | Accuracy of thorium cross section of JENDL-4.0 library in thorium based fuel core evaluation | Annals of Nuclear Energy | 57 | | 173 | 178 | 2013 | https://doi.org/10.1016/j.anucene.2013.01.0561 | |
| 43 | Cost impact evaluation of introduction of above 5% enrichment fuel | Transactions of the Atomic Energy Society of Japan | 11 | 2 | 118 | 126 | Jun. 2012 | https://doi.org/10.3327/taesj.J11.0141 | Not refereed |
| 44 | Verification study of thorium cross section in MVP calculation of thorium based fuel core using experimental data | International Conference on the Physics of Reactors 2012, PHYSOR 2012: Advances in Reactor Physics | 3 | | 2605 | 2613 | 2012 | | |
| 45 | Decay heat analysis of thorium fuel used in a light water reactor | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 145 | 145 | 2012 | https://doi.org/10.11561/aesj.2012f.0.145.01 | |
| 46 | Core design and deployment strategy of heavy water cooled sustainable thorium reactor | Sustainability | 4 | 8 | 1933 | 1945 | 2012 | https://doi.org/10.3390/su40819331 | |
| 47 | Preliminary engineering design of sodium-cooled CANDLE core | AIP Conference Proceedings | 1448 | | 29 | 38 | 2012 | https://doi.org/10.1063/1.47254351 | |
| 48 | Core loading pattern optimization of thorium fueled heavy water breeder reactor using genetic algorithm | International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 | 3 | | 1581 | 1587 | 2012 | | |
| 49 | Feasibility study on the thorium fueled boiling water breeder reactor | International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 | 2 | | 1072 | 1076 | 2012 | | |
| 50 | Reactor physics ideas for large scale utilization of thorium in gas cooled reactors | Progress in Nuclear Energy | 53 | 7 | 814 | 819 | Sep. 2011 | https://doi.org/10.1016/j.pnucene.2011.05.0281 | |
| 51 | Breeding and void reactivity analysis on heavy metal closed-cycle water cooled thorium reactor | Annals of Nuclear Energy | 38 | 2-3 | 337 | 347 | Feb. 2011 | https://doi.org/10.1016/j.anucene.2010.10.0091 | |
| 52 | Deployment scenario of heavy water cooled thorium breeder reactor | AIP Conference Proceedings | 1244 | | 109 | 120 | 2010 | https://doi.org/10.1063/1.34627481 | |
| 53 | Symbiotic systems consisting of large-FBR and small water-cooled thorium reactors (WTR) | Annals of Nuclear Energy | 36 | 8 | 1076 | 1085 | Aug. 2009 | https://doi.org/10.1016/j.anucene.2009.05.0091 | |
| 54 | A feasible core design of lead bismuth eutectic cooled CANDLE fast reactor | Annals of Nuclear Energy | 36 | 5 | 562 | 566 | May. 15, 2009 | https://doi.org/10.1016/j.anucene.2009.01.0071 | |
| 55 | All heavy metals closed-cycle analysis on water-cooled reactors of uranium and thorium fuel cycle systems | International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 | 2 | | 1485 | 1492 | 2009 | | |
| 56 | Education of nuclear engineering in Tokai University survives and revives - Challenge for encouragement to master of nuclear enaineers | Atomos | 51 | 7 | 546 | 550 | 2009 | https://doi.org/10.3327/jaesjb.51.7_5461 | Not refereed |
| 57 | Breeding and plutonium characterization analysis on actinides closed water-cooled thorium reactor | International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 | 3 | | 1988 | 1995 | 2009 | | |
| 58 | Breeding capability and void reactivity analysis of heavy-water-cooled thorium reactor | Journal of Nuclear Science and Technology | 45 | 7 | 589 | 600 | Jul. 2008 | https://doi.org/10.1080/18811248.2008.97114571 | |
| 59 | Potential of CANDLE reactor on sustainable development and strengthened proliferation resistance | Progress in Nuclear Energy | 50 | 2-6 | 114 | 118 | Mar. 2008 | https://doi.org/10.1016/j.pnucene.2007.10.0111 | |
| 60 | Performance of natural uranium- and thorium-fueled fast breeder reactors (FBRs) for 233U fissile production | Progress in Nuclear Energy | 50 | 2-6 | 290 | 294 | Mar. 2008 | https://doi.org/10.1016/j.pnucene.2007.11.0741 | |
| 61 | Preliminary study on feasibility of large and small water cooled thorium breeder reactor in equilibrium states | Progress in Nuclear Energy | 50 | 2-6 | 320 | 324 | Mar. 2008 | https://doi.org/10.1016/j.pnucene.2007.11.0141 | |
| 62 | Power density effect on feasibility of water cooled thorium breeder reactor | Progress in Nuclear Energy | 50 | 2-6 | 308 | 313 | Mar. 2008 | https://doi.org/10.1016/j.pnucene.2007.11.0131 | |
| 63 | Actinide closed water cooled thorium breeder reactor | International Conference on the Physics of Reactors 2008, PHYSOR 08 | 2 | | 1541 | 1546 | 2008 | | |
| 64 | Breeding and void reactivity performances of different driver fuel on water cooled thorium reactor | Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work" | 4 | | 2487 | 2495 | 2008 | | |
| 65 | Basic concept of water moderated small reactor for neutron transmutation doping | Transactions of the American Nuclear Society | 99 | | 745 | 746 | 2008 | | |
| 66 | Feasible region of design parameters for water cooled thorium breeder reactor | Journal of Nuclear Science and Technology | 44 | 7 | 946 | 957 | Jul. 2007 | https://doi.org/10.1080/18811248.2007.97113341 | |
| 67 | Parametric survey for benefit of partitioning and transmutation technology in terms of high-level radioactive waste disposal | Journal of Nuclear Science and Technology | 44 | 3 | 398 | 404 | Mar. 2007 | https://doi.org/10.1080/18811248.2007.97113001 | |
| 68 | Feasibility of water cooled thorium breeder reactor based on LWR technology | GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems | | | 1733 | 1738 | 2007 | | |
| 69 | Feasibility study of self sustaining capability on water cooled thorium reactors for different power reactors | 13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007 | 1 | | 392 | 422 | 2007 | | |
| 70 | Impact of different moderator ratios with light and heavy water cooled reactors in equilibrium states | Annals of Nuclear Energy | 33 | 7 | 561 | 572 | May. 2006 | https://doi.org/10.1016/j.anucene.2006.02.0131 | |
| 71 | Design feasible area on water cooled thorium breeder reactor in equilibrium states | International Conference on Nuclear Engineering, Proceedings, ICONE | 2006 | | | | 2006 | https://doi.org/10.1115/ICONE14-893951 | |
| 72 | Systems of symbiotic large FBRs and small CANDLE-Thorium-HTGRs | PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics | 2006 | | | | 2006 | | |
| 73 | Cell configuration effect on feasibility of water cooled thorium breeder reactor | PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics | 2006 | | | | 2006 | | |
| 74 | Iodine transmutation studies using metal iodide targets | Journal of Nuclear Materials | 334 | 2-3 | 149 | 158 | Sep. 1, 2004 | https://doi.org/10.1016/j.jnucmat.2004.05.0121 | |
| 75 | Neutronic potential of water cooled reactor with actinide closed fuel cycle | Progress in Nuclear Energy | 37 | 1-4 | 223 | 228 | 2000 | https://doi.org/10.1016/s0149-1970(00)00050-01 | |
| 76 | Effect of decontamination factor of recycled actinide and FP on the characteristics of scnes | Progress in Nuclear Energy | 32 | 3-4 | 441 | 447 | 1998 | https://doi.org/10.1016/s0149-1970(97)00051-61 | |
| 77 | Toxicity of radioactive wastes discharged from nuclear energy center in the future equilibrium state | Annals of Nuclear Energy | 23 | 8 | 663 | 668 | May. 1996 | https://doi.org/10.1016/0306-4549(95)00031-31 | |
| 78 | Feasibility of Fast Fission System Confining Long-Lived Nuclides | Journal of Nuclear Science and Technology | 29 | 3 | 276 | 283 | 1992 | https://doi.org/10.3327/jnst.29.2761 | |
| 79 | Preliminary Study on Future Society in Nuclear Quasi-Equilibrium | Journal of Nuclear Science and Technology | 28 | 10 | 941 | 946 | Oct. 1991 | https://doi.org/10.3327/jnst.28.9411 | |
| 80 | Evaluation of Neutron Nuclear Data for Z>88 Minor Nuclides | Journal of Nuclear Science and Technology | 27 | 9 | 853 | 861 | 1990 | https://doi.org/10.3327/jnst.27.8531 | |
| MISC |
| No. | Ｔitle | Journal | Vol | No | Start Page | End Page | Publication date |
| 1 | Feasibility study on medical radioisotope production using ABWRs | 日本原子力学会秋の大会予稿集(CD-ROM) | 2025 | | | | 2025 |
| 2 | Planning of activation experiment of trace Hg for nuclear alchemy demonstration at JRR-3 | 日本原子力学会秋の大会予稿集(CD-ROM) | 2025 | | | | 2025 |
| 3 | Conceptual design of Be moderated thermal breeder reactor using natural-uranium disk-shaped fuel | 日本原子力学会春の年会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 4 | A neutronic study on a feasibility of Geo-Reactor in protoEarth period | 日本原子力学会春の年会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 5 | Preliminary study on nuclear propulsion spacecraft using electromagnetic launcher | 日本原子力学会春の年会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 6 | Conceptual core design for large high speed cargo submarine | 日本原子力学会春の年会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 7 | Neutronic Analysis of the Burnability of Geo-Reactor in the Proto-Earth Period | 日本原子力学会秋の大会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 8 | Conceptual design of a long-life small lunar reactor using slightly enriched uranium | 日本原子力学会秋の大会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 9 | Comparative assessment of doses to cancer tumors and normal tissues delivered by αand βemitters considering detachment from ligands in TRT | 日本原子力学会秋の大会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 10 | Nuclear×Space: Possibilities and prospects of space nuclear technology | 日本原子力学会秋の大会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 11 | Production of Ac-225 by multiple irradiation of Ra-226 in LWR | 日本原子力学会春の年会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 12 | Conceptual Design of a Neutron Propulsion Engine for Deep Space Exploration | 日本原子力学会秋の大会予稿集(CD-ROM) | 2024 | | | | 2024 |
| 13 | Conceptual design of high neutron flux irradiation reactor with tight-pitch annular core | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 14 | Study on the effect of inner blanket with inner moderator on the reduction of sodium void reactivity in FBR | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 15 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (1) Research Objectives and Summaries | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 16 | R&D Trends for Water-Cooled Thorium Reactors | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 17 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (8) Neutronic and thermal hydraulic characteristics evaluation on Ac-225 production in PWR | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 18 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (4) Development of 99Mo/99mTc Production Process | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 19 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (3) Concept study of Mo/Tc production using PWR power plant (2) | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 20 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (2) 99Mo and 225Ac pharmaceuticals market environment analysis | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 21 | Conceptual design of a long-life small reactor for the lunar surface using micro-enriched uranium | 宇宙科学技術連合講演会講演集(CD-ROM) | 67th | | | | 2023 |
| 22 | Neutronic analysis of the feasibility of Geo-Reactor in a proto-Earth period | Abstracts of Annual Meeting of the Geochemical Society of Japan | 70 | | 159 | | 2023 |
| 23 | Innovative Reactor Development Inviting Next-Generation Nuclear Engineers | 日本原子力学会春の年会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 24 | Production of Cf-252 neutron source for non-destructive inspection using nuclear reactor | 日本原子力学会春の年会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 25 | Study on MA bearing metallic fuel fast breeder reactor with low void reactivity and recriticality prevention characteristics | 日本原子力学会春の年会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 26 | Feasibility study on pin-type molten salt fast breeder reactor | 日本原子力学会春の年会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 27 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (6) Ac purification and Ra reuse processes in Ac-225 production using fast reactor | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 28 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (7) Manufacturing conditions for medical use of 225Ac | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 29 | Conceptual design of Be moderated thermal breeder reactor using natural uranium fuel | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 30 | R&D on Medical RI production using domestic nuclear infrastructures to achieve self-preparedness (2) (5) RI production using the experimental fast reactor Joyo | 日本原子力学会秋の大会予稿集(CD-ROM) | 2023 | | | | 2023 |
| 31 | Core characteristics and generation cost evaluation of heavy-water-cooled reduced-moderation thorium breeder reactor with radial and axial blankets | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 32 | Evaluation of Ac-225 production by reduced moderation water reactor using light water or heavy water as coolant | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 33 | 230ThO2 target irradiation behavior and optimization of irradiation conditions during Ac-225 production by PWR | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 34 | Neutronic characteristics of coated particle thorium-fueled LWR | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 35 | Core Characteristics and Deployment Scenario of Sustainable Reduced Moderation Thorium Reactor | KURNS-EKR (Web) | | 14 | | | 2022 |
| 36 | Medical RI Production Using Domestic Nuclear Infrastructures for Self-Sustenance (4) Experimental Consideration of 99Mo / 99mTc Production Process | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 37 | Medical RI production using domestic nuclear infrastructures for self-sustenance (7) Ac-225 production using commercial PWR | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 38 | Medical RI production using domestic nuclear infrastructures for self-sustenance (6) Study of Ra/Ac separation method in Ac-225 production using fast reactor | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 39 | Medical RI production using domestic nuclear infrastructures for self-sustenance (1) Overall scope and plan | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 40 | Medical RI production using domestic nuclear infrastructures for self-sustenance (3) Concept study of Mo/Tc production using PWR power plant | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 41 | Medical RI production using domestic nuclear infrastructures for self-sustenance (2) Japan market size estimation on Ac225 radiopharmaceuticals | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 42 | Core design of MOX-fueled reduced-moderation water reactor for marine use | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 43 | Direct energy conversion of radiations emitted from nuclear wastes | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 44 | Medical RI production in existing reactors (2) Optimization of neutron spectrum field for Mo/Tc production in the experimental fast reactor Joyo | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 45 | Values and issues in developing advanced reactors that can contribute to the solution of energy security and radioactive waste issues | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 46 | Medical RI production in existing reactors (1) Ac-225 production in the core center/reflector region of the experimental fast reactor Joyo | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 47 | Consideration of reactivity decrease by assembling fuel assemblies in a heavy water-cooled reduced-moderation reactor | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 48 | Medical RI production in existing reactors (2) Comparison of medical RI production performances in Joyo and PWR | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 49 | Study of Design Domain and Simplified Thrust Evaluation of Alpha Particle Propulsion Engine for Deep Space Exploration | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 50 | Simplified reprocessing and synthetic wave CANDLE burning method to maximize uranium resource utilization | 日本原子力学会秋の大会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 51 | Medical RI production using domestic nuclear infrastructures for self-sustenance (5) Ac-225 production using the experimental fast reactor Joyo | 日本原子力学会春の年会予稿集(CD-ROM) | 2022 | | | | 2022 |
| 52 | Study on plutonium consumption performance and generation cost of BWR using thorium fuel | 日本原子力学会秋の大会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 53 | Conceptual design of ultra compact RTG for deep space exploration | 日本原子力学会秋の大会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 54 | Conceptual design of small-sized space power reactor cooled by natural circulation with centrifugal force | 宇宙科学技術連合講演会講演集(CD-ROM) | 65th | | | | 2021 |
| 55 | Numerical Simulation of Water Flow inside a Nuclear Reactor for Spacecraft and its Coolability Estimation | 宇宙科学技術連合講演会講演集(CD-ROM) | 65th | | | | 2021 |
| 56 | Fuel debris renewal concept (2) Potential evaluation on supply of medical and/or industrial radioisotopes made from fuel debris | 日本原子力学会春の年会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 57 | Fuel Debris Renewal Concept (1) Basic concept on practical use of radioisotopes and valuable resources recovered from fuel debris | 日本原子力学会春の年会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 58 | Conceptual design of metallic-fueled high-flux fast irradiation reactor with low fuel cost | 日本原子力学会秋の大会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 59 | Conceptual Study of an Alpha Particle Propulsion Engine for Deep Space Exploration | 日本原子力学会秋の大会予稿集(CD-ROM) | 2021 | | | | 2021 |
| 60 | Feasibility of I-129 transmutation by in-core loading in Fast Breeder Reactor | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 61 | Feasibility study on chloride salt fast breeder reactor using spent fuel from light water reactor | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 62 | Research and development of an innovative transmutation system of LLFP by fast reactors (3) Characteristics of a fast reactor core for nuclear transmutation and an irradiation test plan | 日本原子力学会春の年会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 63 | Research and development of an innovative transmutation system of LLFP by fast reactors (4) Candidates of transmutation target and their properties | 日本原子力学会春の年会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 64 | Research and development of an innovative transmutation system of LLFP by fast reactors (1) Research Plan of the Project | 日本原子力学会春の年会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 65 | Study on Ac-225 production for Targeted Alpha Therapy using sodium-cooled fast reactor | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 66 | Conceptual design of small-sized space power reactor cooled by natural circulation with centrifugal force | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 67 | Pros and Cons and the Future R&D | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 68 | Basic study on moderating conditions for breeder reactor with thorium fuel | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 69 | Study on Ac-225 production for Targeted Alpha Therapy using BWR | 日本原子力学会秋の大会予稿集(CD-ROM) | 2020 | | | | 2020 |
| 70 | Report of summer holiday practical training 2018; Feasibility study on nuclear battery using HTTR core; feasibility study for nuclear design | 日本原子力研究開発機構JAEA-Technology(Web) | | 2019-008 | | | 2019 |
| 71 | Briefings and Impressions of the GLOBAL2017 conference | Journal of the Atomic Energy Society of Japan | 60 | 5 | 299 | 302 | 2018 |
| 72 | トクシュウ イマ 、 ナゼ"モ ンジュ"ナ ノ カ : 30ネンゴ ノ エネルギー ノ オオキナ センタクシ ノ ヒトツ | | 36 | 8 | 20 | 24 | Aug. 2016 |
| 73 | 座談会 どうする? もんじゅ(2)適切な規制とは何か,日本の行く末をどう考えるか | Journal of the Atomic Energy Society of Japan | 58 | 3 | 133 | 145 | 2016 |
| 74 | 25pSF-4 Experimental research on fusion-fission and multi-nucleon transfer reactions at JAEA | Meeting Abstracts of the Physical Society of Japan | 70 | 0 | 240 | 241 | 2015 |
| 75 | トリウム利用によるHTTRの燃焼特性改善 | 日本原子力学会春の年会予稿集(CD-ROM) | 2013 | | ROMBUNNO.G17 | | Mar. 11, 2013 |
| 76 | Measures to remove the LWR core debris and its criticality safety management: (4)Criticality safety evaluation during core debris removal and its interim storage | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 158 | | 2013 |
| 77 | Evaluation of β- and γ-energy of FPs for Decay Heat Summation Calculations by Using TAGS Data (2) | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 169 | | 2013 |
| 78 | Study on annular CANDLE core for power flatting | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 195 | | 2013 |
| 79 | Development of gold production technology by neutron nuclear transmutation in nuclear reactor | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 179 | | 2013 |
| 80 | Measures to remove the LWR core debris and its criticality safety management: The boron pellet made by powder metallurgy process, and the gel-like neutron absorption material | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 159 | | 2013 |
| 81 | Measures to remove the LWR core debris and its criticality safety management: (3)Work process and ciriticality safety evaluation of core debris removal and its interim storage | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 157 | | 2013 |
| 82 | Measures against re-criticality of the LWR core during meltdown: (3)Effect of the floatable hollow boron particles on the reactivity safety during core melt down | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 160 | | 2013 |
| 83 | Development of FBR Fuel Loading Pattern Search Tool | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2013 | | 176 | | 2013 |
| 84 | 「 ゲンパツ ゼロ 」 デ イイ ノ カ! ; ゲンパツ ノ シンジツ | | | 増刊 | 85 | 95 | Nov. 2012 |
| 85 | Feasibility Study on a wide-variety of fuel utilization by using HTTR: (1) Outline of Feasibility Study | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 185 | 185 | 2012 |
| 86 | Measurement of core characteristics and Th sample worth of Th loaded core using KUCA:Determinisitic analysis and sensitivity analysis | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | 0 | 157 | 157 | 2012 |
| 87 | Feasibility Study on a wide-variety of fuel utilization by using HTTR: (4) Study on Thorium Fuel Utilization | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 188 | 188 | 2012 |
| 88 | Study on the gold production technology by neutron nuclear transmutation | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 231 | 231 | 2012 |
| 89 | Feasibility Study on availability of HTTR for fuel diversification: (2)Examination of the silicon doping technology and rare-earth elements production using nuclear transmutation | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 186 | 186 | 2012 |
| 90 | Feasibility and economy of nuclear alchemy by using High Temperature engineering Test Reactor | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 229 | 229 | 2012 |
| 91 | Preliminary engineering design of sodium-cooled CANDLE core: (V) Capacity increase and power flatting | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 216 | 216 | 2012 |
| 92 | Preliminary engineering design of sodium-cooled CANDLE core: (VI) Study on Economical Merits | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 217 | 217 | 2012 |
| 93 | Study on power flatting of sodium-cooled CANDLE core | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 210 | | 2012 |
| 94 | Measures against re-criticality of the LWR core during meltdown: (2) Floatable hollow boron particles manufacturing by powder metallurgy | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 151 | | 2012 |
| 95 | Measures against re-criticality of the LWR core during meltdown: (1) Effect of the floatable hollow boron particles on the reactivity safety | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 150 | | 2012 |
| 96 | Evaluation of β– and γ– energy of FPs for Decay Heat Summation Calculations by Using TAGS Data | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 146 | | 2012 |
| 97 | Measures to remove the LWR core debris and its criticality safety evaluation: (1) General remarks and measures to remove the core debris | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 148 | | 2012 |
| 98 | Measures to remove the LWR core debris and its criticality safety evaluation: (2) Criticality safety evaluation during core debris removal | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 149 | | 2012 |
| 99 | Feasibility Study on a wide-variety of fuel utilization by using HTTR: (3) Nuclear characteristics of thorium loaded core | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 187 | 187 | 2012 |
| 100 | Feasibility of heavy water cooled CANDLE reactor using thorium and uranium mixed oxide fuel | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 218 | 218 | 2012 |
| 101 | Measurement of core characteristics and Th sample worth of Th loaded core using KUCA: Experiment plan and results | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 157 | 157 | 2012 |
| 102 | Medium-sized thorium PWR for effective use of Mongolian natural resources | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 220 | 220 | 2012 |
| 103 | Feasibility Study on material creation and new-type fuel utilization by using HTTR: (1) Outline of Feasibility Study | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 198 | 198 | 2011 |
| 104 | Feasibility Study on material creation and new-type fuel utilization by using HTTR: (3) Impact evaluation of rare earth loading on reactivity and economy | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 200 | 200 | 2011 |
| 105 | Feasibility Study on material creation and new-type fuel utilization by using HTTR: (2) Examination of the silicon doping technology and economy assessment | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 199 | 199 | 2011 |
| 106 | Preliminary engineering design of sodium-cooled CANDLE core: Verification of autonomous & stable CANDLE burning by using standard codes | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 178 | 178 | 2011 |
| 107 | Preliminary engineering design of sodium-cooled CANDLE core: (3) CANDLE core design considering design constraints and core performance evaluation | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 180 | 180 | 2011 |
| 108 | Preliminary engineering design of sodium-cooled CANDLE core: (2) Consideration on cladding integrity and cycle length | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 179 | 179 | 2011 |
| 109 | Feasibility Study on material creation and new-type fuel utilization by using HTTR: (4) Feasibility study on irradiation method and development of loading capsule | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 201 | 201 | 2011 |
| 110 | Preliminary engineering design of sodium-cooled CANDLE core: (IV) Consideration on reflector control mechanism | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 213 | 213 | 2011 |
| 111 | Comparison of long lived FP transumutation dependency on nuclear data libraries | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 222 | 222 | 2011 |
| 112 | Feasibility Study on material creation and new-type fuel utilization by using HTTR: (5) Study on Thorium Fuel Utilization | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2011 | | 202 | 202 | 2011 |
| 113 | Deployment Scenario of Heavy Water Cooled Oxide fueled Thorium Breeder Reactor | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 217 | 217 | 2010 |
| 114 | Examination of silicon doping technology in high temperature engineering test reactor (HTTR) | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 200 | 200 | 2010 |
| 115 | Cost impact evaluation of introduction of fuels with enrichment over 5%: (2) Modification of fuel fabrication and reprocessing unit cost | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 218 | 218 | 2010 |
| 116 | Study on the valuable element production technology by neutron nuclear transmutation | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 289 | 289 | 2010 |
| 117 | Economic Analysis of Heavy Water Cooled Thorium Breeder Reactor | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 304 | 304 | 2010 |
| 118 | New Strategy on Rare Earth in Advanced Nuclear Fuel Cycle | | | 56 | 186 | 187 | 2010 |
| 119 | Core design of heavy water cooled thorium breeder reactor -Study on control rod patttern and power flattening- | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 286 | 286 | 2010 |
| 120 | Deployment Scenario of Heavy Water Cooled Thorium Breeder Reactor: Study on transition phase core | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 303 | 303 | 2010 |
| 121 | Study on plutonium productivity improvement and plutonium grade deterioration(_II_): Impact of moderator material introduction into radial blanket on pawer distribution | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2010 | | 188 | 188 | 2010 |
| 122 | Thorium reactor based transmutation scenario for minor actnides generated in LWR and FBR: (2)Evaluation of MA containing Thorium reactor core performance and heat generation of fuels | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009 | | 241 | 241 | 2009 |
| 123 | Study on improvement of Pu generation efficiency and deterioration in Pu grade | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009 | | 246 | 246 | 2009 |
| 124 | Maintenance and practical use of Tokai University nuclear reactor simulator (TURS) | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009 | | 416 | 416 | 2009 |
| 125 | Cost impact evaluation of introduction of fuels with enrichment over 5% | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009 | | 243 | 243 | 2009 |
| 126 | Student training course using the experimental fast reactor Joyo and related facilities: (4) Education effect from the university points of view | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009 | | 47 | 47 | 2009 |
| 127 | Thorium reactor based transmutation scenario for minor actnides generated in LWR and FBR | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2009 | | 219 | 219 | 2009 |
| 128 | Status and Perspectives of Partitioning and Transmutation Technology | Ατομοσ | 50 | 3 | 158 | 163 | Mar. 1, 2008 |
| 129 | Feasibility of Water Cooled Thorium Breeder Reactor | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2008 | | 216 | 216 | 2008 |
| 130 | Increase in tarnsmutaion rate of LLFP with Annular Pellet | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2008 | | 259 | 259 | 2008 |
| 131 | Feasibility Study on Water Cooled Thorium Breeder Reactor: (1) Intention | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2006 | | 154 | 154 | 2006 |
| 132 | 会議報告 ワークショップ「次世代原子力システムの核拡散抵抗性」--その定義と評価の方法 | Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan | 47 | 9 | 638 | 641 | Sep. 30, 2005 |
| 133 | Characteristics for Different Moderation Ratios of the Reactor with Heavy Water Coolant in Equilibrium State | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2005s | | 208 | 208 | 2005 |
| 134 | Helium-cooled Fast Reactor employing Coated-Particle Fuel in Hexagonal Matrix | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2004 | | 196 | 196 | 2004 |
| 135 | 特別寄稿 Atoms for Peace 50周年によせて | Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan | 46 | 12 | 864 | 869 | 2004 |
| 136 | STUDY ON LLFP TRANSMUTATION TECHNOLOGY USING FAST REACTOR (6): Transmutation Performance of Lead-Bismuth Cooled and Sodium Cooled Reactors | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 42nd | | 240 | 240 | 2004 |
| 137 | Study on Metal Fuel Core of Small Sodium Cooled FR for High Temperature Plant | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 42nd | | 233 | 233 | 2004 |
| 138 | STUDY ON LLFP TRANSMUTATION TECHNOLOGY USING FAST REACTOR (5): Effect of Loading Position and Residence Time | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2003 | | 154 | 154 | 2003 |
| 139 | Core Design Studies on Various Forms of Coolants and Fuel Materials. (2). Studies on Liquid Heavy Metal and Gas Cooled Cores, Small Cores and Evaluation of 4-type Cores. | サイクル機構技報 | | 12 | | | 2001 |
| 140 | Development of Advanced Small Reactors | Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan | 43 | 11 | 1054 | 1099 | 2001 |
| 141 | Study of core characteristics on fuel and coolant types. Results of the phase-I of the Feasibility Study Commercialized Fast Reactor Cycle Systems. | 炉心・燃料(燃料形態)の技術検討書 実用化戦略調査研究(フェーズ1)成果報告書 (研究報告) 平成13年 | | | | | 2001 |
| 142 | Experiments and Analyses on Reactivity Worth of Gas Expansion Module(GEM) in FCA XX-1. | 日本原子力研究所JAERI-Research | | | | | 2001 |
| 143 | Core Design Studies on Various Forms of Coolants and Fuel Materials. (1). Studies on Sodium Cooled Fast Reactor Cores. | サイクル機構技報 | | 12 | | | 2001 |
| 144 | Engineering Approach toward SCNES. (No.2. Potential of Current Technology). | 日本原子力学会秋の大会予稿集 | 1998 | | | | 1998 |
| 145 | Engineering approach toward SCNES. (No.1. concept). | 日本原子力学会秋の大会予稿集 | 1998 | | | | 1998 |
| 146 | Correlation between H/HM ratio and reactivity of actinide recycle water cooled reactor. | 日本原子力学会秋の大会予稿集 | 1997 | | | | 1997 |
| 147 | Effect of decontamination factor and reprocessing frequency on the nuclear equilibrium state. | 日本原子力学会春の年会要旨集 | 34th | | | | 1996 |
| 148 | Sodium void reactivity reduction by loading absorber material. | 日本原子力学会春の年会要旨集 | 33rd | | | | 1995 |
| 149 | Research and Developments of Transmutation of High Level Radioactive Waste. | 日本原子力学会誌 | 37 | 3 | 159 | 193 | 1995 |
| 150 | Comparative Analysis of Minor Actinide Mass Balance for Several Transmutation Scenarios. | 日本原子力学会春の年会要旨集 | 32nd | | | | 1994 |
| 151 | Study on the Future Society in Nuclear Equilibrium. (XIII). Balance of Toxicity. | 日本原子力学会春の年会要旨集 | 32nd | | | | 1994 |
| 152 | Mass Balance for a Scenario Adopted Nuclear Transmutation Technology Using MOX-FBR. | 日本原子力学会秋の大会予稿集 | 1993 | | | | 1993 |
| 153 | Examination of Nuclear Transmutation Concept. | 日本原子力学会秋の大会予稿集 | 1992 | | | | 1992 |
| 154 | Study on the Future Society in Nuclear Quasi-Equilibrium. (X). Change of Toxicity. | 日本原子力学会春の年会要旨集 | 30th | | | | 1992 |
| 155 | Study on the Future Society in Nuclear Quasi-Equilibrium. (IX). General Remarks of Presentation I~VIII. | 日本原子力学会春の年会要旨集 | 30th | | | | 1992 |
| 156 | Study on the Future Society in Nuclear Quasi-Equilibrium. VII. Th-Thermal and U-Fast Reactor Synergetic System. | 日本原子力学会秋の大会予稿集 | 1991 | | | | 1991 |
| 157 | Study on nuclear quasi-equilibrium state in future. VI. Investigation of no long-life waste producing fuel cycle. | 日本原子力学会春の年会要旨集 | 29th | | | | 1991 |
| 158 | Study on the Future Society in Nuclear Quasi-Equilibrium. (VIII). Structual Material in Equilbrium Society. | 日本原子力学会秋の大会予稿集 | 1991 | | | | 1991 |
| 159 | Study on nuclear quasi-eqilibrium state in future. V. Equilibrium composition in core considering decay during fuel discharge. | 日本原子力学会秋の大会予稿集 | 1990 | | | | 1990 |
| 160 | Experience with Clinical usage of Barojectsol 100.Especially radivgraphic magnitication of minnte dipressed lesions of the larg intestine. | 新薬と臨床 | 39 | 10 | | | 1990 |
| 161 | Clinical use of Magcorol P. Pretreatment of examination of large intestine. | 新薬と臨床 | 37 | 10 | | | 1988 |
