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TAKAKI Naoyuki

Profile Research field Research achievement Educational achievement Social contribution achievement

 

Books etc  
No.TitleAutour TypePublisherPublication dateRangeISBN
1no_english_title Joint Work The Institute of Electrical Engineers of Japan (IEEJ) Jan. 1, 2021 p.4-8  
2no_english_title Single Work Nov. 1, 2020 p31  
3no_english_title Single Work Jan. 1, 2020  
4Molten Salt Reactor and Thorium Fuel Single Work Atomic Energy Society of Japan Aug. 1, 2018  
5Reacent Development Activities of Molten Salt Reactor Single Work Japan Energy Conference Mar. 1, 2018  
6Briefings and Impressions of the GLOBAL2017 conference Joint Work Atomic Energy Society of Japan Jan. 1, 2018 299-302  
7What is ASTRID ? Single Work Japan Energy Conference Jul. 1, 2017  
8no_english_title Single Work Aug. 1, 2016  
9Energy Procedia, The Fourth International Symposium on Innovative Nuclear Energy Systems, INES-4 Joint Work Elsevier Ltd. May. 1, 2015  
10no_english_title Single Work Sep. 1, 2013 27編 原子力発電  
11no_english_title Single Work Jun. 1, 2011  
12no_english_title Single Work Apr. 1, 2011  
13no_english_title Single Work Apr. 1, 2011  
14Establishment of nuclear education and research network in Asia Joint Work Nuclear Eye Dec. 1, 2009  
15no_english_title Joint Work Dec. 1, 2009  
16no_english_title Single Work Dec. 1, 2009  
17State of the art of advanced reactor development in India Single Work Nuclear Eye Aug. 1, 2009 No.8  
18Toward collaboration between India and Japan in nuclear industry Single Work Nuclear Eye Mar. 1, 2007 No.3  
19Overview of Partitioning and Transmutation Technology Development Joint Work Atomic Energy Society of Japan Feb. 1, 2004  
20Development of advanced small reactor Joint Work Atomic Energy Society of Japan Nov. 1, 2001 p.1094 - 1099  
21R&D of transmutation technology of high level nuclear waste Joint Work Atomic Energy Society of Japan Mar. 1, 1995  

 

Published Papers  
No.TitleJournalVolNoStart PageEnd PagePublication dateDOIReferee
1Semi-Permanent Mass Production of Ac-225 for Cancer Therapy by the (3n,x) Reaction in Pressurized Water Reactor Processes Dec. 29, 2023 https://doi.org/10.3390/pr120100831Refereed 
2Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via the 226 Ra (n,2n) reaction Journal of Nuclear Science and Technology Dec. 14, 2023 https://doi.org/10.1080/00223131.2023.22950181Refereed 
3Evaluation 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 12 Aug. 21, 2023 https://doi.org/10.1080/00223131.2023.22439411Refereed 
4Study 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 
5Breed and burn reactor concept to maximize uranium utilization without fuel shuffling International Symposium on Zero-Carbon Energy Systems, Tokyo Institute of Technology, 2023, 10–12 January, Ookayama, Japan Jan. 2023  Refereed 
6State of the art and perspective of innovative light water reactors 配管技術 65 2023  
7Value 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 2023  
8Neutronic Study on Ac-225 Production for Cancer Therapy by (n,2n) Reaction of Ra-226 or Th-230 Using Fast Reactor Joyo Processes Jun. 2022 https://doi.org/10.3390/pr100712391Refereed 
9Design 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.2021.1088301Refereed 
10Core depletion analysis of long-life CANDLE gas-cooled fast reactor using OpenMC code AIP Conference Proceedings 2374 Jul. 23, 2021 https://doi.org/10.1063/5.00589061Refereed 
11Initial core design analysis of lead (208) -bismuth eutectic-cooled reactor with radial fuel shuffling International Journal of Energy Research 45 12317 12324 Jun. 25, 2021 https://doi.org/10.1002/er.64761Refereed 
12Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant Nuclear Engineering and Technology 53 423 429 Feb. 2021 https://doi.org/10.1016/j.net.2020.07.0081Refereed 
13Archives 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 Jan. 1, 2021 https://doi.org/10.1541/ieejjournal.141.41Not refereed 
14Performance indices optimization of long-lived fission products transmutation in fast reactors International Journal of Energy Research 2021 https://doi.org/10.1002/er.72501Refereed 
15Preliminary 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.49131Refereed 
16A fast reactor transmutation system for 6 LLFP nuclides Nuclear Engineering and Design 363 Jul. 2020 https://doi.org/10.1016/j.nucengdes.2020.1106671Refereed 
17Feasibility 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 
18Study on method to achieve high transmutation of LLFP using fast reactor Scientific Reports Dec. 1, 2019 https://doi.org/10.1038/s41598-019-55489-w1Refereed 
19Conceptual 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.2019.1101741Refereed 
20Core 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.2019.1102081Refereed 
21Convex 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.2018.12.0221Refereed 
22Study on transmutation system of LLFP using fast reactors Transactions of the American Nuclear Society 121 1511 1513 2019 https://doi.org/10.13182/T307591
23Conceptual 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/10.1155/2019/27537891Refereed 
24Geometry survey on the convex shaped core for recriticality prevention against CDA in sodium-cooled fast reactor International Conference on Nuclear Engineering, Proceedings, ICONE 2018 https://doi.org/10.1115/ICONE26-813311Refereed 
25Erratum: Publisher Correction: Method to Reduce Long-lived Fission Products by Nuclear Transmutations with Fast Spectrum Reactors (Scientific reports (2017) 7 1 (13961)) Scientific reports 17270 Dec. 5, 2017 https://doi.org/10.1038/s41598-017-17100-y1Refereed 
26Role 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.119.2225011Refereed 
27Core 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
28Thermal-hydraulic Feasibility Study of a Convex shaped Fast Reactor Core Energy Procedia 131 86 93 2017 https://doi.org/10.1016/j.egypro.2017.09.4531Refereed 
292B09 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 188 189 2017 https://doi.org/10.20549/jseeja.2017.0_1881Not refereed 
30Study on the technology for enhancing element value by neutron transmutation in light water reactors Transactions of the American Nuclear Society 116 1013 2017  
31Fission 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
32Study 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
33Accident analysis of heavy water cooled thorium breeder reactor AIP Conference Proceedings 1656 Apr. 2015 https://doi.org/10.1063/1.49171331
34Fission 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
35Post-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  
36Start-up fuel and power flattening of sodium-cooled candle core International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads 790 797 2013  
37Accuracy 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
38Cost impact evaluation of introduction of above 5% enrichment fuel Transactions of the Atomic Energy Society of Japan 11 118 126 Jun. 2012 https://doi.org/10.3327/taesj.J11.0141
39Decay 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
40Core design and deployment strategy of heavy water cooled sustainable thorium reactor Sustainability 1933 1945 2012 https://doi.org/10.3390/su40819331
41Preliminary engineering design of sodium-cooled CANDLE core AIP Conference Proceedings 1448 29 38 2012 https://doi.org/10.1063/1.47254351
42Core loading pattern optimization of thorium fueled heavy water breeder reactor using genetic algorithm International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 1581 1587 2012  
43Feasibility study on the thorium fueled boiling water breeder reactor International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 1072 1076 2012  
44Verification 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 2605 2613 2012  
45Reactor physics ideas for large scale utilization of thorium in gas cooled reactors Progress in Nuclear Energy 53 814 819 Sep. 2011 https://doi.org/10.1016/j.pnucene.2011.05.0281
46Breeding 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
47Deployment scenario of heavy water cooled thorium breeder reactor AIP Conference Proceedings 1244 109 120 2010 https://doi.org/10.1063/1.34627481
48Symbiotic systems consisting of large-FBR and small water-cooled thorium reactors (WTR) Annals of Nuclear Energy 36 1076 1085 Aug. 2009 https://doi.org/10.1016/j.anucene.2009.05.0091
49A feasible core design of lead bismuth eutectic cooled CANDLE fast reactor Annals of Nuclear Energy 36 562 566 May. 15, 2009 https://doi.org/10.1016/j.anucene.2009.01.0071
50Education of nuclear engineering in Tokai University survives and revives - Challenge for encouragement to master of nuclear enaineers Atomos 51 546 550 2009 https://doi.org/10.3327/jaesjb.51.7_5461
51Breeding and plutonium characterization analysis on actinides closed water-cooled thorium reactor International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 1988 1995 2009  
52All 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 1485 1492 2009  
53Breeding capability and void reactivity analysis of heavy-water-cooled thorium reactor Journal of Nuclear Science and Technology 45 589 600 Jul. 2008 https://doi.org/10.1080/18811248.2008.97114571
54Potential 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
55Performance 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
56Preliminary 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
57Power 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
58Actinide closed water cooled thorium breeder reactor International Conference on the Physics of Reactors 2008, PHYSOR 08 1541 1546 2008  
59Breeding 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" 2487 2495 2008  
60Basic concept of water moderated small reactor for neutron transmutation doping Transactions of the American Nuclear Society 99 745 746 2008  
61Feasible region of design parameters for water cooled thorium breeder reactor Journal of Nuclear Science and Technology 44 946 957 Jul. 2007 https://doi.org/10.1080/18811248.2007.97113341
62Parametric survey for benefit of partitioning and transmutation technology in terms of high-level radioactive waste disposal Journal of Nuclear Science and Technology 44 398 404 Mar. 2007 https://doi.org/10.1080/18811248.2007.97113001
63Feasibility of water cooled thorium breeder reactor based on LWR technology GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems 1733 1738 2007  
64Feasibility 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 392 422 2007  
65Impact of different moderator ratios with light and heavy water cooled reactors in equilibrium states Annals of Nuclear Energy 33 561 572 May. 2006 https://doi.org/10.1016/j.anucene.2006.02.0131
66Design 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
67Cell configuration effect on feasibility of water cooled thorium breeder reactor PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics 2006 2006  
68Systems of symbiotic large FBRs and small CANDLE-Thorium-HTGRs PHYSOR-2006 - American Nuclear Society's Topical Meeting on Reactor Physics 2006 2006  
69Iodine 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
70Neutronic 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
71Effect 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
72Toxicity of radioactive wastes discharged from nuclear energy center in the future equilibrium state Annals of Nuclear Energy 23 663 668 May. 1996 https://doi.org/10.1016/0306-4549(95)00031-31
73Feasibility of Fast Fission System Confining Long-Lived Nuclides Journal of Nuclear Science and Technology 29 276 283 1992 https://doi.org/10.3327/jnst.29.2761
74Preliminary 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
75Evaluation of Neutron Nuclear Data for Z&gt;88 Minor Nuclides Journal of Nuclear Science and Technology 27 853 861 1990 https://doi.org/10.3327/jnst.27.8531

 

MISC  
No.TitleJournalVolNoStart PageEnd PagePublication date
1Conceptual 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 
2Study 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 
3Production 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 
4Feasibility 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 
5R&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 
6R&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 
7Innovative 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 
8Study 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 
9R&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 
10R&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 
11Conceptual 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 
12R&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 
13R&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 
14R&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 
15R&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 
16R&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 
17Core 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 
18Consideration 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 
19Medical 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 
20Medical 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 
21Simplified 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 
22Evaluation 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 
23Study 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 
24Medical 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 
25Core Characteristics and Deployment Scenario of Sustainable Reduced Moderation Thorium Reactor KURNS-EKR (Web) 14 2022 
26Medical 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 
27Medical 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 
28230ThO2 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 
29Medical 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 
30Medical 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 
31Medical 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 
32Core 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 
33Direct 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 
34Medical 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 
35Values 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 
36Medical 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 
37Conceptual 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 
38Conceptual 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 
39Conceptual 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 
40Study 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 
41Conceptual 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 
42Numerical 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 
43Fuel 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 
44Fuel 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 
45Feasibility 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 
46Research 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 
47Research 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 
48Research 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 
49Study 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 
50Conceptual 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 
51Pros 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 
52Basic 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 
53Study 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 
54Feasibility 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 
55Report 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 
5625pSF-4 Experimental research on fusion-fission and multi-nucleon transfer reactions at JAEA Meeting Abstracts of the Physical Society of Japan 70 240 241 2015 
57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 
58Measurement 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 157 157 2012 
59Status and Perspectives of Partitioning and Transmutation Technology Ατομοσ 50 158 163 Mar. 1, 2008 
60Study 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 
61Experiments 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 
62Core 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 
63Core 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 
64Engineering approach toward SCNES. (No.1. concept). 日本原子力学会秋の大会予稿集 1998 1998 
65Engineering 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 
66Correlation 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 
67Effect 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 
68Sodium void reactivity reduction by loading absorber material. 日本原子力学会春の年会要旨集 33rd 1995 
69Research and Developments of Transmutation of High Level Radioactive Waste. 日本原子力学会誌 37 1995 
70Comparative 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 
71Study 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 
72Mass 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 
73Study 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 
74Examination of Nuclear Transmutation Concept. 日本原子力学会秋の大会予稿集 1992 1992 
75Study 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 
76Study 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 
77Study 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 
78Study 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 
79Study 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 

 

Research Grants & Projects  
No.Offer organizationSystem nameTitleFund classificationDate
1Chubu Electric Power Company commissioned research research_project industry_academia_cooperation  2021 - NOW 
2research_project competitive_research_funding  2021 - 2022 
3research_project competitive_research_funding  2020 - 2021 
4Chubu Electric Power Company commissioned research research_project industry_academia_cooperation  2020 - NOW 
5Chubu Electric Power Company commissioned research research_project industry_academia_cooperation  2019 - NOW 
6research_project competitive_research_funding  2019 - NOW 
7NucMed Collaborative research research_project industry_academia_cooperation  2019 - NOW 
8research_project competitive_research_funding  2018 - NOW 
9Chubu Electric Power Company commissioned research research_project industry_academia_cooperation  2018 - 2018 
10research_project competitive_research_funding  2018 - NOW 
11research_project competitive_research_funding  2018 - NOW 
12research_project competitive_research_funding  2017 - NOW 
13JAPAN NUS CO.,Ltd. commissioned research research_project industry_academia_cooperation  2017 - NOW 
14research_project competitive_research_funding  2017 - NOW 
15research_project competitive_research_funding  2017 - NOW 
16Chubu Electric Power Company commissioned research research_project industry_academia_cooperation  2017 - NOW 
17Chubu Electric Power Company commissioned research research_project industry_academia_cooperation  2016 - NOW 
18research_project competitive_research_funding  2016 - 2016 
19Tokai University commissioned research research_project industry_academia_cooperation  2016 - NOW 
20research_project competitive_research_funding  2016 - NOW 
21research_project competitive_research_funding  2015 - 2015 
22research_project competitive_research_funding  2015 - 2015 
23research_project competitive_research_funding  2015 - NOW 
24research_project industry_academia_cooperation  2014 - 2014 
25research_project competitive_research_funding  2014 - NOW 
26research_project industry_academia_cooperation  2013 - 2014 
27research_project industry_academia_cooperation  2013 - 2013 
28research_project industry_academia_cooperation  2013 - 2013 
29research_project industry_academia_cooperation  2013 - 2013 
30Japan Atomic Power Company commissioned research research_project industry_academia_cooperation  2012 - NOW 
31research_project competitive_research_funding  2012 - 2012 
32research_project industry_academia_cooperation  2012 - 2012 
33research_project industry_academia_cooperation  2012 - 2012 
34research_project industry_academia_cooperation  2011 - 2011 
35research_project industry_academia_cooperation  2010 - 2010 
36research_project industry_academia_cooperation  2010 - 2010 
37research_project industry_academia_cooperation  2010 - 2010 
38research_project industry_academia_cooperation  2010 - 2010 
39research_project industry_academia_cooperation  2009 - 2009 
40research_project industry_academia_cooperation  2009 - 2009 
41research_project industry_academia_cooperation  2009 - 2009 
42research_project industry_academia_cooperation  2008 - 2008 
43research_project industry_academia_cooperation  2008 - 2008