| Published Papers |
| No. | Ｔitle | Journal | Vol | No | Start Page | End Page | Publication date | DOI | Referee |
| 1 | Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications  | Journal of Nuclear Engineering and Radiation Science | 9 | 4 | | | Mar. 14, 2023 | https://doi.org/10.1115/1.40568541 | |
| 2 | Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study | Journal of Nuclear Engineering and Radiation Science | 9 | 2 | | | Mar. 2, 2023 | https://doi.org/10.1115/1.40568341 | |
| 3 | Evaluation of mechanical cutting for disassembly of fast reactor fuel assemblies | Journal of Nuclear Science and Technology | | | 1 | 12 | Aug. 18, 2022 | https://doi.org/10.1080/00223131.2022.20877811 | Refereed |
| 4 | Improvement of solidification model and analysis of 3D channel blockage with MPS method | Frontiers in Energy | 15 | 4 | 946 | 958 | Dec. 2021 | https://doi.org/10.1007/s11708-021-0754-z1 | Refereed |
| 5 | Experimental study on transport behavior of cesium iodide in the reactor coolant system under LWR severe accident conditions | Journal of Nuclear Science and Technology | 57 | 12 | 1287 | 1296 | Dec. 1, 2020 | https://doi.org/10.1080/00223131.2020.17822811 | Refereed |
| 6 | Release behavior of radionuclides from MOX fuels irradiated in a fast reactor during heating tests | Journal of Nuclear Materials | 536 | | 152199 | 152199 | Aug. 2020 | https://doi.org/10.1016/j.jnucmat.2020.1521991 | Refereed |
| 7 | Feasibility of Disassembly of Fast Reactor Fuel Assembly Using Fiber Laser Cutting Technology | Transactions of the Atomic Energy Society of Japan | 19 | 2 | 65 | 75 | 2020 | https://doi.org/10.3327/taesj.j19.0061 | Refereed |
| 8 | Chemical reaction kinetics dataset of Cs-I-B-MoO-H system for evaluation of fission product chemistry under LWR severe accident conditions | Journal of Nuclear Science and Technology | 56 | | 228 | 240 | Nov. 2018 | | Refereed |
| 9 | Hard X-ray photoelectron spectroscopy study for transport behavior of CsI in heating test simulating a BWR severe accident condition: Chemical effects of boron vapors | NUCLEAR ENGINEERING AND DESIGN | 297 | | 251 | 256 | Feb. 2016 | https://doi.org/10.1016/j.nucengdes.2015.10.0291 | Refereed |
| 10 | Thermophysical properties of americium-containing barium plutonate | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 52 | 10 | 1285 | 1289 | Oct. 2015 | https://doi.org/10.1080/00223131.2015.10295541 | Refereed |
| 11 | Chemical form consideration of released fission products from irradiated fast reactor fuels during overheating | PROGRESS IN NUCLEAR ENERGY | 82 | | 86 | 91 | Jul. 2015 | https://doi.org/10.1016/j.pnucene.2014.07.0331 | Refereed |
| 12 | Influence of boron vapor on transport behavior of deposited CsI during heating test simulating a BWR severe accident condition | JOURNAL OF NUCLEAR MATERIALS | 461 | | 22 | 28 | Jun. 2015 | https://doi.org/10.1016/j.jnucmat.2015.02.0321 | Refereed |
| 13 | Penetration behavior of water solution containing radioactive species into dried concrete/mortar and epoxy resin materials | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 52 | 4 | 580 | 587 | Apr. 2015 | https://doi.org/10.1080/00223131.2014.9637251 | Refereed |
| 14 | Distribution of radioactive nuclides of boring core samples extracted from concrete structures of reactor buildings in the Fukushima Daiichi Nuclear Power Plant | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 51 | 7-8 | 1006 | 1023 | Jul. 2014 | https://doi.org/10.1080/00223131.2014.9157691 | Refereed |
| 15 | Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 51 | 7-8 | 876 | 885 | Jul. 2014 | https://doi.org/10.1080/00223131.2014.8962291 | Refereed |
| 16 | Americium and plutonium release behavior from irradiated mixed oxide fuel during heating | JOURNAL OF NUCLEAR MATERIALS | 437 | 1-3 | 275 | 281 | Jun. 2013 | https://doi.org/10.1016/j.jnucmat.2013.02.0261 | Refereed |
| 17 | Results of detailed analyses performed on boring cores extracted from the concrete floors of the Fukushima Daiichi Nuclear Power Plant reactor buildings | International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads | 1 | | 272 | 277 | Jan. 1, 2013 | | Not refereed |
| 18 | Simple formula to evaluate helium production amount in fast reactor MA-containing MOX fuel and its accuracy | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 50 | 1 | 107 | 121 | Jan. 2013 | https://doi.org/10.1080/00223131.2013.7500661 | Refereed |
| 19 | Therrnophysical properties of perovskite type alkaline-earth metals and plutonium complex oxides | JOURNAL OF NUCLEAR MATERIALS | 422 | 1-3 | 163 | 166 | Mar. 2012 | https://doi.org/10.1016/j.jnucmat.2011.12.0361 | Refereed |
| 20 | Measurement of Surface Melting Temperature with High-speed Pyrometers by Containerless Method | 2012 PROCEEDINGS OF SICE ANNUAL CONFERENCE (SICE) | | | 32 | 34 | 2012 | | Refereed |
| 21 | Evaluation of fission products migration behavior by fuel heating tests:(3) Release behavior of fission products from the heated fuel sample | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 378 | 378 | 2012 | https://doi.org/10.11561/aesj.2012f.0.378.01 | |
| 22 | Evaluation of fission products migration behavior by fuel heating tests:(1) Objective and outline | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 376 | 376 | 2012 | https://doi.org/10.11561/aesj.2012f.0.376.01 | |
| 23 | Decontamination Experiment for Floor of Fukushima Daiichi Reactor Buildings:Penetration Behavior of Simulated-contaminated Water into Floor and Wall Materials | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 642 | 642 | 2012 | https://doi.org/10.11561/aesj.2012f.0.642.01 | |
| 24 | Evaluation of fission products migration behavior by fuel heating tests:(2) Phase status of the heated fuel sample | Proceedings of Annual / Fall Meetings of Atomic Energy Society of Japan | 2012 | | 377 | 377 | 2012 | https://doi.org/10.11561/aesj.2012f.0.377.01 | |
| 25 | Burnup dependence of melting temperature of FBR mixed oxide fuels irradiated to high burnup | JOURNAL OF NUCLEAR MATERIALS | 418 | 1-3 | 207 | 214 | Nov. 2011 | https://doi.org/10.1016/j.jnucmat.2011.07.0011 | Refereed |
| 26 | Fission gases and helium gas behavior in irradiated mixed oxide fuel pin | JOURNAL OF NUCLEAR MATERIALS | 416 | 1-2 | 151 | 157 | Sep. 2011 | https://doi.org/10.1016/j.jnucmat.2010.11.0281 | Refereed |
| 27 | Thermal conductivity of BaPuO3 at temperatures from 300 to 1500 K | JOURNAL OF NUCLEAR MATERIALS | 414 | 2 | 316 | 319 | Jul. 2011 | https://doi.org/10.1016/j.jnucmat.2011.04.0571 | Refereed |
| 28 | Melting behavior of MgO-based inert matrix fuels containing (Pu,Am)O2-x | JOURNAL OF NUCLEAR MATERIALS | 400 | 1 | 32 | 36 | May. 2010 | https://doi.org/10.1016/j.jnucmat.2010.02.0061 | Refereed |
| 29 | Diffusion behaviors of plutonium and americium in polycrystalline urania | ACTINIDES 2009 | 9 | | | | 2010 | https://doi.org/10.1088/1757-899X/9/1/0120051 | Refereed |
| 30 | Molecular dynamics analysis of diffusion of uranium and oxygen ions in uranium dioxide | ACTINIDES 2009 | 9 | | | | 2010 | https://doi.org/10.1088/1757-899X/9/1/0120031 | Refereed |
| 31 | Microstructure and elemental distribution of americium-containing uranium plutonium mixed oxide fuel under a short-term irradiation test in a fast reactor | JOURNAL OF NUCLEAR MATERIALS | 385 | 2 | 407 | 412 | Mar. 2009 | https://doi.org/10.1016/j.jnucmat.2008.12.0281 | Refereed |
| 32 | Research and development of americium-containing mixed oxide fuel for fast reactors | GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems | | | 897 | 902 | Dec. 1, 2007 | | Not refereed |
| 33 | A rational Minor Actinide (MA) recycling concept based on innovative oxide fuel with high AM content | GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems | | | 283 | 289 | Dec. 1, 2007 | | Not refereed |
| 34 | An effective loading method of americium targets in fast reactors | GLOBAL 2007: Advanced Nuclear Fuel Cycles and Systems | | | 1280 | 1288 | Dec. 1, 2007 | | Not refereed |
| 35 | High temperature behavior of irradiated mixed nitride fuel during heating tests | JOURNAL OF ALLOYS AND COMPOUNDS | 444 | | 580 | 583 | Oct. 2007 | https://doi.org/10.1016/j.jallcom.2007.02.1571 | Refereed |
| 36 | Innovative oxide fuels doped with minor actinides for use in fast reactors | ENERGY AND SUSTAINABILITY | 105 | | 357 | + | 2007 | https://doi.org/10.2495/ESUS0703511 | Refereed |
| 37 | Oxygen potentials Of (U0.685Pu0.270Am0.045)O2-x solid solution | JOURNAL OF ALLOYS AND COMPOUNDS | 397 | 1-2 | 110 | 114 | Jul. 2005 | https://doi.org/10.1016/j.jallcom.2005.01.0241 | Refereed |
| 38 | Molecular dynamics studies of neptunium dioxide | JOURNAL OF ALLOYS AND COMPOUNDS | 387 | 1-2 | 9 | 14 | Jan. 2005 | https://doi.org/10.1016/j.jallcom.2004.06.0371 | Refereed |
| 39 | Molecular dynamics studies of minor actinide dioxides | Journal of Nuclear Science and Technology | 41 | 8 | 827 | 831 | 2004 | https://doi.org/10.1080/18811248.2004.97155521 | Refereed |
| 40 | Reaction of modified SUS316 with tellurium under low oxygen potentials | CORROSION SCIENCE | 45 | 8 | 1757 | 1766 | Aug. 2003 | https://doi.org/10.1016/s0010-938X(03)00022-21 | Refereed |
| 41 | Fission products release from irradiated FBR MOX fuel during transient conditions | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 40 | 2 | 104 | 113 | Feb. 2003 | https://doi.org/10.1080/18811248.2003.97153391 | Refereed |
| 42 | Oxidation behavior of modified SUS316 (PNC316) stainless steel under low oxygen partial pressure | JOURNAL OF NUCLEAR MATERIALS | 304 | 1 | 21 | 28 | Jul. 2002 | https://doi.org/10.1016/S0022-3115(02)00872-31 | Refereed |
| 43 | A method for determining an effective porosity correction factor for thermal conductivity in fast reactor uranium-plutonium oxide fuel pellets | Journal of Nuclear Materials | 281 | 2-3 | 117 | 128 | 2000 | https://doi.org/10.1016/S0022-3115(00)00243-91 | Refereed |
| 44 | Behavior of fission products zirconium and barium in fast reactor fuel irradiated to high burnup | JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 36 | 9 | 775 | 780 | Sep. 1999 | https://doi.org/10.1080/18811248.1999.97262671 | Refereed |
| 45 | Behavior of metallic fission products in uranium-plutonium mixed oxide fuel | JOURNAL OF NUCLEAR MATERIALS | 273 | 3 | 239 | 247 | Aug. 1999 | https://doi.org/10.1016/S0022-3115(99)00071-91 | Refereed |
| 46 | Distribution of molybdenum in FBR fuel irradiated to high burnup | Journal of Nuclear Materials | 247 | | 46 | 49 | 1997 | https://doi.org/10.1016/S0022-3115(97)00062-71 | Refereed |
