| Published Papers |
| No. | Ｔitle | Journal | Vol | No | Start Page | End Page | Publication date | DOI | Referee |
| 1 | Development and validation of fuel stub motion model for the disrupted core of a sodium-cooled fast reactor | Nuclear Engineering and Technology | 53 | 12 | 3930 | 3943 | Dec. 2021 | https://doi.org/10.1016/j.net.2021.06.0181 | Refereed |
| 2 | 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 |
| 3 | Study on dominant aspects of unprotected loss-of-flow to be evaluated in the initiating phase for a sodium-cooled fast reactor | Journal of Nuclear Science and Technology | 58 | 3 | 347 | 360 | Mar. 2021 | https://doi.org/10.1080/00223131.2020.18389641 | Refereed |
| 4 | Numerical simulation of the solid particle sedimentation and bed formation behaviors using a hybrid method | Energies | 13 | 19 | | | Oct. 2020 | https://doi.org/10.3390/en131950181 | Refereed |
| 5 | Sedimentation behavior of mixed solid particles | Journal of Nuclear Science and Technology | 55 | 6 | 623 | 633 | Jun. 3, 2018 | https://doi.org/10.1080/00223131.2017.14198881 | Refereed |
| 6 | Experimental study on debris bed characteristics for the sedimentation behavior of solid particles used as simulant debris | Annals of Nuclear Energy | 111 | | 474 | 486 | Jan. 2018 | https://doi.org/10.1016/j.anucene.2017.09.0111 | Refereed |
| 7 | Numerical simulation of solid-particle sedimentation behaviorusing a multi-fluid model coupled with Dem | 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 | 2017-September | | | | Jan. 1, 2017 | | Refereed |
| 8 | Fundamental experiments of jet impingement and fragmentation simulating the fuel relocation in the core disruptive accident of sodium-cooled fast reactors | 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings | | | | | Jan. 1, 2017 | | Refereed |
| 9 | SAS4A analysis study on the initiating phase of atws events for generation-IV loop-type SFR | 2017 International Congress on Advances in Nuclear Power Plants, ICAPP 2017 - A New Paradigm in Nuclear Power Safety, Proceedings | | | | | Jan. 1, 2017 | | Refereed |
| 10 | Two-phase flow measurements in a simulated debris bed  | 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 | 2017-September | | | | 2017 | | Refereed |
| 11 | Measurements of two-phase pressure drop in a simulated debris bed | International Conference on Nuclear Engineering, Proceedings, ICONE | 9 | | | | 2017 | https://doi.org/10.115/ICONE25-679271 | Refereed |
| 12 | Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors | Journal of Nuclear Science and Technology | 53 | 5 | 698 | 706 | May. 3, 2016 | https://doi.org/10.1080/00223131.2016.11434091 | Refereed |
| 13 | A new empirical model for self-leveling behavior of cylindrical particle beds | Journal of Nuclear Science and Technology | 53 | 5 | 713 | 725 | May. 3, 2016 | https://doi.org/10.1080/00223131.2015.11262041 | Refereed |
| 14 | Validation study in SAS4A code in simulated mild TOP condition | Transactions of the American Nuclear Society | 115 | | 1597 | 1598 | Jan. 1, 2016 | | Refereed |
| 15 | Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor | International Conference on Nuclear Engineering, Proceedings, ICONE | 2 | | | | 2016 | https://doi.org/10.1115/ICONE24-608931 | Refereed |
| 16 | Evaluation of recriticality behavior in the material-relocation phase for Japan sodium-cooled fast reactor | Journal of Nuclear Science and Technology | 52 | 11 | 1448 | 1459 | Nov. 2, 2015 | https://doi.org/10.1080/00223131.2015.10057191 | Refereed |
| 17 | A preliminary evaluation of unprotected loss-of-flow accident for a prototype fast-breeder reactor | Nuclear Engineering and Technology | 47 | 3 | 240 | 252 | Apr. 2015 | https://doi.org/10.1016/j.net.2015.03.0011 | Refereed |
| 18 | A numerical study on local fuel-coolant interactions in a simulated molten fuel pool using the SIMMER-III code | Annals of Nuclear Energy | 85 | | 740 | 752 | Mar. 25, 2015 | https://doi.org/10.1016/j.anucene.2015.06.0301 | Refereed |
| 19 | SIMMER-III analyses of local fuel-coolant interactions in a simulated molten fuel pool: Effect of coolant quantity | Science and Technology of Nuclear Installations | 2015 | | | | Jan. 14, 2015 | https://doi.org/10.1155/2015/9643271 | Refereed |
| 20 | First analysis of local fuel-coolant interactions in a molten pool by SIMMER-III using reactor materials | International Conference on Nuclear Engineering, Proceedings, ICONE | 2015-January | | | | 2015 | | Refereed |
| 21 | An investigation on debris bed self-leveling behavior with non-spherical particles | Journal of Nuclear Science and Technology | 51 | 9 | 1096 | 1106 | Sep. 2, 2014 | https://doi.org/10.1080/00223131.2014.9104781 | Refereed |
| 22 | The effect of coolant quantity on local fuel-coolant interactions in a molten pool | Annals of Nuclear Energy | 75 | | 20 | 25 | Aug. 19, 2014 | https://doi.org/10.1016/j.anucene.2014.07.0421 | Refereed |
| 23 | An experimental study on local fuel-coolant interactions by delivering water into a simulated molten fuel pool | Nuclear Engineering and Design | 275 | | 133 | 141 | Aug. 2014 | https://doi.org/10.1016/j.nucengdes.2014.05.0031 | Refereed |
| 24 | Numerical study on sedimentation behavior of solid particles used as simulant fuel debris | Journal of Nuclear Science and Technology | 51 | 5 | 681 | 699 | May. 4, 2014 | https://doi.org/10.1080/00223131.2014.8874811 | Refereed |
| 25 | A scenario of core disruptive accident for Japan sodium-cooled fast reactor to achieve in-vessel retention | Journal of Nuclear Science and Technology | 51 | 4 | 493 | 513 | Apr. 2014 | https://doi.org/10.1080/00223131.2013.8774051 | Refereed |
| 26 | Evaluation of debris bed self-leveling behavior: A simple empirical approach and its validations | Annals of Nuclear Energy | 63 | | 188 | 198 | Jan. 2014 | https://doi.org/10.1016/j.anucene.2013.07.0501 | Refereed |
| 27 | Characteristics of pressure buildup from local fuel-coolant interactions in a simulated molten fuel pool | International Conference on Nuclear Engineering, Proceedings, ICONE | 2B | | | | 2014 | https://doi.org/10.1115/ICONE22-312211 | Refereed |
| 28 | Development of an evaluation methodology for the fuelrelocation into the coolant plenum in the core disruptive accident of sodium-cooled fast reactors | International Conference on Nuclear Engineering, Proceedings, ICONE | 3 | | | | 2014 | https://doi.org/10.1115/ICONE22-303451 | Refereed |
| 29 | Safety evaluation of prototype fast-breeder reactor -Analysis of ULOF accident to demonstrate in-vessel retention | International Conference on Nuclear Engineering, Proceedings, ICONE | 6 | | | | 2014 | https://doi.org/10.1115/ICONE22-306041 | Refereed |
| 30 | An experimental investigation on self-leveling behavior of debris beds using gas-injection | Experimental Thermal and Fluid Science | 48 | | 110 | 121 | Jul. 2013 | https://doi.org/10.1016/j.expthermflusci.2013.02.0141 | Refereed |
| 31 | Characteristics of self-leveling behavior of debris beds in a series of experiments | Nuclear Engineering and Technology | 45 | 3 | 323 | 334 | Jun. 2013 | https://doi.org/10.5516/NET.02.2012.0681 | Refereed |
| 32 | Empirical correlations for predicting the self-leveling behavior of debris bed | Nuclear Science and Techniques | 24 | 1 | | | Feb. 20, 2013 | | Refereed |
| 33 | Safety design and evaluation in a large-scale Japan sodium-cooled fast reactor | Science and Technology of Nuclear Installations | 2012 | | | | 2012 | https://doi.org/10.1155/2012/6149731 | Refereed |
| 34 | Experimental studies and empirical models for the transient self-leveling behavior in debris bed | Journal of Nuclear Science and Technology | 48 | 10 | 1327 | 1336 | Oct. 2011 | https://doi.org/10.3327/jnst.48.13271 | Refereed |
| 35 | Experimental investigation of bubbling in particle beds with high solid holdup | Experimental Thermal and Fluid Science | 35 | 2 | 405 | 415 | Feb. 2011 | https://doi.org/10.1016/j.expthermflusci.2010.11.0031 | Refereed |
| 36 | Experimental investigation on self-leveling behavior in debris beds | Nuclear Engineering and Design | 241 | 1 | 366 | 377 | Jan. 2011 | https://doi.org/10.1016/j.nucengdes.2010.11.0131 | Refereed |
| 37 | A Simple Approach to the Prediction of Transient Self-Leveling Behavior of Debris Bed | PROCEEDINGS OF ISHTEC2012, 4TH INTERNATIONAL SYMPOSIUM ON HEAT TRANSFER AND ENERGY CONSERVATION | | | 406 | 410 | 2011 | | Refereed |
| 38 | Self-leveling onset criteria in debris beds | Journal of Nuclear Science and Technology | 47 | 4 | 384 | 395 | Apr. 2010 | https://doi.org/10.1080/18811248.2010.97119691 | Refereed |
| 39 | Evaluation of a steam generator tube rupture accident in an accelerator driven system with lead cooling | Progress in Nuclear Energy | 50 | 2-6 | 363 | 369 | Mar. 2008 | https://doi.org/10.1016/j.pnucene.2007.11.0181 | Refereed |
| 40 | The SIMMER safety code system and its validation efforts for fast reactor application | International Conference on the Physics of Reactors 2008, PHYSOR 08 | 3 | | 2370 | 2378 | 2008 | | Refereed |
| 41 | Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels | Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment | 562 | 2 | 863 | 866 | Jun. 23, 2006 | https://doi.org/10.1016/j.nima.2006.02.0731 | Refereed |
| 42 | Transient analyses for accelerator driven system PDS-XADS using the extended SIMMER-III code | Nuclear Engineering and Design | 235 | 24 | 2594 | 2611 | Dec. 2005 | https://doi.org/10.1016/j.nucengdes.2005.06.0121 | Refereed |
| 43 | Application of high frame-rate neutron radiography to liquid-metal two-phase flow research | Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment | 542 | 1-3 | 168 | 174 | Apr. 21, 2005 | https://doi.org/10.1016/j.nima.2005.01.0951 | Refereed |
| 44 | Measurements of liquid-metal two-phase flow by using neutron radiography and electrical conductivity probe | Experimental Thermal and Fluid Science | 29 | 3 | 323 | 330 | Mar. 2005 | https://doi.org/10.1016/j.expthermflusci.2004.05.0091 | Refereed |
| 45 | Velocity field measurement in gas-liquid metal two-phase flow with use of PIV and neutron radiography techniques | Applied Radiation and Isotopes | 61 | 4 | 683 | 691 | Oct. 2004 | https://doi.org/10.1016/j.apradiso.2004.03.1101 | Refereed |
| 46 | Source and reactivity perturbations in accelerator driven systems with conventional MOX and advanced fertile free fuels | Proceedings of the PHYSOR 2004: The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments | | | 2023 | 2031 | 2004 | | Refereed |
| 47 | Safety aspects of oxide fuels for transmutation and utilization in accelerator driven systems | Journal of Nuclear Materials | 320 | 1-2 | 147 | 155 | Jul. 1, 2003 | https://doi.org/10.1016/S0022-3115(03)00182-X1 | Refereed |
| 48 | Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Extended verification using multi-bubble condensation experiment | Nuclear Engineering and Design | 220 | 3 | 240 | 254 | Apr. 2003 | https://doi.org/10.1016/S0029-5493(02)00350-31 | Refereed |
| 49 | Development of multicomponent vaporization/condensation model for a reactor safety analysis code SIMMER-III: Theoretical modeling and basic verification | Nuclear Engineering and Design | 220 | 3 | 224 | 239 | Apr. 2003 | https://doi.org/10.1016/S0029-5493(02)00351-51 | Refereed |
| 50 | Analysis of gas-liquid metal two-phase flows using a reactor safety analysis code SIMMER-III | Nuclear Engineering and Design | 220 | 3 | 207 | 223 | Apr. 2003 | https://doi.org/10.1016/S0029-5493(02)00349-71 | Refereed |
| 51 | Analyses of unprotected transients in the lead/bismuth-cooled accelerator driven system PDS-XADS | Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy | | | 1725 | 1732 | 2003 | | Refereed |
| 52 | Unprotected transients in a small scale accelerator driven system | International Meeting on Nuclear Applications of Accelerator Technology: Accelerator Application in a Nuclear Renaissance | | | 677 | 683 | 2003 | | |
| Conference Activities & Talks |
| No. | Ｔitle | Conference | Publication date | Promoter | Venue |
| 1 | Preliminary analysis of the post-disassembly expansion phase and structural response under unprotected loss of flow accident in prototype sodium cooled fast reactor | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2016 | | |
| 2 | First analysis of local fuel-coolant interactions in a molten pool by SIMMER-III using reactor materials | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2015 | | |
| 3 | Safety evaluation of prototype fast-breeder reactor -Analysis of ULOF accident to demonstrate in-vessel retention | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2014 | | |
| 4 | Development of an evaluation methodology for the fuelrelocation into the coolant plenum in the core disruptive accident of sodium-cooled fast reactors | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2014 | | |
| 5 | Characteristics of pressure buildup from local fuel-coolant interactions in a simulated molten fuel pool | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2014 | | |
| 6 | A methodological study on extending an empirical model to predict self-leveling behavior of debris beds with non-spherical particles | International Conference on Power Engineering 2013, ICOPE 2013 | Jan. 1, 2013 | | |
| 7 | Recent knowledge from an experimental investigation on self-leveling behavior of debris bed | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2013 | | |
| 8 | Experimental evaluation of debris bed characteristics in particulate debris sedimentation behaviour | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2013 | | |
| 9 | Numerical simulation of the self-leveling phenomenon by modified SIMMER-III | International Conference on Nuclear Engineering, Proceedings, ICONE | Jan. 1, 2012 | | |
| 10 | Experimental study of bubble behavior in a two-dimensional particle bed with high solid holdup | International Conference on Nuclear Engineering, Proceedings, ICONE | Dec. 1, 2010 | | |
| 11 | Development of severe accident evaluation technology (Level 2 PSA) for sodium-cooled fast reactors (1) overview of evaluation methodology development | International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 | Jan. 1, 2009 | | |
| 12 | The SIMMER safety code system and its validation efforts for fast reactor application | International Conference on the Physics of Reactors 2008, PHYSOR 08 | Jan. 1, 2008 | | |
| 13 | Analyses of transients for an 800 MW-class accelerator driven transmuter with fertile-free fuels | Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment | Jun. 23, 2006 | | |
| 14 | Application of high frame-rate neutron radiography to liquid-metal two-phase flow research | Nuclear Instruments and Methods in Physics Research, Section A: Accelerators, Spectrometers, Detectors and Associated Equipment | Apr. 21, 2005 | | |
| 15 | Analyses of unprotected transients in the lead/bismuth-cooled accelerator driven system PDS-XADS | Global 2003: Atoms for Prosperity: Updating Eisenhowers Global Vision for Nuclear Energy | Dec. 1, 2003 | | |
| 16 | Advanced modeling of multicomponent vaporization/condensation phenomena for a reactor safety analysis code SIMMER-III | International Conference on Nuclear Engineering, Proceedings, ICONE | Oct. 19, 2002 | | |
