Published Report
| No. | 2026 - 06 |
|---|---|
| Publication Date | October 2026 |
| Media | ACC2026 |
| Title | Dose Reduction by Water Chemistry Improvement during Hot Functional Test (HFT) in PWR Plants (Part 1) |
| No. | 2026 - 05 |
|---|---|
| Publication Date | October 2026 |
| Media | TopFuel2026 |
| Title | Development of a Flow Regime Identification Method for Gas-Liquid Two-Phase Flow in a Vertical Pipe toward Rod Bundle Applications |
| No. | 2026 - 04 |
|---|---|
| Publication Date | October 2026 |
| Media | TopFuel2026 |
| Title | Development of In-situ Observation System for Fracture Behavior of Cr-coating Film on Zircaloy-4 Using the Acoustic Emission Technique under High-Temperature |
| No. | 2026 - 03 |
|---|---|
| Publication Date | October 2026 |
| Media | TopFuel2026 |
| Title | Effects of Coating Process on LOCA Burst and High-Temperature Behaviors of Cr-coated cladding |
| No. | 2026 - 02 |
|---|---|
| Publication Date | October 2026 |
| Media | TopFuel2026 |
| Title | INVESTIGATION OF IRRADIATION EFFECTS ON CHROMIUM COATED CLADDING PERFORMANCE: INITIAL EVALUATION OF FUEL BEHAVIOR |
| No. | 2026 - 01 |
|---|---|
| Publication Date | August 2026 |
| Media | Journal of Nuclear Science and Technology |
| Title | Mitigation of steam-oxidation in uranium nitride fuel pellets by carbon addition |
| No. | 2025 - 03 |
|---|---|
| Publication Date | November 2025 |
| Media | SBNWM2025 |
| Title | Determination of the Ultra-Low 36Cl Leached from Irradiated Fuel Cladding Using Accelerator Mass Spectrometry |
| No. | 2025 - 02 |
|---|---|
| Publication Date | October 2025 |
| Media | IGRDM-24 |
| Title | Specimen Reconstitution with an Extremely Small Heat Affected Zone using Additive Manufacturing |
| No. | 2025 - 01 |
|---|---|
| Publication Date | June 2025 |
| Media | ISORD-12 |
| Title | Japanese Concrete Composition Standards for shielding calculation |
| No. | 2024 - 01 |
|---|---|
| Publication Date | September 2024 |
| Media | TopFuel2024 |
| Title | DEVELOPMENT OF CHROMIUM COATED CLADDING IN JAPAN FOR THE COMMERCIAL PWR |
| No. | 2023 - 05 |
|---|---|
| Publication Date | March 2024 |
| Media | SMiRT27 |
| Title | Nickel (Ni) elution-suppressing effect from TT690 of iron supply to the primary coolant |
| No. | 2023 - 04 |
|---|---|
| Publication Date | June 2024 |
| Media | SWINTH-2024 |
| Title | Development of Advanced Neutronics/Thermal-Hydraulics Coupling Simulation System (9) Development of Measuremrnt Mathod for Gas-Liquid Two-Phase flow inside a Fuel Bundle to Obtain Code Validation Data |
| No. | 2023 - 03 |
|---|---|
| Publication Date | November 2023 |
| Media | SBNWM2023 |
| Title | Determination of Mo-93 Inventory in Irradiated BWR Tie Plate Using Triple Quadrupole ICP-MS |
| No. | 2023 - 02 |
|---|---|
| Publication Date | September 2023 |
| Media | NPC2023 |
| Title | Semiconductor properties of Ni-base alloys oxide formed in PWR primary conditions with Zn Injction |
| No. | 2023 - 01 |
|---|---|
| Publication Date | May 2023 |
| Media | ICONE30 |
| Title | Steam oxidation tests of uranium nitride fuels with addittives |
| No. | 2022 - 02 |
|---|---|
| Publication Date | September 2022 |
| Media | ICRS14 |
| Title | On Publication of ‛A Handbook of Radiation Shielding‘ Supervised by the Shielding Research Committee of Atomic Energy Society of Japan |
| No. | 2022 - 01 |
|---|---|
| Publication Date | September 2022 |
| Media | ICRS14 |
| Title | Current status of discussion for Japanese Shielding Materials Standard for facility |
| No. | 2021 - 01 |
|---|---|
| Publication Date | October 2021 |
| Media | TopFuel2021 |
| Title | DEVELOPMENT OF M-REX FUEL ASSEMBLY WITH M-MDA CLADDING AND STRUCTURAL COMPONENTS |
| No. | 2019 - 02 |
|---|---|
| Publication Date | May 2019 |
| Media | ICONE27 |
| Title | Practical application of CFD to a design process of PWR |
| No. | 2019 - 01 |
|---|---|
| Publication Date | May 2019 |
| Media | ICONE27 |
| Title | VERIFICATION OF STRENGTH LIMIT ANALYSIS MODEL FOR THIMBLE TUBE WITH MATERIAL PLASTICITY UNDER BENDING MOMENT AND AXIAL COMPRESSION FORCE |
| No. | 2018 - 02 |
|---|---|
| Publication Date | September 2018 |
| Media | HOTLAB2018 |
| Title | Miniature C (T) Specimen Fabrication for Reutilization of Surveillance Tested Materials |
| No. | 2018 - 01 |
|---|---|
| Publication Date | July 2018 |
| Media | ICONE26 |
| Title | STRENGTH LIMIT OF THIMBLE TUBE WITH MATERIAL PLASTICITY UNDER BENDING MOMENT AND AXIAL COMPRESSION FORCE |
| No. | 2017 - 06 |
|---|---|
| Publication Date | October 2017 |
| Media | SBNWM2017 |
| Title | Investigation of C-14 in the CRUD collected on the coolant filter for safety disposal of radioactive waste containing C-14 (I) |
| No. | 2017 - 05 |
|---|---|
| Publication Date | October 2016 |
| Media | IGRDM20 |
| Title | Fracture toughness evaluation using Miniature C (T) specimen for the irradiated materials |
| No. | 2017 - 04 |
|---|---|
| Publication Date | September 2017 |
| Media | HOTLAB2017 |
| Title | Post-irradiation Examination Using TEM Method for Swelling Evaluation of Baffle Plate in PWR Core Internals |
| No. | 2017 - 03 |
|---|---|
| Publication Date | July 2017 |
| Media | ASME PVP 2017 |
| Title | APPLICABILITY OF MINIATURE C(T) SPECIMEN TO FRACTURE TOUGHNESS EVALUATION FOR THE IRRADIATED JAPANESE REACTOR PRESSURE VESSEL STEEL |
| No. | 2017 - 02 |
|---|---|
| Publication Date | July 2017 |
| Media | ASME PVP 2017 |
| Title | SWELLING CHARACTERISTICS OF A TYPE 304SS BAFFLE PLATE IRRADIATED UP TO 50dpa IN PWR AND VALIDATION OF A SWELLING EQUATION |
| No. | 2017 - 01 |
|---|---|
| Publication Date | April 2017 |
| Media | ICAPP2017 |
| Title | Development of M-MDA as reliable cladding and structural materials |
| No. | 2016 - 03 |
|---|---|
| Publication Date | October 2016 |
| Media | NPC2016 |
| Title | A Modelling Study on Water Radiolysis for Primary Coolant in PWR |
| No. | 2016 - 02 |
|---|---|
| Publication Date | August 2016 |
| Media | FEPFS2016 |
| Title | FEM analysis of cylindrical tube with and without pellets against axial impact force |
| No. | 2016 - 01 |
|---|---|
| Publication Date | July 2016 |
| Media | ASME PVP 2016 |
| Title | Applicability of miniature C (T) specimen to fracture toughness evaluation for the irradiated Japanese reactor pressure vessel steel |
| No. | 2015 - 03 |
|---|---|
| Publication Date | March 2016 |
| Media | Journal of Nuclear Science and Technology, Volume 53 |
| Title | Primary yields and reaction sets with corresponding rate constants for computer simulation of water radiolysis at elevated temperature |
| No. | 2015 - 02 |
|---|---|
| Publication Date | January 2016 |
| Media | Acta Materialia, Volume 102 |
| Title | The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening : Bcc Nb particles and nanometric Nb clusters embedded in hcp Zr |
| No. | 2015 - 01 |
|---|---|
| Publication Date | November 2015 |
| Media | Scripta Materialia, Volume 108 |
| Title | Microstructural analysis of impurity segregation around β-Nb precipitates in Zr-Nb alloy using positron annihilation spectroscopy and atom probe tomography |
| No. | 2014 - 05 |
|---|---|
| Publication Date | December 2014 |
| Media | APCF/SIF-2014 International Congress |
| Title | Dynamic buckling tests of cylindrical tubes with and without pellets |
| No. | 2014 - 04 |
|---|---|
| Publication Date | November 2014 |
| Media | Nuclear Engineering and Design, Volume 279 |
| Title | CFD application to advanced design for high efficiency spacer grid |
| No. | 2014 - 03 |
|---|---|
| Publication Date | October 2014 |
| Media | NPC2014 |
| Title | Study for Nickel deposition on the fuel cladding by DH transition under simulated PWR conditions |
| No. | 2014 - 02 |
|---|---|
| Publication Date | October 2014 |
| Media | NPC2014 |
| Title | Appropriate zinc addition management into PWR primary coolant after the plant long-term maintenance |
| No. | 2014 - 01 |
|---|---|
| Publication Date | October 2014 |
| Media | NPC2014 |
| Title | The effects of zinc injection from at TOMARI Unit 3 |
| No. | 2013 - 03 |
|---|---|
| Publication Date | January 2014 |
| Media | Sixth International Symposium on Small Specimen Test Techniques |
| Title | Evaluation of fracture toughness for reactor pressure vessel by miniature C (T) specimen |
| No. | 2013 - 02 |
|---|---|
| Publication Date | November 2013 |
| Media | Journal of Nuclear Materials, Volume 442 |
| Title | Heterogeneous UO2 fuel irradiated up to a high Burn-up : HBS and fission products release studies |
| No. | 2013 - 01 |
|---|---|
| Publication Date | July 2013 |
| Media | ASME PVP 2013 |
| Title | Applicability of miniature C (T) specimen to evaluation of fracture toughness for reactor pressure vessel steel |
| No. | 2012 - 06 |
|---|---|
| Publication Date | October 2012 |
| Media | NuMat2012 |
| Title | Thermal property change of MOX and UO2 irradiated up to high burnup |
| No. | 2012 - 05 |
|---|---|
| Publication Date | October 2012 |
| Media | NuMat2012 |
| Title | Dynamic load impact tests on high burnup spent fuel rods on BWR and PWR |
| No. | 2012 - 04 |
|---|---|
| Publication Date | October 2012 |
| Media | Journal of Nuclear Science and Technology，Volume 49 |
| Title | Thermal condcutivity degradation analyses of LWR MOX fuel by the quasi-two phase material model |
| No. | 2012 - 03 |
|---|---|
| Publication Date | September 2012 |
| Media | NPC2012 |
| Title | Effect of Zinc injection from hot functional test at TOMARI Unit3 |
| No. | 2012 - 02 |
|---|---|
| Publication Date | September 2012 |
| Media | NPC2012 |
| Title | Study on a corrosion products behavior with zinc injection in PWR primary circuit based on the CRUD investigation in actual plant |
| No. | 2012 - 01 |
|---|---|
| Publication Date | July 2012 |
| Media | ASME PVP 2012 |
| Title | A round robin program of master curve evaluation using miniature C (T) specimens-1st report : Effect of test machine and detailed testing procedure |
| No. | 2010 - 05 |
|---|---|
| Publication Date | October 2010 |
| Media | NUTHOS-8 |
| Title | Sub-channel analysis of TRU fuel fabrication coupled with multi-dimensional thermal hydraulics |
| No. | 2010 - 04 |
|---|---|
| Publication Date | October 2010 |
| Media | NPC2010 |
| Title | Study for highly functional resin (macro porous resin) superior in removing micro particles PWR primary circuit: on site test |
| No. | 2010 - 03 |
|---|---|
| Publication Date | October 2010 |
| Media | NPC2010 |
| Title | ZINC INJECTION DURING HOT FUNCTIONAL TEST (HFT) IN UNIT3 |
| No. | 2010 - 02 |
|---|---|
| Publication Date | September 2010 |
| Media | 2010 LWR Fuel Performance/TopFuel/WRFPM |
| Title | Irradiation behavior of MOX fuel under high burnup |
| No. | 2010 - 01 |
|---|---|
| Publication Date | September 2010 |
| Media | Journal of Nuclear Science and Technology, Volume 47 |
| Title | Development of sub-channel analysis tool for TRU fuel fabrication |
| No. | 2009 - 04 |
|---|---|
| Publication Date | January 2010 |
| Media | Journal of Nuclear Materials, Volume 396 |
| Title | Relationship between changes in the crystal lattice strain and thermal conductivity of high burnup UO2 pellets |
| No. | 2009 - 03 |
|---|---|
| Publication Date | July 2009 |
| Media | ICONE17 |
| Title | Study on spacer grid span pressure loss under high Reynolds number flow condition |
| No. | 2009 - 02 |
|---|---|
| Publication Date | May 2009 |
| Media | ICAPP2009 |
| Title | Study on innovative fast reactor utilizing hydride neutron absorber -Development of coating technique on cladding inner surface- |
| No. | 2009 - 01 |
|---|---|
| Publication Date | May 2009 |
| Media | ICAPP2009 |
| Title | Development of the cooling technology on TRU fuel pin bundle during fuel fabrication process (4) Steady state cooling test of full mock up fuel pin bundle |