Institute of Nuclear TechnologyWorking to further enhance the safety
and reliability of nuclear power

Working to further enhance the safety and reliability of nuclear power

Institute of Nuclear Technology

Katsuhiko Fujii

Institute of Nuclear TechnologyNuclear Power Plant Aging Research CenterMaterial Technology GroupLeader

Research Articles

201825075090 Influence of long-term thermal aging and irradiation on microstructure of austenitic stainless steel welds
201724109119 Influence of Solute Elements on Radiation Embrittlement of Reactor Vessel Steels
201623070078 Solute Cluster Formation in Austenitic Stainless Steel under Neutron Irradiation
201522084091 APT analysis of stainless steel welds after long-term thermal aging and neutron irradiation
201421108117 Atom Probe Tomography Characterization of Neutron Irradiated Austenitic Stainless Steel
201320118124 Atom Probe Tomography Characterizations of Medium-Cu Reactor Pressure Vessel Steels from a PWR Surveillance Test Program
201219144154 Effects of Irradiation on Duplex Stainless Steels
201118198210 Development of a Tensile Testing Device under Ion Irradiation and Study on Effect of Stress on Radiation Embrittlement
201017172177 Development ofmicro tensile testing method in an FIB system for evaluating grain boundary strength
200916160168 Effects of Solute Elements on Irradiation Hardening and Microstructural Evolution in Low Alloy Steels
200815172187 Microstructural Evolution in Low Alloy Steels after High Dose Ion Irradiation(2)
200815141151 Role of Intergranular Oxidation on PWSCC of Nickel Based Alloys
200613137146 Microstructural evolution in low alloy steels under high dose ion irradiation
200512240250 Microstructural evolution in low alloy steels under low dose neutron irradiation
200411173181 Characterization of matrix damage in ion-irradiated reactor vessel steel
200310186197 Microstructural Evolution in A533B Steels under Electron Irradiation
200209162170 Characterization of SCC Crack Tips and Surface Oxide Layers in Alloy 600
200108143150 Characterization of SCC Crack Tip and Hydrogen Distribution in Alloy 600
200007118128 Swelling of SUS 304 and SUS 316 Stainless Steels under Heavy Ion Irradiation