Topics
News List
Award List
About INSS
Message From The President
Basic Principles
History Of INSS
Director
Advisory Committee
Organization
Recruit
Access・MAP
Institutes
Institute of Social Research
Research Center for Human Factors
Human Behavior Research Group
Organization and Culture Research Group
Research Project for Social Awareness and Energy Issues
Institute of Nuclear Technology
Nuclear Power Plant Aging Research Center
Thermal Hydraulics and Mechanics Group
Material Technology Group
Nuclear Power Information Research Project
Nuclear Safety and Emergency Support Research Project
Research Achievements
INSS JOURNAL
Publication & Event
Publication List
Event List
Award List
Access・MAP
Inquiry
LINK
JAPANESE
Custom Search
Institute of Nuclear Technology
Working to further enhance the safety
and reliability of nuclear power
Working to further enhance the safety and reliability of nuclear power
ホーム
>
ENGLISH
>
Institutes
>
Institute of Nuclear Technology
>
Nuclear Power Plant Aging Research Center
>
Material Technology Group
>
Staff
Staff
Institute of Nuclear Technology
Takuyo Yamada
Institute of Nuclear Technology
Nuclear Power Plant Aging Research Center
Material Technology Group
Research Articles
202330222230
SCC growth behavior in weld HAZ of austenitic stainless steels in a simulated PWR primary water - Current research status and future program -
202229139148
SCC Growth Behavior of Stainless Steel Weld Metals in Oxygenated High -Temperature Water -Influence of Thermal Aging, Temperature and Water Chemistry-
202128113120
The Effect of Microstructure on SCC behavior of SUS630 in High-temperature Water
202027187196
The effect of long-term thermal aging on SCC of SUS630 in high-temperature water
201926136144
SCC Growth Behavior of Welds and Cast of Stainless Steels in Oxygenated High-Temperature Water - Infl uence of Water Chemistry and Test Temperature -
201825091101
SCC Growth Behavior of SUS630 in High-Temperature Water(2nd report) - The eff ects of thermal aging, temperature and applied stress on SCC -
201724101108
SCC Growth Behavior of SUS630 in High-Temperature Water
201623145152
Infl uence of long-term thermal aging on SCC Behavior of Cast Stainless Steels and stainless steel weld metals in High-Temperature Water - Current research status and Future Program -
201522117128
SCC Growth Behavior of alloy 182 and 152 /SUS316 dissimilar metal weld joints in High-Temperature Water
201421133143
SCC growth behavior of cold worked alloy 690 in high-temperature water -Dependence of test temperature, dissolved hydrogen in water, grain boundary carbide and chemical composition-
201320149156
Role of cavity formation in SCC of cold worked carbon steel in high-temperature water ―Part 2: Study of crack initiation behavior―
201219108117
Thermal-aging evaluation of on site aged cast duplex stainless steel
201118158169
SCC Growth Behavior of Cast Stainless Steels in High-Temperature Water ― Influences of Corrosion Potential, Steel Type, Thermal Aging and Cold-Work ―
201017150158
SCC growth behavior of stainless steel weld heat-affected zone in hydrogenated high temperature water
200916127135
SCC Growth Behavior of Stainless Steel Weld Metals in High-Temperature Water ―Influence of Corrosion Potential, Weld Type, Thermal Aging, Cold-Work and Temperature―
200815217224
Effect of Cr content, hardness and micro structure on flow-accelerated corrosion in carbon steel pipes -Examination of replaced carbon steel pipes-
200714197210
Stress Corrosion Cracking of Stainless Steels under Deaerated High-Temperature Water − Influence of Grain Boundary Carbide Precipitation, and Effect of Mo and Cr in Alloys −
200613194204
Stress Corrosion Cracking of Stainless Steel under Deaerated High-Temperature Water - Influence of Grain Boundary Carbide Precipitation -
200512200206
Microstructural Observation of Cold Worked Austenitic Atainless Steel
200310141150
Influence of Thermal Aging on Primary Water Stress Corrosion Cracking of Cast Duplex Stainless Steel (Second Report) ― Consideration on Fractography after Slow Strain Rate Technique ―
200108125133
Influence of Thermal Aging on Primary Water Stress Corrosion Cracking of Cast Duplex Stainless Steels
200007145158
Study on Thermal Aging Mechanism of Cast Duplex Stainless Steel
Institutes
Institute of Social Research
Research Center for Human Factors
Human Behavior Research Group
Organization and Culture Research Group
Research Project for Social Awareness and Energy Issues
Institute of Nuclear Technology
Nuclear Power Plant Aging Research Center
Thermal Hydraulics and Mechanics Group
Material Technology Group
Nuclear Power Information Research Project
Nuclear Safety and Emergency Support Research Project