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Publications by Masakatsu MATSUMOTO
Evaluation of JIC Fracture Toughness of Nuclear Reactor Pressure Vessel Steels by Three-Point Bend Specimens
Tetsu-To-Hagane/Journal of the Iron and Steel Institute of Japan
Alloys
Condensed Matter Physics
Metals
Theoretical Chemistry
Materials Chemistry
Physical
Application of D. C. Electrical Potential Method for Measurement of J-R Curve by a Single Specimen
Tetsu-To-Hagane/Journal of the Iron and Steel Institute of Japan
Alloys
Condensed Matter Physics
Metals
Theoretical Chemistry
Materials Chemistry
Physical
Related publications
Evaluation of Plane Strain Fracture Toughness of Neutron-Irradiated A533B Steels in Nuclear Reactor Vessel Surveillance Test
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
DEVELOPMENT OF TEST PROCEDURES. FRACTURE TOUGHNESS OF REACTOR PRESSURE VESSEL STEELS. Progress Report, May 1, 1965-July 31, 1965
Comparison of Fracture Toughness Values of Normal and High Strength Concrete Determined by Three Point Bend and Modified Disk-Shaped Compact Tension Specimens
Frattura ed Integrita Strutturale
Mechanics of Materials
Mechanical Engineering
Temperature Dependence of JIC Fracture Toughness Values in the Structural Steels and Evaluation of the Testing Method
Tetsu-To-Hagane/Journal of the Iron and Steel Institute of Japan
Alloys
Condensed Matter Physics
Metals
Theoretical Chemistry
Materials Chemistry
Physical
Modeling Pressure Vessel Toughness With Various Small Specimens
Fracture Toughness of Narrow-Gap Welded Joints in the Nuclear Pressure Vessel Steel 22 NiMoCr 37
Nuclear Engineering and Design
Materials Science
Risk
Mechanical Engineering
Waste Management
Nuclear
Nuclear Energy
High Energy Physics
Engineering
Reliability
Safety
Disposal
Quality
Evaluation of Fracture Toughness of Structural Steels Through J Integral
Tetsu-To-Hagane/Journal of the Iron and Steel Institute of Japan
Alloys
Condensed Matter Physics
Metals
Theoretical Chemistry
Materials Chemistry
Physical
Relating Bend Formability and Fracture Toughness
FRACTURE MECHANICS EVALUATION OF REACTOR VESSEL STEELS. Quarterly Progress Report for the Period Ending December 31, 1967.
