24 results on '"Shohei KAWANO"'
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2. Development of mechanical model of droplet erosion on martensite stainless steel containing 15 % Cr
3. Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components
4. Simulation of Radiation Induced Grain Boundary Segregation in Stainless Steels under Boiling Water Reactor Conditions
5. Re-weldability of neutron irradiated Type 304 and 316L stainless steels
6. Post-irradiation annealing effect on helium diffusivity in austenitic stainless steels
7. Effect of weld thermal cycle, stress and helium content on helium bubble formation in stainless steels
8. Weld repair technique of helium‐containing reactor structural materials
9. Space charge behavior in multilayered polyimide films under DC high stress near breakdown strength
10. Weld Repair Technique of Helium-Containing Reactor Structural Materials
11. Effect of weld thermal cycle and restraint stress on helium bubble formation in stainless steels
12. Weldability of Neutron-Irradiated Stainless Steel and Nickel-Base Alloy
13. Weldability of helium-containing stainless steels using a YAG laser
14. Simulation of helium bubble behavior in neutron-irradiated stainless steel during welding
15. Charge behavior of epoxy/silica nanocomposites under AC high fields
16. Space charge accumulation characteristics in multilayered polyimide films under DC high stress
17. Development of Ultrasonic Shot Peening Technique for Reactor Components to Improve Structural Integrity Against Stress Corrosion Cracking
18. Thick Plate Welding of Irradiated Stainless Steel
19. Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components (III)
20. Development of Underwater Laser Cladding and Underwater Laser Seal Welding Techniques for Reactor Components (II)
21. 3P2-X01 Flexible and partially stretchable pulse wave measuring device with mesh structure(Nursing and Mechatronics)
22. Laser de-sensitization treatment for inside surface of SUS304 stainless steel pipe welds in nuclear power plants
23. OS8-02 Development of Internal CRD with Ceramics Insulated Heat Proof Coil : (2) Endurance and Robustness Tests of Bearing Materials in High Temperature Water
24. ICONE11-36508 DEVELOPMENT OF INTERNAL CRD FOR NEXT GENERATION BWR
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