Zobrazeno 1 - 10
of 49
pro vyhledávání: '"Johsei Nagakawa"'
Publikováno v:
Journal of Nuclear Materials. 417:120-123
In situ stress-controlled fatigue tests were performed for F82H steels under 17 MeV proton irradiation with an energy degrader at 60 °C. The energy degrader enhanced the hydrogen implantation rate from 2.6 × 10 −6 to 1.3 × 10 −3 appm/s at a do
Publikováno v:
Journal of Nuclear Materials. :264-267
Although fusion blankets are exposed to severe irradiation, its rear side would stay at rather a modest condition. In this research, the irradiation-induced deformation of F82H IEA-heat steel at 300 °C was examined. A torsion creep apparatus with a
Publikováno v:
MATERIALS TRANSACTIONS. 50:740-743
In order to contribute to the development of first wall/blanket structural materials in nuclear fusion reactors, we have assessed the influence of nuclear-transmutational helium, which is widely known to often induce grain boundary embrittlement at h
Publikováno v:
MATERIALS TRANSACTIONS. 49:2243-2246
Stress-controlled fatigue tests were performed for 5% and 15% cold-worked 304 stainless steels under in-situ irradiation with 17 MeV protons at 300°C. Increase of fatigue life with prolonged crack propagation length under in-situ irradiation was det
Publikováno v:
Journal of Nuclear Materials. :910-914
Austenitic stainless steels will be used in ITER as a major structural material. Although, initially supplied in annealed condition, cold-working is inevitable during construction or operation. Martensite would be introduced by cold-work in the case
Publikováno v:
Journal of Nuclear Science and Technology. 43:669-674
SUS 304 stainless steel has been used in the light-water reactors constructed in earlier days, in which irradiation-assisted stress corrosion cracking has drawn increasing attention and tensile residual stress is believed to be one of the major cause
Publikováno v:
Fusion Engineering and Design. 81:999-1003
Load-controlled fatigue tests in tension–tension mode were performed for the side-notched 20% cold-worked 316 stainless steel in the in-beam and post-irradiation conditions with 17 MeV protons at 300 °C. Fatigue life in the in-beam tests was almos
Publikováno v:
Journal of Nuclear Materials. 334:104-108
Influence of helium on creep rupture properties of a reduced activation 9Cr3WVTaB martensitic steel for fusion applications has been examined. Homogeneous helium implantation using α-particle irradiation at an accelerator was adopted to simulate tra
Publikováno v:
Journal of Nuclear Materials. :416-419
The influence of transmutational helium on creep response of a V–4Cr–4Ti reference alloy called NIFS-HEAT-2 was examined. This is a candidate structural material for future fusion applications. Helium ions were injected into creep specimens at 70
Publikováno v:
Journal of Nuclear Materials. :1066-1071
Stress-controlled fatigue tests were conducted for side-notched small specimens of F82H steel under in-beam and unirradiated conditions with 17 MeV protons at 500 °C. The environment for the fatigue tests was impure He gas containing 10–3000 ppm o