Zobrazeno 1 - 10
of 60
pro vyhledávání: '"Masakazu Fujitsuka"'
Publikováno v:
International Journal of Pressure Vessels and Piping. 86:693-698
The creep rupture behavior and the effects of oxidation on the creep strength of ASME T23 steel have been investigated. At 625 °C and 650 °C, a greater degradation of long-term creep strength was observed than expected from conventional master curv
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42de7ff01073082e13cf337a0abcee65
https://doi.org/10.1016/j.ijpvp.2009.03.001
https://doi.org/10.1016/j.ijpvp.2009.03.001
Publikováno v:
Materials Letters. 57:2950-2953
The thermal conductivities of W and W–Re alloys with Re contents of up to 25% were obtained from their thermal diffusivity data. The W and W–Re alloys were fabricated by powder metallurgy process. The samples with 8-mm diameter and 1-mm thickness
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5dab87c213ea7a80371c69a4bb9aab72
https://doi.org/10.1016/s0167-577x(02)01403-9
https://doi.org/10.1016/s0167-577x(02)01403-9
Publikováno v:
Journal of Nuclear Materials. :426-430
W–5% Re–HfC alloys with aimed HfC contents of 0.5, 1 and 3 wt% were fabricated by powder metallurgy. Their thermal diffusivity and lattice constant were measured before and after neutron irradiation at 330 K up to a fast neutron (E>1 MeV) fluence
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f04d02fd0b598c0aad86811536a58986
https://doi.org/10.1016/s0022-3115(02)01099-1
https://doi.org/10.1016/s0022-3115(02)01099-1
Publikováno v:
Journal of Nuclear Materials. :1148-1151
Thermal diffusivities of W–Re alloys were examined before and after neutron irradiation by a laser-flash method. W and W–Re alloys (up to 25 mass% Re) were irradiated in the Japan materials test reactor (JMTR) reactor at 330 K to thermal and fast
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6208240c27a29d08fa19513681b0c72
https://doi.org/10.1016/s0022-3115(00)00170-7
https://doi.org/10.1016/s0022-3115(00)00170-7
Publikováno v:
Journal of Nuclear Materials. :638-644
In view of the recent interest in high Z materials as plasma facing materials, high heat load tests were performed on tungsten and tungsten containing alloys such as WRe and TaW. The dimensions of the specimens were 20 mm Φ × 1 – 10 mm thic
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3805a1fe92623fac7269f682f0f6b3a2
https://doi.org/10.1016/s0022-3115(96)00102-x
https://doi.org/10.1016/s0022-3115(96)00102-x
Publikováno v:
Journal of Nuclear Materials. :1140-1143
Carbon-boron-titanium compounds were synthesized by hot press and subsequent HIP (high temperature isostatic press) treatment for application as plasma facing material. The thermal diffusivity of the compounds was measured by conventional and advance
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ad9e09150b8697d0040fc7da10f3d4b1
https://doi.org/10.1016/s0022-3115(06)80211-4
https://doi.org/10.1016/s0022-3115(06)80211-4
Publikováno v:
Journal of Nuclear Materials. :382-385
The carbon-boron-titanium compounds were synthesized by hot press and subsequent HIP (high temperature isostatic press) treatment. The thermal diffusivity of the compounds was measured by the advanced laser-flash technique, and the heat-load shock re
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a584122642f7b90cb0ccaa684103db21
https://doi.org/10.1016/s0022-3115(09)80071-8
https://doi.org/10.1016/s0022-3115(09)80071-8
Publikováno v:
Journal of Nuclear Materials. :611-615
We are developing carbon-boron compounds for use as a plasma facing material and highly pure carbon-fiber silicon carbide composites as a low-activation first-wall material. To study the irradiation behavior of these materials, samples have been irra
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::547f22910018ef5713b2f2694aa6c5f8
https://doi.org/10.1016/s0022-3115(09)80119-0
https://doi.org/10.1016/s0022-3115(09)80119-0
Publikováno v:
TANSO. 1992:91-97
C-B-Ti composite ceramic materials have some preferable properties including high melting point as the inner wall materials of nuclear fusion devices, but their thermal shock resistances are not well known. In this experiment, those materials were fa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5f1affda591d4a135e9cd82e80abb5b4
https://doi.org/10.7209/tanso.1992.91
https://doi.org/10.7209/tanso.1992.91
