Mitsubishi Jukogyo Kabushiki Kaisha

Mitsubishi Heavy Industries Limited

Sumitomo Metal Industries, Inc.

Nkk Corporation

The Tokyo Electric Power Company, Incorporated

Mitsubishi Metal Corporation

Toshio Yonezawa

Yasutaka Okada

Hiroo Nagano

Kazuo Yamanaka

Hiroshi Susukida

Nobuya Sasaguri

Kichiro Onimura

Toshihiko Iwamura

Koji Fujimoto

Takao Minami

Hiroshi Kanasaki

Mamoru Inoue

Katsuji Kawaguchi

Koji Takahashi

Saburo Wakita

Akira Mitsuhashi

Yoshikuni Kadoya

Masaki Taneike

Yutaka Moriya

Haruo Suzuki

Takemi Yamada

Ikumasa Koshiro

Shunichi Suzuki

Katsumi Masamura

Yasuhiro Sakaguchi

Takashi Shige

Junji Hoshi

Yaautaka Okada

Takaya Kusakabe

Noritake Yamaguchi

Hidehito Mimaki

Toshiyuki Shimamura

Toru Inazumi

Kenrou Takamori

Naotake Ito

Suguru Ooki

Kazuhide Ajiki

Shizuo Nakada

Naoki Anahara

Mitsuhiro Nakamura

Naoki Hiranuma

There are provided an austenitic stainless steel having high stress corrosion crack resistance, characterized by containing, in percent by weight, 0.030% or less C, 0.1% or less Si, 2.0% or less Mn, 0.03% or less P, 0.002% or less S, 11 to 26% Ni, 17 to 30% Cr, 3% or less Mo, and 0.01% or less N, the balance substantially being Fe and unavoidable impurities; a manufacturing method for an austenitic stainless steel, characterized in that a billet consisting of the said austenitic stainless steel is subjected to solution heat treatment at a temperature of 1000 to 1150&#xb0; C.; and a pipe and a in-furnace structure for a nuclear reactor to which the said austenitic stainless steel is applied.

Austenitic stainless steel, manufacturing method for the same, and structure using the same

An austenitic stainless steel having resistance to neutron-irradiation-induced deterioration obtained by subjecting a stainless steel consisting of not more than 0.08% by weight of C, not more than 2.0% by weight of Mn, not more than 1.5% by weight of Si, not more than 0.045% by weight of P, not more than 0.030% by weight of S, 8.0 to 22.0% of by weight Ni, 16.0 to 26.0% of by weight Cr and the balance as Fe; to thermal solid solution treatment at a temperature of 1,000&deg; C. to 1,180&deg; C. and then subjecting the so-treated steel to aging treatment at a temperature in the range of 600&deg; C. to 750&deg; C.

Austenitic stainless steel resistant to neutron-irradiation-induced deterioration and method of making thereof

This invention relates to a spray coating powder material which, when applied to gas turbines using a crude low-quality fuel oil as fuel, has sufficiently higher corrosion resistance to sulfur, vanadium, sodium and other substances that accelerate corrosion in a high-temperature service environment, than conventional materials such as Ni-50 Cr and MCrAlY materials, as well as high-temperature components coated therewith. Specifically, this invention relates to a spray coating powder material comprising, on a weight percentage basis, greater than 45% and up to 60% of chromium, 5 to 15% of aluminum, 0.5 to 10% of zirconium, and the balance comprising cobalt or iron, or both, and incidental impurities, as well as high-temperature components coated therewith. This material can yield a sprayed coating having high corrosion resistance to sulfur, vanadium, sodium and other substances that accelerate corrosion in a high-temperature service environment.

Spray coating powder material and high-temperature components coated therewith

High-nickel austenitic stainless steel resistant to degradation by

Ferrous group shape memory alloys consisting essentially of Cr: 16.0-21.0 wt %, Si: 3.0-7.0 wt % and Ni: 11.0-21.0 wt % and satisfying Ni wt %.gtoreq.[0.67.times.{Cr+1.2.times.(Si+Ti+Zr+Hf+V+Nb+Ta)}-] wt % and (Cr+Si) wt %.gtoreq.20 wt %, these ferrous-group shape-memory alloys having a corrosion resistance, a shape-memorizing properties, an intergranular corrosion resistance and a stress corrosion cracking resistance in nitric acid for nuclear fuel reprocessing plants and high-temperature, high-pressure water for light-water reactors.

Fe-Cr-Ni-Si shape memory alloys with excellent stress corrosion cracking

A precipitation strengthening type nickel base single crystal alloy, which consists essentially of, on a weight percent basis,

Precipitation hardening nickel base single crystal cast alloy

The present invention is concerned with a high-strength Ni-based alloy excellent in resistance to stress corrosion cracking in high-temperature high-pressure water, characterized by consisting essentially of, in terms of weight ratio, 0.08% or less of C, 0.15% or less of Si, 0.1 to 1% of Mn, 15% or less of Fe, 20 to 30% of Cr, 3.5% or less of Ti, 2% or less of Al, 7% or less of Nb and the balance of Ni, having at least one of a .gamma.' phase and a .gamma.' phase in a .gamma. base, and semicontinuously predominantly precipitating M.sub.23 C.sub.6 in grain boundaries; a method for preparing this high-strength Ni-based alloy by heating and maintaining the alloy having the identical composition at 980.degree. to 1,200.degree. C., cooling it, and subjecting it once or more to an aging treatment of additionally heating and maintaining it at 550.degree. to 850.degree. C.; a method for preparing the aforesaid alloy by heating and maintaining the alloy having the identical composition at 980.degree. to 1,200.degree. C., cooling it, subjecting it to a cold working at a 10% or more reduction of area, and subjecting it once or more to an aging treatment of additionally heating and maintaining it at 550.degree. to 850.degree. C.; and a method for preparing the aforesaid alloy by subjecting the alloy having the identical composition to a hot working at 850.degree. to 1,250.degree. C. at a draft percentage of 20% or more, heating and maintaining the alloy at 980.degree. to 1,200.degree. C., cooling it, and subjecting it once or more to an aging treatment of additionally heating and maintaining it at 550.degree. to 850.degree. C.

Ni-based alloy and method for preparing same

A nickel-chromium alloy excellent in a stress corrosion cracking resistance which is obtained by carrying out an annealing treatment under specific conditions, said alloy having the following composition:

Nickel-chromium alloy in stress corrosion cracking resistance

An alloy for heat transfer pipes excellent in an alkali stress corrosion cracking resistance which is obtained by heating and retaining said alloy at a temperature within the range of a temperature (T.degree.C.), at which a carbide in said alloy is thoroughly solubilized, to T+100.degree. C. for 1 minute or more; cooling it once to a level of 200.degree. C. or less; and carrying out a thermal treatment under conditions within a hatched range Z in FIG. 2, said alloy comprising: in terms of % by weight, 0.15% or less of C; 1.0% or less of Si; 1.0% or less of Mn; 25 to 35% of Cr; 40 to 70% of Ni; 0.5% or less of Al; 0.01 to 1.0% of Ti; 0.5 to 5.0%, in all, of one or more of Mo, W and V; 0.30% or less of P; 0.020% or less of S; and the residue of Fe and impurities.

Method for thermal treatment of alloy for heat transfer pipes

A method for a thermal treatment of a nickel based alloy, characterized in that said nickel based alloy for a material which will be subjected to a high-temperature and high-pressure water or vapor comprises, in terms of % by weight, 58% or more of Ni, 25 to 35% of Cr, 0.003% or less of B, 0.012 to 0.035% of C, 1% or less of Mn, 0.5% or less of Si, 0.015% or less of P, 0.015% or less of S, and the residue of Fe and usual impurities; in a first thermal treatment process, said nickel based alloy is heated and retained at a temperature of T.degree. C. to (T+100).degree.C. and is cooled at a cooling rate of a furnace cooling rate or more; and in a second thermal treatment process, said nickel based alloy is then retained at a temperature of 600.degree. to 750.degree. C. and at a temperature within a sensitization recovery range for a period of 0.1 to 100 hours and is cooled at a cooling rate of said furnace cooling rate or more.

Method for thermal treatment of nickel based alloy materials

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Takasago, Japan

Toshio Yonezawa