Doryokuro Kakunenryo Kaihatsu Jigyodan

Kobe Steel, Ltd.

Sumitomo Metal Industries, Inc.

Toyohashi University of Technology

Toshio Nishida

Hiroshi Teranishi

Masayuki Fujiwara

Susumu Hirano

Shigeo Nomura

Itaru Shibahara

Takanari Okuda

Masahiko Morinaga

Yoshinori Murata

Yuji Enokido

Motoharu Nakajima

Aturou Iseda

Yoshinori Tateishi

Makoto Harada

Sakae Shikakura

Shigeharu Ukai

A high-Ni austenitic stainless steel having swelling resistance, high-temperature creep strength, and phase stability under irradiation. The irradiation resistance and high-temperature strength of the high-Ni austenitic stainless steel are enhanced when it is composed of the following percentages by weight: Si, not exceeding 0.5 wt. %; Mn, not exceeding 1.0 wt. %; Cr, 13-18 wt. %; Ni, 30-50 wt. %; Mo+W=2.0-6.0 wt. %; Nb+V=0.1-0.8 wt. % (Nb/(Nb+V) �weight ratio!=0.20-0.85 �weight ratio!; N, 0.01-0.2 wt. %; and the residual consisting of Fe and unavoidable impurities.

High-Ni austenitic stainless steel having excellent high-temperature

A dispersion strenghened ferritic steel having excellent ductility and toughness which has been heat treated to produce a matrix having a tempered martensitic structure composed of 0.05 to 0.25% by weight of carbon, 0.1% by weight or less of silicon , 0.1% by weight or less of manganese, 8 to 12% by weight of chromium, 0.1 to 4.0% by weight in total of molybdenum and tungsten, and 0.02% by weight or less of oxygen (exclusive of oxide particles) with the balance being iron and inevitable impurities and, homogeneously dispersed in the matrix, composite oxide particles comprising Y.sub.2 O.sub.3 and TiO.sub.2 in an amount of 0.1 to 1.0% by weight in total of Y.sub.2 O.sub.3 and TiO.sub.2 and a TiO.sub.2 to Y.sub.2 O.sub.3 molar ratio of 0.5 to 2.0.

Dispersion strengthened ferritic steel for high temperature structural

A dispersion strengthened ferritic steel cladding tube for use in a nuclear reactor and having a double-layer structure is provided. The cladding tube comprises a tube body made of a dispersion strengthened ferritic steel having a ceramic dispersed therein and containing 8 to 13% by weight of chromium. The inner surface of the tube body is lined with a ferritic steel containing 18 to 30% by weight of chromium. The cladding tube has not only excellent compatibility with a mixed oxide fuel but also excellent high temperature strength and swelling resistance. A method of producing the cladding tube using powder metallurgy is also provided.

Dispersion strengthened ferritic steel cladding tube for nuclear reactor

Growing community of inventors

Kobe, Japan

Toshio Nishida