Mitsubishi Heavy Industries Limited

The Tokyo Electric Power Company, Incorporated

Yasuhiro Sakaguchi

Kazuo Murakami

Toyoaki Yasui

Katsunari Ohsono

Toshiro Kobayashi

Tomikane Saida

Tadashi Kimura

Masaki Taneike

Toshio Yonezawa

Masaharu Minami

Takeshi Yokoyama

Shunichi Suzuki

Shinji Ookame

Tatsumi Takahashi

Hiroshi Kanasaki

Toshihiko Iwamura

Kazuo Asada

Naoki Tokizane

Kazuhisa Shibue

Hidehito Mimaki

Kenrou Takamori

Suguru Ooki

Naoki Anahara

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

A radioactive-material container includes a container body that shields nuclear radiation, which includes a cavity that stores a basket containing a recycle fuel assembly, a lid that covers the cavity, and a metal gasket that includes a sealing area that makes a physical contact with the container body and the lid. The sealing area has a specific shape that disperses tightening stress acting on the metal gasket for a sealing.

Radioactive-material container, metal gasket for sealing the radioactive-material container, and method of manufacturing the metal gasket

A basket has a lattice-like section for accommodating individual used nuclear fuel in predetermined positions in a cask. The basket is made from aluminum composite material having good neutron absorption ability, excellent mechanical property and workability. The aluminum composite material is made by having, in an Al or Al alloy base phase, B or B compound with a neutron absorption ability and an additive element, e.g. Zr or Ti, for giving a high strength property, and subjecting to a sintering under pressure.

Aluminum composite material, manufacturing method therefor, and basket and cask using the same

An aluminum powder is mixed with a neutron absorber powder through cold isostatic press to form a preliminary molding. The preliminary molding is then subjected to sintering under no pressure in vacuum. After sintering, a billet is subjected to induction heating and hot extrusion to form a square pipe.

Method of manufacturing a radioactive-substance storage member, billet for use in extrusion of the same, and square pipe

A rectangular pipe is molded by mixing aluminum powder with powder of a neutron absorbing material, molding a premolded body by means of cold isostatic pressing (CIP), canning the premolded body, sintering the premolded body by means of hot isostatic pressing (HIP), performing outer cutting and end face cutting on the can after the sintering, taking a billet out of the can, and extruding this billet.

Manufacturing method for spent fuel storage member and mixed power

The present invention provides an aluminum composite material having neutron absorbing power that improves the ability to absorb neutrons by increasing the content of B, while also being superior to materials of the prior art in terms of mechanical properties and workability. The aluminum composite material having neutron absorbing power contains in Al or an Al alloy matrix phase B or a B compound having neutron absorbing power in an amount such that the proportion of B is 1.5% by weight or more to 9% by weight or less, and the aluminum composite material has been pressure sintered.

Aluminum composite material having neutron-absorbing ability

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Hyogo, Japan

Yasuhiro Sakaguchi