Ngk Insulators, Inc.

Japan Atomic Energy Research Institute

Genshi Nenryo Kogyo Kabushiki Kaisha

Agency of Industrial Science and Technology Japan Atomic Energy Research

Hiroshi Kawamura

Naoki Sakamoto

Kiyotoshi Nishida

Yoshio Hasegawa

Minoru Uda

Yoshio Ito

Katsuyoshi Tatenuma

Munenori Uchida

Taketoshi Takeuchi

Shigeharu Yoshimuta

Etsuo Ishitsuka

A material for a nuclear fusion reactor of the present invention contains intermetallic compounds of beryllium with Ti, V, Zr, Nb, Ta, Mo, W or Y. The beryllium intermetallic compounds are mixed with another metal or intermetallic compound. The material is preferably applied to blankets and facing members which are exposed to neutrons and heat generated by plasma of the nuclear fusion reactor.

Material including beryllium intermetallic compound and having excellent high-temperature property applied to nuclear fusion reactor

For bonding pure beryllium to a copper alloy, a functionally gradient beryllium-copper material comprising a single layer or multiple layers having a thickness of 0.3-3.0 mm and containing at least 50 atomic % of Cu is inserted between the pure beryllium and the copper alloy to prevent bonding strength from degrading in the bonding process or during operation of a nuclear fusion reactor, by effectively mitigating formation of brittle intermetallic compounds and generation of thermal stress at the bonding interface.

Beryllium-copper bonding material

Process for preparing metallic beryllium pebbles

For bonding pure beryllium to a copper alloy, a beryllium-copper material comprising a single layer or multiple layers having a thickness of 0.3-3.0 mm and containing at least 50 atomic % of Cu is inserted between the pure beryllium and the copper alloy to prevent bonding strength from degrading in the bonding process or during operation of a nuclear fusion reactor, by effectively mitigating formation of brittle intermetallic compounds and generation of thermal stress at the bonding interface.

The invention provides a method for recovering metal beryllium from waste beryllium that has become radioactive in the reaction with neutrons, by converting the radioactive beryllium to halogenated beryllium with a halogen gas such as chlorine, bromine or iodine, and subsequently submitting the halogenated beryllium to thermal decomposition. In this way, the invention allows effective recovery of metal beryllium from waste, radioactive beryllium, thereby reducing production of radioactive wastes and ensuring an economical use of natural resources.

Method of recovering radioactive beryllium

High-purity, sintered spherical Li.sub.2 O granules is produced by a gel precipitation technique. Li.sub.2 CO.sub.3 powder is dispersed in an aqueous solution of a water-soluble resin, whose drops are transferred through a nozzle into a solidifying acetone bath. Spherical gel particles in which Li.sub.2 CO.sub.3 is dispersed are formed in the acetone bath. The spherical gel particles are dried, calcined, thermally decomposed and sintered.

Method for producing sintered lithium oxide granules

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Mito, Japan

Hiroshi Kawamura