Hitachi, Ltd.

Nippon Engelhard Ltd.

Kiyomi Funabashi

Makoto Kikuchi

Tetsuya Matsui

Yoshiaki Ichikawa

Koichi Chino

Akira Sekine

Takako Oono

Fumio Kawamura

Tsutomu Baba

Hideo Yusa

Takashi Nishi

Masami Matsuda

Toshio Takagi

Osamu Kuriyama

Shin Tamata

Shunsuke Uchida

Kunio Kamiya

Tetsuo Fukasawa

Katsumi Ohsumi

Susumu Horiuchi

Naohito Uetake

Tomohiro Sato

Tatsuo Izumida

Takashi Ikeda

Hiroyuki Tsuchiya

Kenji Motojima

Masato Ohura

Megumu Urata

Itaru Komori

Tetsuro Adachi

Mitsuyoshi Ichimura

Makoto Kikushi

Akira Sasahiro

Shin Tamada

Morimasa Hashimoto

A chemical substance total management system aids for reduction of release and transferring amount of managing substances in business entities. The system retrieves releasing and transferring amount record relating to predetermined managing substance on the basis of total tabulation link information with correlation between the tabulation result record managing releasing and transferring amount of managing substance per releasing and transferring destination and releasing and transferring amount record to be a source generating tabulation result record.

Chemical substance total management system, storage medium storing chemical substance management program and chemical substance total management method

The present invention relates to a method of solidifying radioactive waste with cement, comprising forming a mixture comprising water, a hydrophilic material and cement substantially non-shrinkable or expansible with respect to volume change upon hardening, mixing said mixture with the radioactive waste, followed by hardening to form a solid body. The present invention enables the formation of a compact solid body having voids, such as capillary voids, of reduced volume, which makes it possible to reduce the leaching rate of hazardous materials. Further, since no shrinkage accompanies hardening, no tensile stress occurs in the cement surrounding minute waste particles within the hardened material, thereby enabling a decrease in the strength of the solid body to be minimized. This in turn enables an increase in the amount of packing of waste. Prior addition of a hydrophilic material enables the cement fluidity before hardening to be maintained even after complete absorption of water by a water absorptive waste. This is extremely advantageous in carrying out hardening.

Method for solidifying radioactive waste

The present invention adds carbonates or chlorides of alkaline earth metals to the radioactive wastes containing sodium sulfate and subjects sulfate group in the radioactive wastes to reduction treatment, thereby converts the sulfate group into sulfides of alkaline earth metals which are chemically stable substances while suppressing SOx generation, and solidifies the radioactive wastes stably for an extended period of time by applying to the converted radioactive wastes solidifying treatment.

Disposal method of radioactive wastes

A method of solidifying a radioactive waste of an atomic power plant, for example, begins with concentrating the liquid waste to powder or pellet form to reduce its volume. Prior to reducing its volume, an estimation is made of what the concentration will be once the liquid waste is converted into powdered or pelletized form. The powdered or pelletized waste is charged into a container, and a solidifying agent is poured over the contents to form a solidified body. The solidifying agent is prepared to have a desired coefficient of distribution that is determined in accordance with the estimated concentration of the reduced volume solidified waste so that the amount of leaching of the solidified body that is produced will be less than or equal to a predetermined value, such as the known value of leaching for a conventional cement-solidified waste that is not processed to reduce its volume before being solidified.

Method and apparatus for solidifying radioactive waste

Method of cementing radioactive waste and cemented body

Method for solidifying radioactive wastes

A process and an apparatus for cleaning nuclear reactor cooling water with cation exchange resin whose ion-exchanging groups have a bonding energy of not more than 300 KJ/mole are disclosed, whereby the radiation exposure of operators in an atomic power plant can be considerably reduced, and the waste ion exchange resin can be readily disposed.

Process and apparatus for cleaning nuclear reactor cooling water

The present invention relates to a method and an apparatus for producing a waste package of radioactive waste containing particles of radioactive waste material of low modulus of elasticity, particles of radioactive waste material of high modulus of elasticity, and a solidifying agent in which the particles of radioactive waste material of low modulus of elasticity and the particles of radioactive waste material of high modulus of elasticity are fixed in an almost uniformly dispersed state. According to this invention, the radioactive waste generated from nuclear power plants can be greatly reduced in volume and also a waste package of radioactive waste with high strength and excellent water resistance can be obtained.

Radioactive waste treatment method

An inorganic adsorbent comprising a porous titanium metal and titanium oxide sintered and impregnated on the surfaces of micropores of the porous titanium metal can be produced by impregnating the porous titanium metal with a titanium alkoxide solution, followed by hydrolysis and oxidation to give titanium oxide, and can be used for selectively removing transition metal ions in a water coolant of nuclear reactor.

Inorganic adsorbent and process for production thereof

A solid radioactive waste can be solidified by a process comprising packing a solid radioactive waste in a container, adding to the container an aqueous solution comprising an alkali silicate, a hardening agent and a fluidity-improving agent for the aqueous solution and conducting the solidification of the alkali silicate, the resulting solidified radioactive waste being excellent in weather resistance, showing no cracks and having sufficient strength.

Process for solidifying radioactive waste

Growing community of inventors

Hitachinaka, Japan

Kiyomi Funabashi