Hitachi-Ge Nuclear Energy, Ltd.

Hitachi, Ltd.

Mamoru Kamoshida

Hiroshi Nakano

Motoo Aoyama

Kazushige Ishida

Takashi Nishi

Masao Chaki

Masaru Sekihara

Kenji Noshita

Atsushi Yukita

Tetsuo Fukasawa

Kazuaki Kito

Masanori Takahashi

Masashi Oda

Takashi Asano

Akira Sasahira

Masashi Shimizu

Yuuko Kani

Takako Sumiya

Yusuke Kitamoto

Kiminori Iga

Youji Shibata

Nozomu Nagayama

Noriaki Takeshi

Motoki Nakane

Provided is a method of treating radioactive liquid waste which reduces the amount of radioactive waste to be generated and is capable of removing a radioactive nuclide from radioactive liquid waste to the extent that the concentration thereof is less than or equal to the measurement lower limit using a simple apparatus configuration. A filtration device is connected to a colloid removal device by a connection pipe. An adsorption tower positioned at the highest stream of an adsorption device is connected to the colloid removal device by a connection pipe. The colloid removal device includes an electrostatic filter. Respective adsorption towers in the adsorption device are sequentially connected by a pipe. A discharge pipe is connected to the adsorption tower positioned at the lowest stream of the adsorption device. Radioactive liquid waste, containing particles having a particle diameter of 1 &#x3bc;m or greater, negatively charged colloids, and a radioactive nuclide, is supplied to the filtration device. The particles having a particle diameter of 1 &#x3bc;m or greater are removed by the filtration device and the negatively charged colloids are removed by the electrostatic filter that is positively charged. The radioactive nuclide is removed by the adsorption tower.

Method of treating radioactive liquid waste and radioactive liquid waste treatment apparatus

Disclosed is a method for treating a radioactive organic waste, the radioactive organic waste including a cation exchange resin adsorbing radionuclide ions, the method including the step of bringing the radioactive organic waste into contact with an organic acid salt aqueous solution containing an organic acid salt and whereby desorbing the radionuclide ions from the cation exchange resin, in which the organic acid salt contained in the organic acid salt aqueous solution includes a cation that is more readily adsorbable by the cation exchange resin than hydrogen ion is. This enables reduction in concentration of a radioactive substance in the radioactive organic waste and reduction in amount of a high-dose radioactive waste.

Radioactive organic waste treatment method

Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to convert the uranium into UF, and the uranium is purified through a simple method of distilling the UFtogether with a absorbent. After removing the most part of the amount of uranium, the remaining nuclear fuel material is dissolved and then transferred to an extraction process to recover plutonium. By doing so, a small sized dry process can be employed as a uranium purification process. Since the nuclear fuel material is dissolved and extracted after removing most part of an amount of uranium, a volume of processing solution can be reduced and the machine installation scale can be made small. Accordingly, the reprocessing facility can be extremely downsized.

Method of reprocessing spent nuclear fuel

Neutron shielding materials and a cask for spent fuel

Growing community of inventors

Hitachi, Japan

Mamoru Kamoshida