The patent badge is an abbreviated version of the USPTO patent document. The patent badge does contain a link to the full patent document.

The patent badge is an abbreviated version of the USPTO patent document. The patent badge covers the following: Patent number, Date patent was issued, Date patent was filed, Title of the patent, Applicant, Inventor, Assignee, Attorney firm, Primary examiner, Assistant examiner, CPCs, and Abstract. The patent badge does contain a link to the full patent document (in Adobe Acrobat format, aka pdf). To download or print any patent click here.

Date of Patent:
May. 30, 2017

Filed:

Jul. 31, 2009
Applicants:

Koji Mizuguchi, Kawasaki, JP;

Reiko Fujita, Nerima-Ku, JP;

Kouki Fuse, Ota-Ku, JP;

Hitoshi Nakamura, Yokohama, JP;

Kazuhiro Utsunomiya, Yokohama, JP;

Nobuhiko Tanaka, Yokohama, JP;

Inventors:

Koji Mizuguchi, Kawasaki, JP;

Reiko Fujita, Nerima-Ku, JP;

Kouki Fuse, Ota-Ku, JP;

Hitoshi Nakamura, Yokohama, JP;

Kazuhiro Utsunomiya, Yokohama, JP;

Nobuhiko Tanaka, Yokohama, JP;

Assignee:
Attorney:
Primary Examiner:
Int. Cl.
CPC ...
C02F 1/38 (2006.01); C25C 1/00 (2006.01); C25C 7/00 (2006.01); C25B 15/00 (2006.01); G21C 19/46 (2006.01); B01D 11/04 (2006.01); B01D 17/02 (2006.01);
U.S. Cl.
CPC ...
G21C 19/46 (2013.01); B01D 11/0434 (2013.01); B01D 17/0217 (2013.01); Y02W 30/883 (2015.05);
Abstract

A spent nuclear fuel is reprocessed by dissolving a spent nuclear fuel in an aqueous nitric acid solution and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A spent nuclear fuel reprocessing method includes: an electrolytic valence adjustment step in which nuclides contained in the fuel solution is electrolytically reduced without removing fission products or minor actinides until valence of plutonium is at a level at which solvent extraction efficiency is low by using the valence of plutonium contained in the fuel solution as a parameter; and a nuclide separation step in which, by using an extraction solvent which extracts uranium contained in the fuel solution, uranium is distributed from the fuel solution subjected to the electrolytic valence adjustment step to the extraction solvent.


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