Method of recovering nuclear fuel material

Patent metadata

Field	Value
Publication number	US-10323330-B2
Application number	US-201715696275-A
Country	US
Kind code	B2
Filing date	Sep 6, 2017
Priority date	Jun 15, 2012
Publication date	Jun 18, 2019
Grant date	Jun 18, 2019

Abstract

According to an embodiment, a nuclear fuel material recovery method of recovering a nuclear fuel material containing thorium metal by reprocessing an oxide of a nuclear fuel material containing thorium oxide in a spent fuel is provided. The method has: a first electrolytic reduction step of electrolytically reducing thorium oxide in a first molten salt of alkaline-earth metal halide; a first reduction product washing step of washing a reduction product; and a main electrolytic separation step of separating the reduction product. The first molten salt further contains alkali metal halide, and contains at least one out of a group consisting of calcium chloride, magnesium chloride, calcium fluoride and magnesium fluoride. The method may further has a second electrolytic reduction step of electrolytically reducing uranium oxide, plutonium oxide, and minor actinoid oxide in a second molten salt of alkali metal halide.

First claim

What is claimed is:

1. A nuclear fuel material recovery method of recovering a nuclear fuel material comprising thorium metal by reprocessing an oxide of a nuclear fuel material comprising thorium oxide, uranium oxide, plutonium oxide, and minor actinoid oxide in a spent fuel, the method comprising, in the following order:
(I) chemically reducing the thorium oxide comprised in the spent fuel in a chemical reducing agent that is a mixture of molten calcium chloride and molten metallic calcium, to produce a reaction product comprising thorium metal; and
(II) electrolytically separating the thorium metal in the reaction product obtained from the chemically reducing (I), in molten salt of lithium chloride, potassium chloride, or a mixed molten salt of lithium chloride and potassium chloride.

2. The method according to claim 1 , further comprising, before the chemically reducing (I):
chemically reducing the uranium oxide comprised in the spent fuel in a chemical reducing agent that comprises at least one selected from the group consisting molten metallic lithium and metallic potassium to produce uranium metal.

3. The nuclear fuel material recovery method according to claim 1 , wherein the chemical reduction of the thorium oxide (I) is carried out at about 850° C. to about 900° C.

4. The nuclear fuel material recovery method according to claim 2 , wherein the chemical reduction of the uranium oxide is carried out at about 650° C.

Assignees

• Toshiba Kk

Inventors

• Takahashi Yuya
• Mizuguchi Koji
• Fujita Reiko
• Nakamura Hitoshi
• Kanamura Shohei
• Kishimoto Naoki
• Matsubayashi Yoshikazu
• Oomori Takashi

Classifications

• C22B60/0291

  obtaining thorium · CPC title

• C25C7/005 Primary

  of cells for the electrolysis of melts (C25C7/02 - C25C7/06 take precedence) · CPC title

• G21C19/46

  Aqueous processes {, e.g. by using organic extraction means, including the regeneration of these means} · CPC title

• C25C3/34

  of metals not provided for in groups C25C3/02 - C25C3/32 · CPC title

• Y02W30/883

  Cross-Sectional Technologies · mapped topic