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Spent fuel reprocessing method

A spent fuel and fuel technology, applied in nuclear power generation, climate sustainability, greenhouse gas reduction, etc., can solve the problems of high nuclear non-proliferation, difficult nuclear non-proliferation, and inability to reprocess processes, etc., to achieve nuclear non-proliferation High diffusivity effect

Inactive Publication Date: 2009-12-02
KK TOSHIBA
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  • Abstract
  • Description
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Problems solved by technology

[0006] In the conventional Purex process, since U and Pu have been separated in the distribution process, it is difficult to say that it has absolute nuclear non-proliferation
[0007] Therefore, it is desired to modify a part of the Purex process, which has high nuclear non-proliferation, that is, a reprocessing process that cannot recover Pu alone

Method used

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no. 1 Embodiment approach

[0054] First, refer to figure 1 and figure 2 A first embodiment of the spent fuel reprocessing method of the present invention will be described.

[0055] figure 1 It is a flowchart showing the first embodiment of the spent fuel reprocessing method of the present invention. figure 1 In the dismantling and shearing step 2, the spent oxide fuel 1 is first dismantled and sheared. Then, in the dissolving step 3, the whole amount is dissolved with nitric acid. At this time, U exists in a hexavalent state and Pu exists in a tetravalent state.

[0056] Then, in the electrolytic valence adjustment step 4, Pu is electrolytically reduced to trivalent. figure 2It is a schematic longitudinal sectional view showing an example of an apparatus used in the electrolytic value adjustment step 4 in the first embodiment. That is, in this device, the cathode chamber 27 is separated from the anode chamber 28 by the diaphragm 50 . Catholyte 24 is contained in cathodic chamber 27 , into whic...

no. 2 Embodiment approach

[0073] Below, refer to Figure 5 and Figure 6 A second embodiment of the spent fuel reprocessing method of the present invention will be described. Here, the same symbols are used for the same or similar parts as those of the first embodiment, and overlapping descriptions are omitted.

[0074] Figure 5 It is a flowchart showing the second embodiment of the spent fuel reprocessing method of the present invention. in addition, Figure 6 It is a schematic longitudinal sectional view showing an example of an apparatus used in the electrolytic reduction step in the second embodiment.

[0075] The steps up to the oxalic acid precipitation 7 for recovering U, Pu, minor actinides, rare earth elements, etc. in the oxalic acid precipitation step 6 are the same as those in the first embodiment.

[0076] In this second embodiment, in order to obtain metal U, Pu, and minor actinides, an oxidation dehydration step 15 and an electrolytic reduction step 17 are provided instead of the c...

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Abstract

A spent fuel reprocessing method has a dissolution step of dissolving the spent fuel in nitric acid solution, an electrolysis / valence adjustment step of reducing Pu to trivalent, maintaining the pentavalent of Np, a uranium extraction step of collecting UO2 by bringing the fuel into contact with organic solvent and extracting hexavalent U by means of an extraction agent, an oxalic acid precipitation step of causing MA and the fissure products remaining in the nitric acid solution to precipitate together as oxalic acid precipitate, a chlorination step of converting the oxalic acid precipitate into chlorides by adding hydrochloric acid to the oxalic acid precipitate, a dehydration step of synthetically producing anhydrous chlorides by dehydrating the chlorides in a flow of Ar gas, and a molten salt electrolysis step of dissolving the anhydrous chlorides into molten salt and collecting U, Pu and MA at the cathode by electrolysis.

Description

technical field [0001] The invention relates to a spent fuel reprocessing method (spent fuel reprocessing method), which includes the process of recovering uranium (U), plutonium (Pu) and minor actinides (MA, minor actinide) from spent oxide nuclear fuel. Background technique [0002] As a representative process of reprocessing spent fuel generated in nuclear power plants, refining and recovering useful substances contained in spent fuel, separating unnecessary fission products, and reusing them as fuel, there is the Purex process (Purex process) . In addition to transuranium elements (TRU, transuranium elements) such as uranium and plutonium, spent fuel also contains alkali metal (AM) elements, alkaline earth metal (AEM) elements, and platinum group elements as fission products (FP, fissionproducts). [0003] Nippon Haraden Co., Ltd.'s reprocessing plant in Rokkasho, Japan adopts the Purex process. That is, the process that cannot recover Pu alone after the following proc...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21F9/06
CPCG21C19/46C25C1/22C25C3/34Y02E30/30Y02P10/20Y02W30/50G21F9/06
Inventor 水口浩司藤田玲子布施行基中村等宇都宫一博川边晃宽
Owner KK TOSHIBA
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