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Method for preparing powder comprising particles of triuranium octoxide and particles of plutonium dioxide

A technology for uranium 8 oxide and plutonium dioxide, which is used in the field of recycling spent nuclear fuel and can solve problems such as dependence

Pending Publication Date: 2019-06-18
COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

AI Technical Summary

Problems solved by technology

However, this relies on the potentially tricky step of reducing plutonium(IV) to plutonium(III) and stabilizing plutonium(III)

Method used

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  • Method for preparing powder comprising particles of triuranium octoxide and particles of plutonium dioxide
  • Method for preparing powder comprising particles of triuranium octoxide and particles of plutonium dioxide
  • Method for preparing powder comprising particles of triuranium octoxide and particles of plutonium dioxide

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Embodiment Construction

[0093] This example concerns an aqueous solution A of uranium(IV) nitrate 1 and an aqueous solution of plutonium(IV) nitrate and uranium(VI) nitrate A' 1 Prepared by U 3 o 8 Particles and PuO 2 A powder consisting of a mixture of particles.

[0094] Aqueous solution A 1 Including 0.15mol / L uranium(IV) nitrate or formula U(NO 3 ) 4 Tetravalent uranium nitrate, 2.5mol / L nitric acid and 0.06mol / L hydrazine ion N 2 h 5 + (as hydrazine nitrate N 2 h 5 NO 3 Added in the form of), while the aqueous solution A' 1 Including 0.15mol / L of the formula Pu(NO 3 ) 4 plutonium (IV) nitrate, 0.038mol / L uranium (VI) nitrate or formula UO 2 (NO 3 ) 2 Uranyl nitrate and 2.5mol / L nitric acid.

[0095] Aqueous solution A 1 Concentration of uranium(IV) nitrate in medium and aqueous solution A' 1 The concentration of plutonium(IV) nitrate in the medium is chosen such that, taking into account the volumes of aqueous solutions involved, the starting Pu(IV) / U(IV)+Pu(IV) molar ratio i...

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Abstract

The invention relates to a method for preparing a powder comprising an intimate mixture of U3O8 particles and PuO2 particles and which may further comprise particles of ThO2 or NpO2. The method comprises: a) preparing, by oxalic precipitations, an aqueous suspension Si of particles of uranium(IV) oxalate and an aqueous suspension S2 of particles of plutonium(IV) oxalate; b) mixing the aqueous suspension Si with the aqueous suspension S2 to obtain an aqueous suspension S1+2 comprising particles of uranium(IV) oxalate and particles of plutonium(IV) oxalate; c) separating the aqueous suspension S1+2 into an aqueous phase and a solid phase comprising the particles of uranium(IV) oxalate and the particles of plutonium(IV) oxalate; and d) calcining the solid phase to convert (1) the particles ofuranium(IV) oxalate to particles of triuranium octoxide and (2) the particles of plutonium(IV) oxalate to particles of plutonium(IV) dioxide, whereby the powder is obtained; and is characterized in that steps b) and c) are performed simultaneously or successively. The invention further relates to the fabrication of nuclear fuels of MOX type, e.g. for LWR or FNR reactors.

Description

technical field [0001] The invention relates to the field of recycling spent nuclear fuel. [0002] More specifically, the present invention relates to a method capable of utilizing aqueous streams produced by hydrometallurgical processing of spent nuclear fuel to produce U3O8-containing U 3 o 8 Granules and plutonium dioxide PuO 2 A method of a powder of an intimate mixture of particles, and said powder may additionally comprise tetravalent actinide dioxide particles selected from thorium and neptunium. [0003] The powder obtained can be used in particular for the production of fresh nuclear fuel of the MOX type (Mixed OXide Fuel) which can be irradiated, for example, in light water reactors (LWR) or fast neutron reactors (FNR). Background technique [0004] In the present case, the processing / recycling of spent nuclear fuel for the reuse of plutonium contained in spent nuclear fuel and for the production of fuel of the MOX type includes in particular the following step...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): C01F17/00G21F9/30G21C19/48
CPCG21C3/623G21C19/46C01G43/01C01G56/005C01G56/007C01P2002/72C01P2004/03C01P2004/51C01P2006/12Y02E30/30G21C3/62
Inventor 弗朗索瓦·庞斯莱特尼古拉斯·维吉尔本艾蒂科特·阿布拉-查派勒特奥雷利·高特赫埃莱奥诺·外勒科玛玛丽-贺勒尼·努伊勒
Owner COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
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