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Method of producing pellets of a nuclear fuel based on mixed oxide (U,Pu)O2 or (U,Th)O2

A mixed oxide, nuclear fuel technology, applied in the direction of reactor fuel elements, reactor fuel materials, nuclear engineering solutions, etc., can solve the problems of no reported effect, loss of integrity, etc.

Inactive Publication Date: 2007-01-03
COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES +1
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  • Summary
  • Abstract
  • Description
  • Claims
  • Application Information

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Problems solved by technology

[0007] 2. Withstands changes in reactor power without losing its integrity
[0036] On the other hand, the literature does not report that the wax has an effect on (U / Pu)O 2 plutonium-containing clusters in UO 2 Any effect on the distribution in the matrix

Method used

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  • Method of producing pellets of a nuclear fuel based on mixed oxide (U,Pu)O2 or (U,Th)O2
  • Method of producing pellets of a nuclear fuel based on mixed oxide (U,Pu)O2 or (U,Th)O2
  • Method of producing pellets of a nuclear fuel based on mixed oxide (U,Pu)O2 or (U,Th)O2

Examples

Experimental program
Comparison scheme
Effect test

Embodiment 1

[0095] By mixing 543.7 g of UO in a ball mill jar 2 powder (U / O ~ 2.18) and 204.6g of PuO 2 The powders were co-milled for 4 hours to prepare 748.3 g of an initial powder mixture (or mixture MP1 ) having a plutonium weight content of 25%.

[0096] After milling, 8 g of this MP1 mixture was mixed with 0.04 g of Cr 2 o 3 (corresponding to a weight ratio of 5000 ppm) in a turbo mixer (revolving speed of container: 10 rpm; rotating speed of steam turbine: 3000 rpm) for 3 cycles of 10 minutes each.

[0097] The resulting mixture was sieved through a sieve with a pore size of 80 μm in order to retain only powder aggregates with a size smaller than or equal to 80 μm.

[0098] Then 8.04 g of this undersize and 12 g of the same UO as used to prepare the MP1 mixture 2 powder, mixed with 0.06 g of zinc stearate (ZnSt) to obtain a final powder mixture with a plutonium content of 11% by weight.

[0099] The final mixture was prepared in a Turbula mixer for 30 minutes at a speed of 60 ...

Embodiment 2

[0113] A portion of the MP1 mixture prepared in Example 1 was taken and sieved on a sieve with a pore size of 250 μm to retain only powder aggregates with a size less than or equal to 250 μm.

[0114] Then 8 g of this undersize and 12 g of the same UO as used to prepare the MP1 mixture 2 powder, with 0.04g of Cr 2 o 3 (corresponding to a weight ratio of 2000 ppm) and 0.06 g of ZnSt to obtain a final powder mixture with a plutonium content of 11% by weight.

[0115] The final mixture was prepared under the same conditions as described in Example 1. Its composition by weight is as follows: 88.5% UO 2 , 11% PuO 2 , 0.2% Cr 2 o 3 and 0.3% ZnSt.

[0116] The pellets were then granulated as described in Example 1 and the pellets were sintered.

[0117] After sintering, the particles have the following characteristics:

[0118] ·The hydraulic density is equal to 96.7% of the theoretical density, where the theoretical density is 11.02;

[0119] ·from image 3 It can be seen...

Embodiment 3

[0125] Mix 8 g of the MP1 mixture prepared in Example 1 with 0.016 g of Cr 2 o 3 (corresponding to a weight ratio of 2000 ppm) in a turbo mixer (rotational speed of vessel: 10 rpm; rotational speed of steam turbine: 3000 rpm) for 3 cycles of 10 minutes each.

[0126] The resulting mixture was sieved through a sieve with a pore size of 80 μm to retain only powder aggregates with a size less than or equal to 80 μm.

[0127] Then 8.016 g of this undersize and 12 g of the same UO as used to prepare the MP1 mixture 2 powder, with 0.024g of Cr 2 o 3 and 0.06 g of ZnSt to obtain a final powder mixture with a plutonium content of 11% by weight.

[0128] The final mixture was prepared under the same conditions as described in Example 1. Its composition by weight is as follows: 88.5% UO 2 , 11% PuO 2 , 0.2% Cr 2 o 3 and 0.3% ZnSt.

[0129] The pellets were then granulated as described in Example 1 and the pellets were sintered.

[0130] After sintering, the particles have the...

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Abstract

The invention relates to a process for producing pellets of a nuclear fuel based on a (U,Pu)O2 or (U,Th)O2 mixed oxide which comprises a) preparing a primary mixture of powders by co-milling a UO2 powder P1 and a PuO2 or ThO2 powder P2, b) sieving this mixture, c) preparing a final mixture of powders by diluting the undersize with a UO2 powder P3, d) pelleting this final mixture, and e) sintering the pellets, and in which at least one compound is incorporated chosen from the group consisting of the oxides of Cr, Al, Ti, Mg, V and Nb, precursors thereof and inorganic compounds capable of providing the element sulphur during step e), is incorporated in at least one of the powders P1, P2 and P3 and / or in at least one of the primary or final mixture of powders.

Description

technical field [0001] The invention relates to a method for preparing nuclear fuel particles based on mixed oxides of uranium and plutonium or mixed oxides of uranium and thorium. [0002] In particular, the present invention relates to a method for making particles to be prepared based on (U,Pu)O 2 Process for nuclear fuel of mixed oxides or MOX fuel, said particles having a heterogeneous microstructure, i.e. formed of at least two different phases, one called the uranium-containing phase (which is substantially free of plutonium) and the other called as a plutonium-containing phase (which is enriched in plutonium), and is characterized by an increased volume of the plutonium-containing phase and a particle size of the phase Increase. [0003] These particles are of great value in the preparation of oil columns for various nuclear reactors, especially light water reactors. Background technique [0004] Fuel for the core of a nuclear reactor provide...

Claims

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Application Information

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Patent Type & Authority Applications(China)
IPC IPC(8): G21C3/62
CPCG21Y2004/10G21C3/623G21Y2004/20G21Y2004/40Y02E30/38G21Y2002/104Y02E30/30
Inventor 西尔维·杜波伊斯吉勒·塞西利娅
Owner COMMISSARIAT A LENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES
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