CN109943763B - Preparation method of high-thermal-conductivity nuclear fuel pellet - Google Patents
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Abstract
The invention discloses a preparation method of a high-thermal-conductivity nuclear fuel pellet, which comprises the following steps: mixing W/Mo/diamond/SiC powder with UO2Carrying out ultrasonic oscillation treatment and ball milling on the powder to obtain doped alloy powder, and carrying out spray granulation or plasma granulation to obtain alloy spheroidized powder with micron-sized particle size; performing W/Mo coating sputtering on the alloy spheroidized powder, and controlling the temperature, time and power of the W/Mo sputtering to prepare an alloy ball wrapped by a W/Mo layer with micron-sized coating thickness; pressing the alloy ball wrapped by the W/Mo layer to obtain an alloy pressed blank; and sintering to obtain the alloy heat-conducting nuclear fuel pellet. The heat conduction efficiency of the high-heat-conduction nuclear fuel pellet prepared by the method can be improved by 15-25%, and the performance of the high-heat-conduction nuclear fuel pellet is superior to that of the conventional nuclear fuel-doped heat conduction pellet. The method is suitable for batch production and can be used for large-scale production.
Description
Technical Field
The invention relates to a preparation method of a nuclear fuel pellet of a hydraulic reactor, in particular to a preparation method of a nuclear fuel pellet with high thermal conductivity.
Background
The nuclear fuel pellet core component of the piezoreactor is uranium dioxide, and the uranium dioxide emits a large amount of heat in the fission process and is conducted to external fluid through a cladding tube, so that the heat transmission and utilization are realized. However, the uranium dioxide has poor heat conducting property and is not beneficial to heat conduction, so that a high temperature gradient is generated from the edge to the center of the cross section of the fuel pellet, and even the nuclear fuel pellet is subjected to structural failure. For this reason, it is practically necessary to improve the heat transfer efficiency of the fuel block while controlling the fission speed of uranium dioxide. One of the major ways to improve the thermal conductivity of fuel pellets today is by adding highly thermally conductive substances such as the metals tungsten, molybdenum, SiC and diamond. The preparation process is mainly completed by the working procedures of powder mixing, pressing, sintering and the like. In the alloy prepared by the method, most doping elements are dispersed or dissolved in the uranium dioxide matrix, and a small amount of doping elements are distributed in the grain boundary. The doping elements inside the grains contribute to intra-grain heat conduction, and the doping elements at the grain boundaries contribute to inter-grain heat transfer. However, the point-type distribution of the high thermal conductivity doping elements at the grain boundaries affects a significant improvement in the thermal conductivity of the fuel pellets because no effective communication is achieved. In addition, in the existing preparation method of the uranium dioxide alloy fuel pellet, the particle size of the powder is selected and controlled by a screening mode basically. Therefore, the powder particle size distribution is wider, and the micro environments such as sintering temperature, pressure, activity and the like are not completely different, so that the controllability of the grain size of the pellet is poorer, and further, the difference of the grain size of the fuel pellet is larger. Meanwhile, high-thermal-conductivity elements such as W/Mo/SiC/diamond and the like at the grain boundary are distributed on the grain boundary randomly and cannot be effectively communicated. Therefore, the thermal conductivity of the existing uranium dioxide pellets is not ideal.
Disclosure of Invention
In order to solve the defects in the prior art, the invention aims to provide a preparation method of a high-thermal-conductivity nuclear fuel pellet, which focuses on the design of components and microstructures of the fuel pellet on the basis of continuously optimizing the density and fission heat release strength of a uranium dioxide alloy fuel pellet. On the one hand, the heat transfer capacity of the alloy pellet crystal grain energy is improved through a high-heat-conduction element doping mode, on the other hand, the communication of a high-heat-conduction channel at a crystal boundary is realized through a powder inclusion mode, the thermal resistance of the crystal boundary is reduced, the heat transfer efficiency is improved, and further the integral promotion of the heat conduction performance of the fuel pellet is ensured.
The invention is realized by the following technical scheme.
The invention provides a preparation method of a high-thermal-conductivity nuclear fuel pellet, which comprises the following steps:
1) alloy powder doping
The weight ratio of (1-2): (18-25) mixing UO with one of W/Mo/diamond/SiC2Putting the powder into a dispersion medium for ultrasonic oscillation treatment, and then performing ball milling and drying on the treated mixed slurry to prepare doped alloy powder;
2) granulating
According to the solid-liquid ratio (65-70): (30-35) mixing and stirring the alloy powder and a polyvinyl alcohol aqueous solution, and granulating the alloy powder mixed solution by controlling the rotating speed and the air inlet and outlet temperature of a centrifugal spray granulator, or carrying out plasma granulation on the alloy powder to prepare alloy spheroidized powder with micron-sized particle diameter;
3) vacuum magnetron sputtering
Performing magnetron sputtering on the W/Mo coating on the alloy spheroidizing powder, and preparing a W/Mo layer-coated alloy ball with the micron-sized coating thickness by controlling the vacuum degree, temperature, time and power of the magnetron sputtering of the W/Mo coating;
4) profiling die
Pressing the alloy ball wrapped by the W/Mo layer to obtain an alloy pressed blank;
5) sintering to obtain high-heat-conductivity nuclear fuel pellet
And sintering the prepared alloy pressed compact in a resistance furnace under a protective atmosphere, and preparing the alloy heat-conducting nuclear fuel pellet by controlling the sintering temperature and time.
With respect to the above technical solutions, the present invention has a further preferable solution:
optionally, in step 1), the UO and one of W/Mo/diamond/SiC2Putting the powder into a dispersion medium, carrying out ultrasonic oscillation treatment in a mixer for 3-5 h, and then adding ZrO into the treated mixed slurry according to the ball-to-material ratio of 3-5: 12And (5) ball-milling the grinding balls for 4-10 h at the rotating speed of 300-500 r/min.
Optionally, the dispersion medium is xylene or ethanol.
Optionally, in the step 2), the concentration of the polyvinyl alcohol aqueous solution is 2-5%, and the polyvinyl alcohol aqueous solution is heated and dissolved in a water bath at a temperature of below 80 ℃.
Optionally, in the step 2), the rotating speed of the spray granulation centrifugal nozzle is 1200-1600 r/min, the air inlet temperature is 200-260 ℃, the air outlet temperature is 130-150 ℃, and the particle size D is prepared50Is alloy spheroidized powder of 64-80 μm.
Optionally, the alloy powder is granulated by adopting the plasma granulation mode, the temperature of the plasma beam is adjusted to be 12000-16000 ℃, and the feeding speed of the powder feeder is 20-100 g/min.
Optionally, in the step 3), the vacuum degree of magnetron sputtering is 100-300 pa, the temperature is 120-300 ℃, the sputtering time is 3-4 h, the power is 4-8 kw, and the W/Mo coating with the thickness of 5-35 microns is prepared.
Optionally, in the step 4), the compression pressure is 200-450 MPa, and the pressing time is not more than 40 min.
Optionally, in the step 5), the alloy green compact is in a protective atmosphere of 95% Ar + 5% H in a resistance furnace2And (3) performing medium sintering, wherein the sintering temperature is 1700-1800 ℃, and the sintering time is 2-4 h.
The preparation method of the high-efficiency heat-conducting nuclear fuel pellet has the following beneficial effects:
1) preparing UO by spraying or plasma method according to main components and grain size of nuclear fuel pellet2+ W/Mo/SiC/diamond and other granulated powders to achieve UO2The spheroidization and the granularity of alloy powder such as + W/Mo/SiC/diamond and the like can be effectively controlled;
2) sputtering tungsten/molybdenum high-heat-conductivity metal coating on the surface of the granulated powder by a low-temperature vacuum magnetron sputtering technology to form W/Mo-in-UO coating2The microcosmic inclusion structure of + Wo/Mo/SiC/diamond alloy spheroidized particle surface';
3) the uniformity control of the three-dimensional quality of the powder pressed compact is realized through the granulated powder which is regularly granulated and has good fluidity and scale control, and the microscopic quality uniformity of the pressed compact is ensured;
4) during sintering, the tungsten-molybdenum coating of the adjacent powder is mutually diffused and densified along with the shrinkage of the particle size of the powder and the elimination of the gaps between the adjacent powder, so that a continuously densified tungsten/molybdenum heat conduction channel is formed.
The invention does not change the UO2Based on the main components of the alloy such as + W/Mo/SiC/diamond and the like, according to the difference of the functions and performance characteristics of uranium dioxide and doped elements in the processes of heat generation and heat transfer, namely the heat generation function of the uranium dioxide and the heat conduction function of the alloy elements such as W/Mo/SiC/diamond and the like. The heat release performance of the grains is balanced by controlling the size uniformity of the microscopic grains; meanwhile, through the structural design of microscopic grain boundaries, a heat conduction layer W/Mo is formed to wrap the heat generation body UO2The microscopic grain structures of the alloys such as + W/Mo/SiC/diamond and the like are mutually connected according to the microscopic grain structures to form a space three-dimensional network heat conduction and support structure, so that the unification of the function optimization of heat-generating materials and the structure reinforcement of heat conduction materials is realized. Namely, on the one hand, the UO in the crystal grains can be reduced moderately2The contents of W/Mo/SiC/diamond and the like in the alloy improve the cracking hot strength; on the other hand, the tungsten and the molybdenum are effectively communicated through the grain boundary, so that the heat-conducting property of the fuel pellet is obviously improved. The heat conduction efficiency of the high-heat-conduction nuclear fuel pellet prepared by the method can be improved by 15-25%, and the high-heat-conduction nuclear fuel pellet is superior to the performance of the uranium dioxide heat conduction pellet prepared by other methods at present. The method is suitable for batch production and can be used for large-scale production.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention:
FIG. 1 is a block diagram of the process of the present invention.
Detailed Description
The present invention will now be described in detail with reference to the drawings and specific embodiments, wherein the exemplary embodiments and descriptions of the present invention are provided to explain the present invention without limiting the invention thereto.
As shown in fig. 1, the preparation method of the high thermal conductivity nuclear fuel pellet of the present invention comprises the following steps:
(1) alloy powder doping
The weight ratio of (1-2): (18-25) standing W-One of Mo/diamond/SiC and UO2Putting the powder into a dispersion medium xylene or ethanol for ultrasonic oscillation treatment for 3-5 h, and then adding ZrO into the treated mixed slurry according to the ball-to-material ratio of 3-5: 12Grinding balls, and mixing the materials for 4-10 hours in vacuum at the rotating speed of 300-500 r/min; and drying the treated mixed slurry to obtain doped alloy powder.
(2) Centrifugal spray granulation spheroidization
Spray granulation mode: granulating the alloy powder through a spray granulator according to a solid-to-liquid ratio (65-70): (30-35) adding the alloy powder into a polyvinyl alcohol aqueous solution with the concentration of 2-5%, stirring while adding, and controlling the temperature of the polyvinyl alcohol aqueous solution to be less than or equal to 80 ℃ through a water bath; forming slurry with the solid-liquid ratio of 65-70%. The air inlet temperature of the centrifugal spray granulator is controlled to be 200-260 ℃, the air outlet temperature is controlled to be 130-150 ℃, and the rotating speed of a centrifugal nozzle is 12000-16000 r/min.
In another embodiment of the invention, a plasma beam granulation mode is adopted, the temperature of the plasma beam is adjusted to be 12000-16000 ℃, and the feeding speed of the powder feeder is 20-100 g/min.
The particle size of the granulated powder is generally about 50 to 80 μm.
(3) Vacuum magnetron sputtering process
And putting the spheroidized alloy powder into a vacuum sputtering furnace chamber to carry out W/Mo coating magnetron sputtering, wherein the vacuum degree of the W/Mo coating magnetron sputtering is controlled to be 100-300 pa, the temperature is controlled to be 120-300 ℃, the time is 3-4 h, the power is 4-8 kw, and the thickness of the sputtering coating is 5-35 mu m.
(4) Pressing and sintering
The powder was compression molded on a tablet press/four-column press/cold isostatic press. The pressing pressure is 200-450 MPa, and the pressing time is less than or equal to 40 min. Then put in 95% Ar + 5% H2And sintering in a sintering furnace at 1700-1800 ℃ for 2-4 h to obtain the alloy heat-conducting nuclear fuel pellet.
Specific examples are given below to further illustrate the present invention.
Example 1
Mixing nano gold in a ratio of 1:19Diamond powder and UO2Putting the powder into a dispersion medium (dimethylbenzene) for ultrasonic vibration treatment for 3 h. Then the treated mixed slurry is transferred into an agate tank, and ZrO is added2Grinding balls according to a ball-material ratio of 5:1, then performing ball milling and mixing by using a planetary ball mill at a rotating speed of 300r/min for 4h, and drying to obtain the diamond-doped uranium dioxide alloy powder. Secondly, according to the solid-to-liquid ratio of 70%, placing the prepared alloy powder into a 2% PVA solution with the water bath temperature of 70 ℃ and stirring for 40 min; then, the mixture was granulated by a centrifugal spray granulator. The rotating speed of the centrifugal nozzle is 12000r/min, the air inlet temperature is 220 ℃, the air outlet temperature is 135 ℃, and the particle diameter D is prepared50Is a 65 μm alloy spheroidized powder. Then carrying out magnetron sputtering on the molybdenum coating, wherein the vacuum degree is 120pa, the temperature is 160 ℃, the sputtering time is 1.5h, and the power is 4kw, and preparing the molybdenum coating with the coating thickness of 15.6 mu m. And (3) pressing the molybdenum-coated uranium dioxide alloy powder on a tablet press, wherein the pressure is 450MPa, and the pressing time is 0.5min, so as to obtain an alloy pressed blank. And finally, sintering in a resistance furnace in the protection of argon and hydrogen mixed atmosphere at 1750 ℃ for 3h to prepare the alloy pellet. And (4) measuring the thermal conductivity of the alloy.
Finally, a high-thermal-conductivity nuclear fuel alloy sample is obtained, and the measured thermal conductivity of the sample is 6.63W/(m.K). While the same molding conditions are used to prepare undoped UO2The room temperature thermal conductivity of the pellet pattern was 5.62W/(m.K), which is a 17.9% improvement on a comparable basis.
Example 2
Mixing nano diamond powder and UO at a ratio of 1:202Putting the powder into a dispersion medium (dimethylbenzene) and carrying out ultrasonic oscillation treatment for 4 hours. Then ZrO is added according to the ball-to-feed ratio of 5:12And grinding the balls, and putting the balls into a planetary ball mill together for ball milling and mixing. The rotating speed of the ball mill is 350r/min, the ball milling time is 5h, and then the ball mill is dried to prepare the UO doped with diamond2And (3) alloy powder. Secondly, according to the solid-to-liquid ratio of 65%, the prepared alloy powder is put into 2.5% PVA water solution with the water bath temperature of 60 ℃ and stirred for 30 min; then, the mixture was granulated by a centrifugal spray granulator. The rotating speed of the centrifugal nozzle is 12500r/min, the air inlet temperature is 200 ℃, the air outlet temperature is 150 ℃, and the particle size D is prepared50Is a 72 μm alloy spheroidized powder. Then through magnetron sputteringThe temperature of the molybdenum coating is 120 ℃, the vacuum degree is 180pa, the sputtering time is 4h, the power is 5kw, and the thickness of the prepared molybdenum coating is 27.3 mu m. Then pressing the blank by a four-column press with the pressure of 400MPa and the pressing time of 2min to obtain an alloy pressed blank. Finally in a resistance furnace with 95% Ar + 5% H2And (4) medium sintering, wherein the process is 1700 ℃ multiplied by 4h, and the alloy core block is prepared. And (4) measuring the thermal conductivity of the alloy.
Finally, a high-thermal-conductivity nuclear fuel alloy sample is obtained, and the measured thermal conductivity of the sample is 6.95W/(m.K). While the same molding conditions are used to prepare undoped UO2The room temperature thermal conductivity of the pellet pattern was 5.62W/(m.K), which is a 23.6% improvement on a comparable basis.
Example 3
Mixing 2:23 ratio of submicron molybdenum powder and UO2Putting the powder into a dispersion medium (alcohol) for ultrasonic oscillation treatment for 4 hours, and then adding ZrO according to a ball-to-material ratio of 3:12Grinding balls are put into a planetary ball mill together for ball milling and mixing, the rotating speed is 500r/min, the ball milling time is 3.5h, and then the mixture is dried to prepare the UO doped with molybdenum powder2And (3) alloy powder. Secondly, according to the solid-to-liquid ratio of 68%, the prepared alloy powder is put into a 3.2% PVA aqueous solution with the water bath temperature of 50 ℃ and stirred for 40 min; then, the mixture was granulated by a centrifugal spray granulator. The rotating speed of a centrifugal spray nozzle for spray granulation is 13000r/min, the air inlet temperature is 260 ℃, the air outlet temperature is 130 ℃, and the particle size D is prepared50Is a 64 μm alloy spheroidized powder. Then, the molybdenum coating is prepared by magnetron sputtering, the vacuum degree is 130pa, the temperature is 300 ℃, the sputtering time is 1h, and the power is 8kw, and the thickness of the prepared molybdenum coating is 23.2 μm. Then pressing by an isostatic press with the pressure of 200MPa and the pressing time of 40min to obtain an alloy pressed blank. Finally in a resistance furnace with 95% Ar + 5% H2And (4) medium sintering, wherein the process is 1750 ℃ multiplied by 3h, and the alloy core block is prepared. And (4) measuring the thermal conductivity of the alloy.
Finally, a high-thermal-conductivity nuclear fuel alloy sample is obtained, and the measured thermal conductivity of the sample is 6.74W/(m.K). While the same molding conditions are used to prepare undoped UO2The room temperature thermal conductivity of the pellet pattern was 5.62W/(m.K), which is a 19.93% improvement on a comparable basis.
Example 4
Mixing 2:25 of submicron tungsten powderAnd UO2Putting the powder into a dispersion medium (dimethylbenzene) for ultrasonic oscillation treatment for 3 hours, and then adding ZrO according to a ball-to-material ratio of 4:12And grinding the balls, and putting the balls into a planetary ball mill together for ball milling and mixing. The rotating speed of the ball mill is 300r/min, the ball milling time is 6h, and then the UO is prepared by drying2And (3) alloy powder. Then, by means of plasma beam granulation, the temperature of the plasma beam is 12000 ℃, the feeding speed of a powder feeder is 60g/min, and the particle diameter D is prepared50Is 46 μm alloy spheroidized powder. Then, the tungsten coating is prepared by magnetron sputtering, the vacuum degree is 150pa, the temperature is 200 ℃, the sputtering time is 2h, and the power is 5kw, and the thickness of the tungsten coating is 15 μm. Then pressing the alloy blank by a four-column press with the pressure of 350MPa and the pressing time of 1.0min to obtain an alloy pressed blank. Finally in a resistance furnace with 95% Ar + 5% H2Sintering in atmosphere at 1750 ℃ for 4h to obtain the alloy core block. And (4) measuring the thermal conductivity of the alloy.
Finally, a high-thermal-conductivity nuclear fuel alloy sample is obtained, and the measured thermal conductivity of the sample is 6.57W/(m.K). While the same molding conditions are used to prepare undoped UO2The room temperature thermal conductivity of the pellet pattern was 5.62W/(m.K), which is a 16.9% improvement on a comparable basis.
Example 5
Mixing 1:20 submicron SiC powder and UO2Putting the powder into a dispersion medium (alcohol) for ultrasonic oscillation treatment for 5 hours, and then adding ZrO according to a ball-to-material ratio of 5:12And grinding the balls, and putting the balls into a planetary ball mill together for ball milling and mixing. The rotating speed of the ball mill is 500r/min, the ball milling time is 6h, and then the SiC powder-doped UO is prepared by drying2And (3) alloy powder. Then, by means of plasma beam granulation, the temperature of the plasma beam is 13000 ℃, the feeding speed of a powder feeder is 80g/min, and the particle size D is prepared50Is 42 μm alloy spheroidized powder. Then, the molybdenum coating is prepared by magnetron sputtering, the vacuum degree is 160pa, the temperature is 150 ℃, the sputtering time is 3h, and the power is 5kw, and the thickness of the prepared molybdenum coating is 25 μm. Then, an alloy pressed blank is prepared by isostatic pressing, the pressure is 200MPa, and the pressing time is 35 min. Finally in a resistance furnace with 95% Ar + 5% H2Sintering in atmosphere at 1700 ℃ for 3h to obtain the alloy pellet. And (4) measuring the thermal conductivity of the alloy.
Finally obtain the heightA sample of a heat-conductive nuclear fuel alloy having a thermal conductivity of 6.79W/(m.K) was measured. While the same molding conditions are used to prepare undoped UO2The room temperature thermal conductivity of the pellet pattern was 5.61W/(m.K), which is a 20.8% improvement on a comparable basis.
The following table 1 shows the comparison of the thermal conductivity of the chromium zirconium copper alloy high thermal conductivity nuclear fuel pellet example prepared by the method of the present invention with the thermal conductivity of the existing nuclear fuel pellet.
TABLE 1 comparison of Properties
From the above-mentioned UO2As can be seen from the comparison of the thermal conductivity of the fuel pellet, the UO prepared by the method of the invention2The conductivity of the fuel pellet is not lower than 6.57W/(m.K), the conductivity of the pellet is as high as 6.94W/(m.K), and the increase is more than 23%. Has great effect on improving the thermal efficiency of the fuel pellet and enhancing the stability of the nuclear fuel pellet, thereby having wide application prospect.
Claims (9)
1. A preparation method of a nuclear fuel pellet with high heat conductivity is characterized by comprising the following steps:
1) alloy powder doping
The weight ratio of (1-2): (18-25) mixing UO with one of W/Mo/diamond/SiC2Putting the powder into a dispersion medium for ultrasonic oscillation treatment, and then performing ball milling and drying on the treated mixed slurry to prepare doped alloy powder;
2) granulating
According to the solid-liquid ratio (65-70): (30-35) mixing and stirring the alloy powder and a polyvinyl alcohol aqueous solution, and granulating the alloy powder mixed solution by controlling the rotating speed and the air inlet and outlet temperature of a centrifugal spray granulator or carrying out plasma granulation to prepare alloy spheroidized powder with micron-sized particle size;
3) vacuum magnetron sputtering
Carrying out magnetron sputtering on the W or Mo coating on the alloy spheroidized powder, and preparing the W or Mo layer-coated alloy spheroidized powder with micron-sized coating thickness by controlling the magnetron sputtering vacuum degree, temperature, time and power of the W or Mo coating;
4) profiling die
Pressing the W or Mo layer coated alloy spheroidized powder to prepare an alloy pressed blank;
5) sintering to obtain high-heat-conductivity nuclear fuel pellet
And sintering the prepared alloy pressed compact in a resistance furnace under a protective atmosphere, and preparing the alloy heat-conducting nuclear fuel pellet by controlling the sintering temperature and time.
2. A method for preparing a nuclear fuel pellet with high thermal conductivity according to claim 1, characterized in that in step 1), the UO is mixed with one of W/Mo/diamond/SiC2Putting the powder into a dispersion medium, carrying out ultrasonic oscillation treatment in a mixer for 3-5 h, and then adding ZrO into the treated mixed slurry according to the ball-to-material ratio of 3-5: 12And (5) ball-milling the grinding balls for 4-10 h at the rotating speed of 300-500 r/min.
3. A method for the preparation of nuclear fuel pellets with high thermal conductivity according to claim 2, characterized in that the dispersion medium is xylene or ethanol.
4. A method for preparing a nuclear fuel pellet with high thermal conductivity according to claim 1, wherein in the step 2), the concentration of the polyvinyl alcohol aqueous solution is 2-5%, and the polyvinyl alcohol aqueous solution is heated and dissolved in a water bath with the temperature below 80 ℃.
5. The method for preparing a nuclear fuel pellet with high thermal conductivity according to claim 1, wherein in the step 2), the rotation speed of the spray granulation centrifugal nozzle is 1200-1600 r/min, the air inlet temperature is 200-260 ℃, the air outlet temperature is 130-150 ℃, and the prepared particle size D is50Is 50-100 μm alloy spheroidized powder.
6. The preparation method of the nuclear fuel pellet with high thermal conductivity according to claim 1, wherein the spheroidization of the alloy powder is realized by adopting the plasma granulation mode, the temperature of a plasma beam is 12000-16000 ℃, and the feeding speed of a powder feeder is 20-100 g/min.
7. The preparation method of a nuclear fuel pellet with high thermal conductivity according to claim 1, wherein in the step 3), the degree of vacuum of magnetron sputtering is 100-300 Pa, the temperature is 120-300 ℃, the sputtering time is 3-4 h, the power is 4-8 kW, and a W or Mo coating with the thickness of 5-35 microns is prepared.
8. The method for preparing a high thermal conductivity nuclear fuel pellet as claimed in claim 1, wherein in the step 4), the compression pressure is 200 to 450MPa, and the compression time is less than or equal to 40 min.
9. A method for preparing a nuclear fuel pellet with high thermal conductivity as claimed in claim 1, wherein in the step 5), the alloy compact is protected in a resistance furnace in a protective atmosphere of 95% Ar + 5% H2Sintering in a mixed atmosphere at the temperature of 1700-1800 ℃ for 2-4 h.
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| CN111014698A (en) * | 2019-12-17 | 2020-04-17 | 中核四0四有限公司 | Granulating method of MOX mixed powder |
| CN113003609A (en) * | 2019-12-20 | 2021-06-22 | 中核北方核燃料元件有限公司 | Plasma spheroidizing process of uranium dioxide particles |
| CN112355311B (en) * | 2020-10-21 | 2022-08-02 | 中国科学院合肥物质科学研究院 | Tungsten-based metal ceramic nuclear fuel pellet and preparation method thereof |
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