CN101172660A - Method for producing high temperature reactor fuel element UO* nuclear core - Google Patents
Method for producing high temperature reactor fuel element UO* nuclear core Download PDFInfo
- Publication number
- CN101172660A CN101172660A CNA2007101757945A CN200710175794A CN101172660A CN 101172660 A CN101172660 A CN 101172660A CN A2007101757945 A CNA2007101757945 A CN A2007101757945A CN 200710175794 A CN200710175794 A CN 200710175794A CN 101172660 A CN101172660 A CN 101172660A
- Authority
- CN
- China
- Prior art keywords
- high temperature
- furnace
- temperature
- sintering
- fuel element
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 27
- 238000004519 manufacturing process Methods 0.000 title abstract description 18
- 238000000034 method Methods 0.000 claims abstract description 37
- 238000010438 heat treatment Methods 0.000 claims abstract description 35
- 238000001816 cooling Methods 0.000 claims abstract description 25
- 238000002360 preparation method Methods 0.000 claims abstract description 15
- 229910001220 stainless steel Inorganic materials 0.000 claims abstract description 10
- 239000010935 stainless steel Substances 0.000 claims abstract description 10
- 239000002994 raw material Substances 0.000 claims abstract description 4
- 238000005245 sintering Methods 0.000 claims description 44
- 239000000498 cooling water Substances 0.000 claims description 14
- 238000009413 insulation Methods 0.000 claims description 11
- 229910052751 metal Inorganic materials 0.000 claims description 6
- 239000002184 metal Substances 0.000 claims description 6
- 229910052750 molybdenum Inorganic materials 0.000 claims description 6
- 238000006722 reduction reaction Methods 0.000 claims description 6
- 230000005587 bubbling Effects 0.000 claims description 5
- 229910052721 tungsten Inorganic materials 0.000 claims description 4
- 230000006698 induction Effects 0.000 claims description 3
- 238000001914 filtration Methods 0.000 claims description 2
- 238000002791 soaking Methods 0.000 claims description 2
- 239000004744 fabric Substances 0.000 abstract description 3
- 238000005406 washing Methods 0.000 abstract description 3
- 238000006243 chemical reaction Methods 0.000 abstract description 2
- 239000011806 microball Substances 0.000 abstract 4
- 230000007423 decrease Effects 0.000 abstract 1
- 230000003247 decreasing effect Effects 0.000 abstract 1
- 238000001035 drying Methods 0.000 description 12
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 7
- 238000005516 engineering process Methods 0.000 description 6
- 239000000463 material Substances 0.000 description 6
- 239000004005 microsphere Substances 0.000 description 6
- 230000006835 compression Effects 0.000 description 5
- 238000007906 compression Methods 0.000 description 5
- 239000002826 coolant Substances 0.000 description 5
- 238000009766 low-temperature sintering Methods 0.000 description 5
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 4
- 239000011733 molybdenum Substances 0.000 description 4
- 238000011031 large-scale manufacturing process Methods 0.000 description 3
- 238000011946 reduction process Methods 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 2
- 230000007797 corrosion Effects 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 238000002317 scanning near-field acoustic microscopy Methods 0.000 description 2
- WFKWXMTUELFFGS-UHFFFAOYSA-N tungsten Chemical compound [W] WFKWXMTUELFFGS-UHFFFAOYSA-N 0.000 description 2
- 239000010937 tungsten Substances 0.000 description 2
- 230000003245 working effect Effects 0.000 description 2
- 239000004372 Polyvinyl alcohol Substances 0.000 description 1
- 239000001089 [(2R)-oxolan-2-yl]methanol Substances 0.000 description 1
- WZECUPJJEIXUKY-UHFFFAOYSA-N [O-2].[O-2].[O-2].[U+6] Chemical compound [O-2].[O-2].[O-2].[U+6] WZECUPJJEIXUKY-UHFFFAOYSA-N 0.000 description 1
- 230000032683 aging Effects 0.000 description 1
- 238000013459 approach Methods 0.000 description 1
- 230000000903 blocking effect Effects 0.000 description 1
- 238000001354 calcination Methods 0.000 description 1
- 229910002091 carbon monoxide Inorganic materials 0.000 description 1
- 239000000919 ceramic Substances 0.000 description 1
- 229910052593 corundum Inorganic materials 0.000 description 1
- 239000010431 corundum Substances 0.000 description 1
- 238000000280 densification Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 229930195733 hydrocarbon Natural products 0.000 description 1
- 150000002430 hydrocarbons Chemical class 0.000 description 1
- 239000004615 ingredient Substances 0.000 description 1
- 229920000609 methyl cellulose Polymers 0.000 description 1
- 239000001923 methylcellulose Substances 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 230000001590 oxidative effect Effects 0.000 description 1
- 229920002451 polyvinyl alcohol Polymers 0.000 description 1
- 238000003980 solgel method Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- BSYVTEYKTMYBMK-UHFFFAOYSA-N tetrahydrofurfuryl alcohol Chemical compound OCC1CCCO1 BSYVTEYKTMYBMK-UHFFFAOYSA-N 0.000 description 1
- 229910000439 uranium oxide Inorganic materials 0.000 description 1
Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
The invention relates to a preparation method for high temperature reactor fuel element UO2 core, relating to the roasting, the reducing and the burning processes of raw material micro ball of UO2 core, and belonging to the technical filed of the reactor fuel element production method. The method is characterized in that the raw material micro ball is paved inside a stainless steel pallet and then is arranged inside a low temperature furnace; air is fed into the low temperature furnace for heating and roasting, and then is kept with temperature range from 450 DEG C to 550 DEG C for one hour; vacuum air is fed into an Ar washing furnace; a reducing reaction is implemented with heating speed of 5 to 10 DEG C per minute; the reduced micro ball is arranged into a pot and then is arranged into a high temperature burning furnace behind the washing furnace to burn the micro ball; and the temperature is decreased and air is closed, and the pot is taken out so as to obtain the high temperature reactor fuel element UO2 core. The low temperature furnace takes a clock cover shape or a case shape low temperature furnace. The invention combines the roasting and the reducing into one furnace to complete, decreases the one-off cooling and heating process, reduces the one-off fabric procedure, effectively shortens the production period, prolongs the service time of the furnace, lowers the production cost, and is suitable to production on scale.
Description
Technical field
The present invention relates to High Temperature Gas heap fuel element UO
2Roasting, reduction and sintering among the preparation technology of nuclear core belong to reactor nuclear fuel element manufacture method technical field.
Technical background
At UO based on sol-gel method
2Among the preparation technology of fuel kernel core,, adhere to specification to obtain size and sphericity no matter, after the gel ball drying, all will carry out roasting, reduction and sintering complete be outer gelling, interior gelling or gelatinizing process, evenly, fine and close UO
2Ceramic microsphere.Roasting, reduction and three technologies of sintering are at UO
2Be defined as dry process in the production of nuclear core.The main effect of dry process is: dried gel ball contains hydrocarbon-containiproducts such as polyvinyl alcohol, methylcellulose gum and tetrahydrofurfuryl alcohol, and the main effect of roasting is to make these oxidizing hydrocarbons by heating, generates CO
2, CO, H
2But evolving gass such as O steam.The chemical ingredients of microballoon is UO after the roasting
3, in order to obtain UO
2Microballoon need carry out low-temperature reduction to it, and the agglomerating purpose be make the microballoon densification, when improving intensity and irradiation to the delay blocking capability of fission product.
At high temperature gas cooled reactor fuel element UO
2In the production of nuclear core, dry process mainly contains following several different approaches: (H.Huschka et al, IAEA-161 in the German NUKEM flow process, 37-47, Vienna (1974)), roasting is finished in retort furnace, by gas blower bubbling air in stove, 450 ℃ of calcining temperatures; Reduction and sintering carry out being divided into pushing away in the boat stove (continuous oven) of 4 warm areas, and preceding two warm areas reduce, and top temperature is 700 ℃, and latter two warm area carries out sintering, 1600 ℃ of top temperatures.Italian patent No.727301; In the described SNAM flow process of No.778786, dry process pushes away in the boat stove at two respectively and carries out: roasting is carried out in a vertical shifting pool furnace, temperature distribution gradient in the air atmosphere, stove, and the highest usable temp is 700 ℃; The reduction sintering carries out in High Temperature Furnaces Heating Apparatus, and this High Temperature Furnaces Heating Apparatus is divided into two warm areas, reduces respectively and sintering, and atmosphere is 4%H
2+ 96%Ar.Dry process is finished in two steps in the description of Japanese Patent JP2006038764A and JP2006038793A: carry out roasting in retort furnace, 400~600 ℃ of temperature, air atmosphere; Reduction and sintering carry out in a high-frequency induction furnace, at first at H
2Following 400~700 ℃ of reduction are carried out sintering in temperature more than 1200 ℃ then, and atmosphere is H
2(Anneleen m ü ller, 3 in the technology of South Africa
RdInternational Meeting on HTR), roasting retort furnace in carry out, 400 ℃, air atmosphere; Reduction and sintering carry out in the bell-jar resistance furnace, at first 450~650 ℃ of reduction, then at 1600 ℃ of sintering, pure H
2Atmosphere.China is at 10 megawatt high temperature gas cooled reactor fuel element production periods, UO
2Roasting, reduction and sintering in the dry process of nuclear core production carry out in three stoves respectively.
Abundant in order to guarantee to examine the roasting of core microballoon, reduction fully, microballoon all needs as far as possible individual layer to arrange in pallet or crucible in roasting and reduction process.In above-described technology, reduction and sintering carry out in pushing away the boat stove continuously in NUKEM flow process and the SNAM flow process, are suitable for producing daily the large scale continuous prod at the 100KgU microballoon, require the production below 50KgU to be unfavorable for saving energy and reduce the cost to daily output; In Japan and the South Africa technology, reduction and sintering carry out in High Temperature Furnaces Heating Apparatus, and the microballoon individual layer is arranged during owing to reduction, and few in certain volumetrical furnace charge amount, production efficiency is low when therefore causing sintering.Secondly, reduction and sintering are placed in the stove and carry out, and the chemical reaction owing to uranium oxide in reduction process can produce a considerable number of water, and exothermic material, the lagging material of high temperature sintering furnace at high temperature all had very big etch, the life-span of stove shortens greatly, has increased production cost.The 3rd, after the stoving oven discharging, microballoon needs again the cloth charging, increases processing step.In China's 10 megawatt high temperature gas cooled reactor fuel element production technique, owing to use three stoves independently to finish roasting, reduction and sintering respectively, number of devices is many; UO
2Microballoon from roasting, revert to sintering and finish, need 168 hours, the cycle is long, the cost height is not suitable for large-scale production.Therefore the present invention proposes a kind of new dry process, roasting and reduction is placed in the stove carries out, and sintering carries out separately.Can reduce the process time like this, reduce operation steps, reduce production costs.
Summary of the invention
The objective of the invention is to be preparation UO
2Nuclear core microballoon provides a kind of new dry process, and major objective is to reduce roasting, reduction, the sintering period of microballoon, reduces production costs, and is suitable for producing daily the large-scale production at 4~50KgU; The 2nd, eliminate the corrosion failure of the steam of reduction generation, the work-ing life of improving stove to tungsten heating element, lagging material in the high temperature sintering furnace.
The present invention with drying after heat treated three processes of microballoon in two stoves, finish respectively, promptly in a low temperature oven, finish the roasting and the reduction of microballoon, and then get the sintering of finishing microballoon in the High Temperature Furnaces Heating Apparatus at an atmosphere protection.
A kind of preparation high temperature nuclear reactor fuel element UO
2The method of nuclear core, its process is:
1, will (composition be UO through the raw material microballoon after ageing, washing and the drying treatment
3And organism) be layed in the stainless steel pallet, laying depth is at 0.6~2mm; Pallet is placed low temperature oven;
2, utilize air compressor machine bubbling air in low temperature oven, air flow quantity 80ml~200ml/min, open water-cooling system, begin the roasting that heats up then, heat-up rate before 300 ℃ is 1~2 ℃ of a per minute, heat-up rate after 300 is 5~10 ℃ of per minutes, and 450~550 ℃ of insulations 1 hour, tail gas entered exhaust system after handling after filtration;
3, after roasting is finished, stop bubbling air, vacuumized 10~30 minutes, fed the Ar prepurging then 20~40 minutes, feed H
2Or H
2The 4%+Ar mixed gas, its flow is adjusted into 5~10ml/min.In this process, furnace maintains the final holding temperature (450~550 ℃) in the roasting process;
4, the heat-up rate according to 5~10 ℃ of per minutes reduces.The highest reduction temperature is 650~700 ℃, and is incubated 1~4 hour; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
When temperature is reduced to 50~70 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet; Take out microballoon after the reduction and pack in the crucible of sintering, crucible is placed high temperature sintering furnace;
5, the high temperature sintering stove evacuation is 10~30 minutes, feeds the Ar prepurging then 20~40 minutes, feeds H
2Or H
2The 4%+Ar mixed gas, the adjustment flow is 2~10ml/min, opens water-cooling system;
6, microballoon is carried out sintering, carry out sintering according to the heat-up rate of 5~10 ℃ of per minutes, the highest sintering temperature is 1400~1650 ℃, soaking time 1~4 hour; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
7, when temperature is reduced to 50~90 ℃, to close H2 gas and feed Ar gas, powered-down and cooling water system when reducing to room temperature take out crucible, promptly obtain high temperature nuclear reactor fuel element UO
2Nuclear core product.
Described low temperature oven is bell-jar or box-type furnace low temperature oven.
Described crucible is Al
2O
3Crucible or metal W or Mo crucible tongs.
Described high temperature sintering furnace is induction heater or resistance furnace.
The major equipment that relates in above-mentioned dry process is a low temperature oven and a High Temperature Furnaces Heating Apparatus, and utility appliance comprises distributor, stainless steel pallet, crucible.
Major advantage of the present invention comprises:
(1) roasting and reduction are merged in the stove finishes, reduced once cooling and temperature-rise period, reduces one time the cloth material process, effectively reduce the production cycle, reduced production cost, suitable large-scale production.
(2) water (450~700 ℃) when low temperature that generates of reduction process just can discharge out of the furnace, and does not use tungsten heating element and lagging material owing in the low temperature oven, so steam do not cause corrosion failure to material in the low temperature oven, does not reduce the work-ing life of stove.
(3) the sintering process microballoon can be laid by individual layer, enhances productivity thereby improve the sinter burden amount.
Specific implementation
Further specify the present invention below in conjunction with embodiment.
Embodiment 1:
Preparation high temperature nuclear reactor fuel element UO
2The method of nuclear core, this method may further comprise the steps:
1, the dry microspheres that contains 5KgU is layed on the circular stainless steel pallet laying depth 1mm through distributor.Pallet places bell-jar low-temperature sintering stove by charging system.
2, open water coolant and pneupress system, the adjusting air flow quantity is 100ml/min.Start heating power supply, temperature increasing schedule is: rise to 300 ℃ from room temperature with 1 ℃/minute temperature rise rate, 5 ℃/minute are warmed up to 450 ℃, are incubated 2 hours.
3, closes compression air vacuumized 10 minutes, fed Ar prepurging 40 minutes, fed Ar+4%H
2, gas flow is 5ml/min.Heat-up rate between 450~600 ℃ is 6 ℃/minute, and 600 ℃ are incubated 1.5 hours; Close heating power supply, the low temperature oven water-cooled cooling; When temperature is reduced to 70 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet.
4, the reduction microballoon that the contains 15KgU corundum (Al that packs into
2O
3) in the crucible, place high temperature resistance furnace by charging system;
5, the high temperature resistance stove evacuation is 10 minutes, feeds the Ar prepurging then 20 minutes, feeds H
2The 4%+Ar mixed gas, flow is 5ml/min, opens water-cooling system;
6, start heating power supply, be heated to 1500 ℃, be incubated 2 hours with the heat-up rate of 6 ℃ of per minutes; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
7, when temperature is reduced to 80 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out the sintering microballoon, promptly obtain preparing high temperature nuclear reactor fuel element UO
2The nuclear core.
Embodiment 2:
Preparation high temperature nuclear reactor fuel element UO
2The method of nuclear core, this method may further comprise the steps:
1, the dry microspheres that contains 7KgU is layed on the circular stainless steel pallet laying depth 2mm through distributor.Pallet places bell-jar low-temperature sintering stove by charging system.
2, open water coolant and pneupress system, the adjusting air flow quantity is 80ml/min.Start heating power supply, temperature increasing schedule is: rise to 300 ℃ from room temperature with 2 ℃/minute temperature rise rate, 8 ℃/minute are warmed up to 500 ℃, are incubated 1 hour.
3, closes compression air vacuumized 30 minutes, fed Ar prepurging 20 minutes, fed Ar+4%H
2, gas flow is 10ml/min.The heat-up rate that per minute is 10 ℃ is heated to 700 ℃, is incubated 3 hours; Close heating power supply, the low temperature oven water-cooled cooling; When temperature is reduced to 60 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet.
4, during the reduction microballoon that contains 14KgU is packed the metal molybdenum crucible into, place high temperature resistance furnace by charging system;
5, the high temperature resistance stove evacuation is 30 minutes, feeds the Ar prepurging then 40 minutes, feeds H
2Gas, flow is 10ml/min, opens water-cooling system;
6, start heating power supply, be heated to 1400 ℃, be incubated 4 hours with the heat-up rate of 5 ℃ of per minutes; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
7, when temperature is reduced to 90 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out the sintering microballoon, promptly obtain preparing high temperature nuclear reactor fuel element UO
2The nuclear core.
Embodiment 3:
Preparation high temperature nuclear reactor fuel element UO
2The method of nuclear core, this method may further comprise the steps:
1, the dry microspheres that contains 4KgU is layed on the circular stainless steel pallet laying depth 0.8mm through distributor.Pallet places bell-jar low-temperature sintering stove by charging system.
2, open water coolant and pneupress system, the adjusting air flow quantity is 200ml/min.Start heating power supply, temperature increasing schedule is: rise to 300 ℃ from room temperature with 1.5 ℃/minute temperature rise rate, 6 ℃/minute are warmed up to 550 ℃, are incubated 1 hour.
3, closes compression air vacuumized 20 minutes, fed Ar prepurging 10 minutes, fed Ar+4%H
2, gas flow is 2ml/min.550 ℃ are incubated 4 hours; Close heating power supply, the low temperature oven water-cooled cooling; When temperature is reduced to 50 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet.
4, during the reduction microballoon that contains 12KgU is packed the metal molybdenum crucible into, place high temperature resistance furnace by charging system;
5, the high temperature resistance stove evacuation is 15 minutes, feeds the Ar prepurging then 20 minutes, feeds H
2Gas, flow is 10ml/min, opens water-cooling system;
6, start heating power supply, be heated to 1650 ℃, be incubated 1 hour with the heat-up rate of 10 ℃ of per minutes; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
7, when temperature is reduced to 70 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out the sintering microballoon, promptly obtain preparing high temperature nuclear reactor fuel element UO
2The nuclear core.
Embodiment 4:
Preparation high temperature nuclear reactor fuel element UO
2The method of nuclear core, this method may further comprise the steps:
1, the dry microspheres that contains 5KgU is layed on the circular stainless steel pallet laying depth 0.6mm through distributor.Pallet places bell-jar low-temperature sintering stove by charging system.
2, open water coolant and pneupress system, the adjusting air flow quantity is 120ml/min.Start heating power supply, temperature increasing schedule is: rise to 300 ℃ from room temperature with 2 ℃/minute temperature rise rate, 10 ℃/minute are warmed up to 500 ℃, are incubated 1 hour.
3, closes compression air vacuumized 15 minutes, fed Ar prepurging 15 minutes, fed Ar+4%H
2, gas flow is 7ml/min.The heat-up rate that per minute is 6 ℃ is heated to 650 ℃, is incubated 2 hours; Close heating power supply, the low temperature oven water-cooled cooling; When temperature is reduced to 50 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet.
4, during the reduction microballoon that contains 5KgU is packed the metal molybdenum crucible into, place high temperature resistance furnace by charging system;
5, the high temperature resistance stove evacuation is 30 minutes, feeds the Ar prepurging then 20 minutes, feeds H
2Gas, flow is 2ml/min, opens water-cooling system;
6, start heating power supply, be heated to 1620 ℃, be incubated 3 hours with the heat-up rate of 7 ℃ of per minutes; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
7, when temperature is reduced to 80 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out the sintering microballoon, promptly obtain preparing high temperature nuclear reactor fuel element UO
2The nuclear core.
Embodiment 5:
Preparation high temperature nuclear reactor fuel element UO
2The method of nuclear core, this method may further comprise the steps:
1, the dry microspheres that contains 6KgU is layed on the circular stainless steel pallet laying depth 1.4mm through distributor.Pallet places bell-jar low-temperature sintering stove by charging system.
2, open water coolant and pneupress system, the adjusting air flow quantity is 150ml/min.Start heating power supply, temperature increasing schedule is: rise to 300 ℃ from room temperature with 1 ℃/minute temperature rise rate, 8 ℃/minute are warmed up to 480 ℃, are incubated 1 hour.
3, closes compression air vacuumized 20 minutes, fed Ar prepurging 30 minutes, fed Ar+4%H
2, gas flow is 10ml/min.The heat-up rate that per minute is 10 ℃ is heated to 680 ℃, is incubated 3 hours; Close heating power supply, the low temperature oven water-cooled cooling; When temperature is reduced to 50 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet.
4, during the reduction microballoon that contains 6KgU is packed the metal molybdenum crucible into, place high temperature resistance furnace by charging system;
5, the high temperature resistance stove evacuation is 20 minutes, feeds the Ar prepurging then 20 minutes, feeds H
2Gas, flow is 7ml/min, opens water-cooling system;
6, start heating power supply, be heated to 1600 ℃, be incubated 2.5 hours with the heat-up rate of 6 ℃ of per minutes; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
7, when temperature is reduced to 90 ℃, close H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out the sintering microballoon, promptly obtain preparing high temperature nuclear reactor fuel element UO
2The nuclear core.
Claims (5)
1. one kind prepares high temperature nuclear reactor fuel element UO
2Examine the method for core, comprise roasting, reduction and the sintering process of microballoon, it is characterized in that this method steps is as follows:
(1) the raw material microballoon is layed in the stainless steel pallet, laying depth is at 0.6~2mm; Pallet is placed low temperature oven;
(2) bubbling air in low temperature oven, air flow quantity 80ml~200ml/min opens water-cooling system, begin the roasting that heats up then, heat-up rate before 300 ℃ was 1~2 ℃ of a per minute, and the heat-up rate after 300 ℃ is 5~10 ℃ of per minutes, 450~550 ℃ of insulations 1 hour; Tail gas enters exhaust system after handling after filtration;
(3) stop bubbling air, low temperature oven vacuumized 10~30 minutes, fed the Ar prepurging then 20~40 minutes, fed H
2Or H
2The 4%+Ar mixed gas, its flow is adjusted into 5~10ml/min;
In this process, furnace maintains 450~550 ℃ of temperature;
(4) heat-up rate according to 5~10 ℃ of per minutes carries out reduction reaction, and the highest reduction temperature is 650~700 ℃, and is incubated 1~4 hour; Close heating power supply after insulation is finished, the stove water-cooled cooling when temperature is reduced to 50~70 ℃, is closed H
2Gas, powered-down, gas and cooling water system when reducing to room temperature take out pallet; Take out microballoon after the reduction and pack in the crucible of sintering, crucible is placed high temperature sintering furnace;
(5) the high temperature sintering stove evacuation is 10~30 minutes, feeds the Ar prepurging then 20~40 minutes, feeds H
2Or H
2The 4%+Ar mixed gas, the adjustment flow is 2~10ml/min, opens water-cooling system;
(6) microballoon is carried out sintering, carry out sintering according to the heat-up rate of 5~10 ℃ of per minutes, the highest sintering temperature is 1400~1650 ℃, soaking time 1~4 hour; After finishing, insulation closes heating power supply, the stove water-cooled cooling;
(7) when temperature is reduced to 50~90 ℃, to close H2 gas and feed Ar gas, powered-down and cooling water system when reducing to room temperature take out crucible, promptly obtain high temperature nuclear reactor fuel element UO
2The nuclear core.
2. a kind of preparation high temperature nuclear reactor fuel element UO according to claim 1
2The method of nuclear core is characterized in that described pallet is the stainless steel pallet.
3. a kind of preparation high temperature nuclear reactor fuel element UO according to claim 1
2The method of nuclear core is characterized in that described low temperature oven is bell-jar or box-type furnace low temperature oven.
4. a kind of preparation high temperature nuclear reactor fuel element UO according to claim 1
2The method of nuclear core is characterized in that described crucible is Al
2O
3Crucible or metal W or Mo crucible tongs.
5. a kind of preparation high temperature nuclear reactor fuel element UO according to claim 1
2The method of nuclear core is characterized in that described high temperature sintering furnace is induction heater or resistance furnace.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CNB2007101757945A CN100551832C (en) | 2007-10-12 | 2007-10-12 | A kind of preparation high temperature nuclear reactor fuel element UO 2The method of nuclear core |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CNB2007101757945A CN100551832C (en) | 2007-10-12 | 2007-10-12 | A kind of preparation high temperature nuclear reactor fuel element UO 2The method of nuclear core |
Publications (2)
Publication Number | Publication Date |
---|---|
CN101172660A true CN101172660A (en) | 2008-05-07 |
CN100551832C CN100551832C (en) | 2009-10-21 |
Family
ID=39421449
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CNB2007101757945A Active CN100551832C (en) | 2007-10-12 | 2007-10-12 | A kind of preparation high temperature nuclear reactor fuel element UO 2The method of nuclear core |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN100551832C (en) |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102229441A (en) * | 2011-05-16 | 2011-11-02 | 清华大学 | Method for preparing quasi-uranium dioxide ceramic fuel microspheres |
CN105642907A (en) * | 2016-01-29 | 2016-06-08 | 中国核动力研究设计院 | UO2-W metal ceramic ball preparation method |
CN106653126A (en) * | 2016-12-28 | 2017-05-10 | 中核北方核燃料元件有限公司 | Method and mould for preparing annular UO2 fuel pellet |
CN108182981A (en) * | 2017-12-27 | 2018-06-19 | 中核北方核燃料元件有限公司 | A kind of spherical shape Nuclear Fuel Element Production Line thickener tanning device and its application method |
CN112122608A (en) * | 2020-09-03 | 2020-12-25 | 江苏精研科技股份有限公司 | Method for reducing oxygen and nitrogen content during sintering in powder injection molding process |
CN112820431A (en) * | 2020-12-31 | 2021-05-18 | 中核北方核燃料元件有限公司 | Metal wall microcapsule nuclear fuel pellet added with oxide and preparation method thereof |
-
2007
- 2007-10-12 CN CNB2007101757945A patent/CN100551832C/en active Active
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN102229441A (en) * | 2011-05-16 | 2011-11-02 | 清华大学 | Method for preparing quasi-uranium dioxide ceramic fuel microspheres |
CN102229441B (en) * | 2011-05-16 | 2013-06-26 | 清华大学 | Method for preparing quasi-uranium dioxide ceramic fuel microspheres |
CN105642907A (en) * | 2016-01-29 | 2016-06-08 | 中国核动力研究设计院 | UO2-W metal ceramic ball preparation method |
CN106653126A (en) * | 2016-12-28 | 2017-05-10 | 中核北方核燃料元件有限公司 | Method and mould for preparing annular UO2 fuel pellet |
CN108182981A (en) * | 2017-12-27 | 2018-06-19 | 中核北方核燃料元件有限公司 | A kind of spherical shape Nuclear Fuel Element Production Line thickener tanning device and its application method |
CN108182981B (en) * | 2017-12-27 | 2019-11-22 | 中核北方核燃料元件有限公司 | A kind of spherical shape Nuclear Fuel Element Production Line thickener tanning device and its application method |
CN112122608A (en) * | 2020-09-03 | 2020-12-25 | 江苏精研科技股份有限公司 | Method for reducing oxygen and nitrogen content during sintering in powder injection molding process |
CN112820431A (en) * | 2020-12-31 | 2021-05-18 | 中核北方核燃料元件有限公司 | Metal wall microcapsule nuclear fuel pellet added with oxide and preparation method thereof |
Also Published As
Publication number | Publication date |
---|---|
CN100551832C (en) | 2009-10-21 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN100551832C (en) | A kind of preparation high temperature nuclear reactor fuel element UO 2The method of nuclear core | |
CN102923699B (en) | Continuous pyrographite purifying device | |
CN101285654B (en) | Microwave sintering apparatus and method | |
CN201289290Y (en) | Rapid cooling type intermediate frequency induction sintering furnace | |
CN104531974A (en) | Large forging quenching heat treatment process | |
CN204159874U (en) | The dual-purpose sintering furnace of vacuum protection atmosphere of metal powder injection molded part | |
CN102229441B (en) | Method for preparing quasi-uranium dioxide ceramic fuel microspheres | |
CN101154485A (en) | Microwave sintering method for thermal resistor with positive temperature coefficient and its special device | |
CN101651101A (en) | Silicon carbide ion activation annealing device and silicon carbide ion activation annealing method | |
CN208234942U (en) | A kind of fusion reactor large scale fine grain component | |
CN102691110A (en) | Annealing process for ingot furnace | |
CN106435738A (en) | Preparation method of cadmium zinc telluride polycrystals | |
CN102491358B (en) | Novel method for preparing amorphous boron powder in tube furnace by taking cut magnesium powder as reducing agent | |
CN106927796A (en) | A kind of preparation method of circular thin-wall boron carbide aluminum oxide pellet | |
CN104451259A (en) | Method for preparing zirconium alloy by sintering discharge plasma | |
CN202350506U (en) | Recycling device for heat energy of intermediate-frequency induction roasting furnace | |
CN102001626A (en) | Method and device for preparing superfine zirconium hydride powder by continuous dynamic hydrogenation method | |
CN210340996U (en) | Annealing device for nut | |
CN103086333A (en) | Production technique of red phosphorus by means of high temperature sealing method | |
CN102794281B (en) | Method for washing graphite piece in thermal field of Czochralski single-crystal furnace | |
CN103159400B (en) | A kind of glass-ceramic rotary processing stove | |
CN206768184U (en) | A kind of Novel annealing furnace | |
CN110128147B (en) | High-temperature-resistant solar heat-collecting ceramic material and preparation method thereof | |
CN216360401U (en) | Vertical activation furnace capable of improving production efficiency of activated carbon | |
CN103570024B (en) | The method that silicon liquid splashes is reduced in polysilicon electron beam melting process |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
C06 | Publication | ||
PB01 | Publication | ||
C10 | Entry into substantive examination | ||
SE01 | Entry into force of request for substantive examination | ||
C14 | Grant of patent or utility model | ||
GR01 | Patent grant |