CN109378097A - A method of preparing simulation spentnuclear fuel - Google Patents
A method of preparing simulation spentnuclear fuel Download PDFInfo
- Publication number
- CN109378097A CN109378097A CN201810960015.0A CN201810960015A CN109378097A CN 109378097 A CN109378097 A CN 109378097A CN 201810960015 A CN201810960015 A CN 201810960015A CN 109378097 A CN109378097 A CN 109378097A
- Authority
- CN
- China
- Prior art keywords
- simulation
- spentnuclear fuel
- organic
- atmosphere
- oxide
- 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
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
-
- 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
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Manufacturing & Machinery (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
A method of simulation spentnuclear fuel is prepared, nuclear material preparation technical field is belonged to.This method is by uranium dioxide, simulation fission product metal oxide and organic additive according to a certain percentage in ball milling mixing abundant on ball mill, and high pressure compression moulding again later is most sintered to obtain simulation spentnuclear fuel afterwards through high-temperature atmosphere.The organic additive includes hydroxyl organic matter, amino-contained organic matter, organic acid or ester-based organic compound, and mass percent of the organic additive in uranium dioxide, simulation fission product metal oxide and organic additive summation is 1-10%, and sintering temperature is lower, is 1400 DEG C -1640 DEG C.This method preparation condition is mild, has firing temperature low, without hydrogen or the advantage lower with hydrogen concentration, firing atmosphere is safer (can use no or little hydrogen).The preparation process condition that the present invention mitigates makes according to simulation fuel prepared by the present invention, at low cost compared with traditional simulation spentnuclear fuel, more economy.
Description
Technical field
The present invention relates to a kind of methods for preparing simulation spentnuclear fuel, belong to nuclear material preparation technical field.
Background technique
Nuclear power is not only the energy of clean and effective, and have capacity is big, technology is more mature, at low cost, freight volume compared with
Small feature, therefore strategy of the nuclear power increasingly by many countries is paid attention to.China by the keynote of nuclear power developing from " actively development
Nuclear power " is promoted to " safe and efficient Nuclear Power Development ", " Nuclear Power Development under the premise of ensuring safety ".However safe and efficient development core
Electricity be unable to do without the nuclear fuel cycle comprising advanced spentnuclear fuel post-processing technology.Spentnuclear fuel is exactly in reactor through neutron bombardment
After nuclear reaction occurs, burn-up level has reached design discharge burn-up, the removal not nuclear fuel used in the reactor from heap
Nuclear fuel in component.It contains a large amount of unspent rise in value material U238 or Th232, and not burning down and newly-generated is easy to crack
Become the transuranic elements such as Np, Am, Cm that material Pu239, U235 or U233 and nuclear fuel generate in irradiation process, and fission
Elements Sr 90, Cs137, Tc99 etc..The spentnuclear fuel that annual whole world nuclear power is drawn off is about 10500tHM.The processing of spentnuclear fuel is disposed
Problem has become the critical issue for influencing nuclear power sustainable development.In spentnuclear fuel, rare earth element (predominantly lanthanide series) and
Actinides occupies the neutron burden of 30% or more fission product and 50% or more." spentnuclear fuel post-processing " is exactly will
After the spentnuclear fuel drawn off decomposes, most of U, Pu resource that can be continued with of recycling, separation removes most neutron poison, especially
It is lanthanide series.Since " spentnuclear fuel post-processing " (refers to spentnuclear fuel conduct after temporary cooling compared to " once passing through "
Waste is directly stored in deep geological disposal library) processing strategie, it gives up with nuclear fuel utilization efficiency can be improved, reduce geological disposal
The advantages that object amount, main nuclear energy uses state all tends to take this mode in the world at present.
Due to true spentnuclear fuel radioactivity with super strength, main nuclear power country of the world grinds in spentnuclear fuel post-processing technology
Study carefully and in development process, will not all directly adopt true spentnuclear fuel, but uses simulation spentnuclear fuel.Simulation fuel generally by
Uranium dioxide and some rare earth oxides and metal oxide containing precious metals composition.In order to replicate the mixing of spentnuclear fuel from microstructure
Phase, when spentnuclear fuel is simulated in preparation, it is necessary to realize evenly dispersed and balance each other.This implies that simulation spentnuclear fuel composition is necessary
It is uniformly mixed in submicron order, requires heat to sufficiently high temperature, later to obtain uniform diffusion rate on atomic level.
From the point of view of open source literature report, the preparation condition for simulating spentnuclear fuel is very harsh.Germany and Canadian scholar are in document (PG
Lucuta, RA Verrall, H Matzke, BJ Palmer.Microstructural features of SIMFUEL-
Simulated high-burnup UO2-based nuclear fuel.Journal of Nuclear Materials,
1991,178 (1): 48-60) in the simulation spentnuclear fuel preparation process that provides and condition be, corresponding mixed oxide object is high
Energy, wet ball-milling mix, and are then spray-dried, and little particle will pass through precompressed, granulation, compression moulding, then in 1650 DEG C of pure hydrogen
2h is fired under atmosphere；South Korea scholar is in document (KH Kang, SH Na, KC Song, SH Lee, SW Kim.Oxidation
behavior of the simulated fuel with dissolved fission products in air at 573–
873K.Thermochimica Acta.2007,455:129-133) in the simulation spentnuclear fuel preparation condition that provides are as follows: by dioxy
Change uranium and additives mixed, spherolite is pressed under 300MPa pressure, then obtain through 1700 DEG C of pure hydrogen processing 4h.South Korea scholar
In document (KH Kang, KC Song, HS Park, JS Moon, MS Yang.Fabrication of simulated DUPIC
Fuel.Metals and Materials, 2000,6 (6): 583-588) in the simulation spentnuclear fuel preparation process condition that provides are as follows:
After corresponding oxide mixture mixes 2 hours in tube mixer, ground 5 times 15 minutes with 150 turns of disk breaker,
126MPa-161MPa compression moulding, in pure H2Lower 1800 DEG C of atmosphere are sintered 12 hours.Nearest South Korea scholar is in document (EY
Choi, JW Lee, JJ Park, JM Hur, JK Kim, KY Jung, SM Jeong.Electrochemical reduction
behavior of a highly porous SIMFUEL particle in a LiCl molten salt.Chemical
Engineering Journal.2012,207-208 (10): 514-520) the simulation spentnuclear fuel preparation process condition provided in
Are as follows: corresponding oxide mixture mixes after mortar grinder through tube mixer, and wet grinding 4h, 300MPa compacting finally exists
4%H26h is fired in 1700 DEG C of Ar.
Totally apparently, the preparation condition of the simulation spentnuclear fuel of open report is very harsh, and one side sintering temperature is very high, greatly
All at 1650-1800 DEG C, it is well known that when firing temperature is higher than 1600 DEG C, to heating furnace and the material for holding material container
Quality requirement is especially high；On the other hand, the atmosphere of firing is mostly pure hydrogen, and minimum density of hydrogen is 4%H2–Ar.It is above-mentioned severe
Preparation condition make simulate spentnuclear fuel preparation cost it is very high, also allow it is many intend carry out spentnuclear fuels post-processing research sections
Unit is ground to hang back.Therefore, research and development preparation condition is mild, firing temperature is low, firing atmosphere is safer, at low cost
Simulation spentnuclear fuel preparation process, for promote spent fuel reprocessing process research and development have important theory and reality
Meaning.
Summary of the invention
In order to solve, traditional analog spentnuclear fuel preparation condition is harsh, firing temperature is high, firing atmosphere safety is poor, at high cost
The problem of, the atmosphere that can generate localized hyperthermia and reproducibility is roasted in inert atmosphere or reducing atmosphere based on organic matter, from
And make the metal oxide mixed in the external Research Thinking for controlling and being reduced sufficiently in the lower situation of temperature, this hair
It is bright to be intended to provide the simulation spentnuclear fuel system that a kind of preparation condition is mild, firing temperature is lower, firing atmosphere is safer, at low cost
Preparation Method.
Technical scheme is as follows:
A method of preparing simulation spentnuclear fuel, it is characterised in that described method includes following steps:
1) by the uranium dioxide of 81%-96%, the simulation fission product metal oxide of 3%-18% and having for 1-10%
Powder is made in ball milling mixing on ball mill in machine aided agent, and by powder tablet press machine high pressure compression moulding；
2) by the blank of compression moulding temperature be 1400-1640 DEG C at carry out high-temperature atmosphere sintering, obtain simulation it is weary
Fuel.
In above-mentioned technical proposal, the organic additive includes hydroxyl organic matter, amino-contained organic matter, organic acid or ester
Type organic.The simulation fission product metal oxide includes molybdenum trioxide, zirconium dioxide, neodymium oxide, titanium dioxide
Ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide.
In step 2) of the invention, the high-temperature atmosphere sintering is carried out in air, inert atmosphere or reducing atmosphere
High temperature sintering；The reducing atmosphere refers to the gaseous mixture of one of hydrogen, carbon monoxide or ammonia with inert atmosphere,
The percent by volume of middle hydrogen, carbon monoxide or ammonia in gaseous mixture is 0-4%；The inert atmosphere refer to nitrogen, argon gas,
Helium or its gaseous mixture.
The present invention has that preparation condition is mild, firing temperature is lower compared with traditional simulation spentnuclear fuel preparation process
The features such as (1400-1640 DEG C), firing atmosphere safer (hydrogen can be used no or little), and with traditional simulation spentnuclear fuel
Preparation method is compared, at low cost, more economy.
Detailed description of the invention
Fig. 1 is process flow chart of the invention.
Fig. 2 is the simulation spentnuclear fuel pictorial diagram being prepared in embodiment 1.
Specific embodiment
Weary combustion is simulated including the preparation of raw material mixing-step of compression moulding-high temperature sintering three the present invention provides a kind of
The process of material.Uranium dioxide, simulation fission product metal oxide and organic additive are weighed in proportion and sufficiently ball milling is mixed
It closes, high pressure compression moulding again later, is most sintered to obtain simulation spentnuclear fuel through high-temperature atmosphere afterwards.Uranium dioxide, simulation fission product
The percentage of metal oxide and organic additive in the feed is respectively 81%-96%, 3%-18% and 1%-10%；Described
Simulating fission product metal oxide includes molybdenum trioxide (MoO3), zirconium dioxide (ZrO2), neodymium oxide (Nd2O3), dioxy
Change ruthenium (RuO2), ceria (CeO2), barium carbonate (BaCO3), palladium oxide (PdO), lanthanum sesquioxide (La2O3), strontium oxide strontia
(SrO), yttria (Y2O3) and rhodium sesquioxide (Rh2O3).Using hydroxyl organic matter, (such as alcohols has organic additive
Machine object, phenol organic matter etc.), amino-contained organic matter (such as primary amine, tertiary amine, secondary amine, amide organic matter etc.), organic acid (such as
Organic carboxyl acid, organic sulfonic acid, amino acid etc.) or ester-based organic compound.Sintering temperature is 1400-1640 DEG C, and high-temperature atmosphere includes sky
Gas, inert atmosphere or reducing atmosphere, reducing atmosphere is using one of hydrogen, carbon monoxide and ammonia and inert atmosphere
Gaseous mixture, wherein the percent by volume of hydrogen, carbon monoxide or ammonia in gaseous mixture is 0-4%.
Below by embodiment, the present invention will be described in detail, it should be noted that following examples are simulated two in spentnuclear fuel
Urania and the composition for simulating fission product metal oxide prepare (With 55GWd/tU burnup according to such as the following table 1
and 8years of cooling)。
The composition of the simulation spentnuclear fuel of table 1
Embodiment 1:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive hexamethylenetetramine (amino-contained organic matter), hexamethylenetetramine is in uranium dioxide, simulation fission product metal
Mass percent is 7% in oxide and organic additive summation.Ball grinder is added in above-mentioned material, makes object in ball milling on ball mill
Material is sufficiently mixed.It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 300MPa, and maintain 10 minutes, obtain
It to cylinder blank, is placed in high temperature process furnances, is passed through 3%H2/ Ar gaseous mixture, is gradually heated to 1640 DEG C, roast after 6h from
It so is down to room temperature, obtains simulation spentnuclear fuel.
Comparative example 1:
South Korea scholar is in document (K.H.Kang, S.H.Na, K.C.Song, S.H.Lee, S.W.Kim.Oxidation
behavior of the simulated fuel with dissolved fission products in air at 573–
873K.Thermochimica Acta.2007,455:(2007) 129-133) preparation process that provides: it is provided according to document
Uranium dioxide and other metal oxides are sufficiently mixed by ratio, the compression moulding under 300MPa pressure, through 1700 DEG C of pure hydrogens
It handles 4h and obtains simulation spentnuclear fuel.
Embodiment 2:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
Organic additive hexamethylenetetramine is measured, hexamethylenetetramine is in uranium dioxide, simulation fission product metal oxide and has machine aided
Mass percent is 1% in agent summation.Ball grinder is added in above-mentioned material, is sufficiently mixed material in ball milling on ball mill.Claim
It takes 11 grams of mixed material to be put into cylindrical die, is suppressed in 300MPa, and maintain 5 minutes, obtain cylinder blank, set
In high temperature process furnances, it is passed through 4%H2/ He gaseous mixture is gradually heated to 1400 DEG C, is down to room temperature naturally after roasting 8h, obtains
Simulate spentnuclear fuel.
Comparative example 2: South Korea scholar is in document (KH Kang, KC Song, HS Park, JS Moon, MS
Yang.Fabrication of Simulated DUPIC Fuel fuel.Metals and Materials,2000,6(6):
The simulation spentnuclear fuel preparation process provided in 583-588): by uranium dioxide and other corresponding oxide mixtures in tubular-mix
After being mixed 2 hours in device, ground 5 times 15 minutes with 150 turns of disk breaker, 126MPa-161MPa compression moulding, in pure H2
Lower 1800 DEG C of atmosphere are sintered 12 hours, obtain simulation spentnuclear fuel.
Embodiment 3:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive beta cyclodextrin (hydroxyl organic matter), beta cyclodextrin is in uranium dioxide, simulation fission product metal oxide and has
Mass percent is 5% in machine aided agent summation.Ball grinder is added in above-mentioned material, keeps material sufficiently mixed in ball milling on ball mill
It closes.It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 150MPa, maintain 12 minutes, obtain cylindrical base
Material, is placed in high temperature process furnances, is passed through 2%CO/He gaseous mixture, is gradually heated to 1600 DEG C, is down to room temperature naturally after roasting 4h,
Obtain simulation spentnuclear fuel.
Comparative example 3: South Korea scholar document (EY Choi, JW Lee, JJ Park, JM Hur, JK Kim, KY Jung,
SM Jeong.Electrochemical reduction behavior of a highly porous SIMFUEL
particle in a LiCl molten salt.Chemical Engineering Journal.2012,207-208(10):
The simulation spentnuclear fuel preparation process provided in 514-520): by uranium dioxide and other corresponding oxide mixtures in mortar grinder
Tube mixer mixing, wet grinding 4h, 300MPa compacting, finally in 4%H26h is fired in 1700 DEG C of/Ar.
Embodiment 4:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive beta cyclodextrin (hydroxyl organic matter), beta cyclodextrin is in uranium dioxide, simulation fission product metal oxide and has
Mass percent is 8% in machine aided agent summation.Ball grinder is added in above-mentioned material, keeps material sufficiently mixed in ball milling on ball mill
It closes.It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 250MPa, maintain 8 minutes, obtain cylindrical base
Material, is placed in high temperature process furnances, is passed through 3%H2/ Ar gaseous mixture is gradually heated to 1550 DEG C, is down to room temperature naturally after roasting 2h,
Obtain simulation spentnuclear fuel.
Comparative example 4:
Germany and Canadian scholar are in document (PG Lucuta, RA Verrall, H Matzke, BJ
Palmer.Microstructural features of SIMFUEL—simulated high-burnup UO2-based
Nuclear fuel.Journal of Nuclear Materials, 1991,178 (1): 48-60) in the weary combustion of simulation that provides
Expect preparation process: corresponding mixed oxide object high energy, wet ball-milling being mixed, are then spray-dried, little particle will be by pre-
Pressure is granulated, compression moulding, then fires 2h under 1650 DEG C of pure hydrogen atmospheres.
Embodiment 5:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive citric acid (organic acid), citric acid is total in uranium dioxide, simulation fission product metal oxide and organic additive
It is 3% with middle mass percent.Ball grinder is added in above-mentioned material, is sufficiently mixed material in ball milling on ball mill.It weighs mixed
11 grams of material after conjunction are put into cylindrical die, suppress in 200MPa, maintain 15 minutes, obtain cylinder blank, be placed in height
In warm tube furnace, it is passed through 3%H2/N2Gaseous mixture is gradually heated to 1640 DEG C, is down to room temperature naturally after roasting 2h, obtains simulating weary
Fuel.
Embodiment 6:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive ethyl caprilate (ester-based organic compound), ethyl caprilate is in uranium dioxide, simulation fission product metal oxide and has
Mass percent is 9% in machine aided agent summation.Ball grinder is added in above-mentioned material, keeps material sufficiently mixed in ball milling on ball mill
It closes.It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 280MPa, maintain 12 minutes, obtain cylindrical base
Material, is placed in high temperature process furnances, is passed through 1%H2/ Ar gaseous mixture is gradually heated to 1640 DEG C, is down to room temperature naturally after roasting 5h,
Obtain simulation spentnuclear fuel.
Embodiment 7:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
Organic additive hexamethylenetetramine is measured, hexamethylenetetramine is in uranium dioxide, simulation fission product metal oxide and has machine aided
Mass percent is 10% in agent summation.Ball grinder is added in above-mentioned material, is sufficiently mixed material in ball milling on ball mill.Claim
It takes 11 grams of mixed material to be put into cylindrical die, is suppressed in 300MPa, maintain 3 minutes, obtain cylinder blank, be placed in
In high temperature process furnances, it is passed through inert gas argon gas, is gradually heated to 1450 DEG C, room temperature is down to naturally after roasting 6h, is simulated
Spentnuclear fuel.
Embodiment 8:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive beta cyclodextrin (hydroxyl organic matter), beta cyclodextrin is in uranium dioxide, simulation fission product metal oxide and has
Mass percent is 10% in machine aided agent summation.Ball grinder is added in above-mentioned material, keeps material sufficiently mixed in ball milling on ball mill
It closes.It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 250MPa, maintain 13 minutes, obtain cylindrical base
Material, is placed in high temperature process furnances, and 1550 DEG C are gradually heated in air atmosphere, is down to room temperature naturally after roasting 5h, obtains mould
Quasi- spentnuclear fuel.
Embodiment 9:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
It measures organic additive n-octyl alcohol (hydroxyl organic matter), n-octyl alcohol is in uranium dioxide, simulation fission product metal oxide and organic
Mass percent is 2% in auxiliary agent summation.Ball grinder is added in above-mentioned material, is sufficiently mixed material in ball milling on ball mill.
It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 280MPa, maintain 9 minutes, obtain cylinder blank, set
In high temperature process furnances, it is passed through 3%H2/N2Gaseous mixture is gradually heated to 1620 DEG C, is down to room temperature naturally after roasting 6h, obtains mould
Quasi- spentnuclear fuel.
Embodiment 10:
30 grams of uranium dioxide are weighed, weigh molybdenum trioxide, zirconium dioxide, neodymium oxide, dioxy according to the ratio in table 1
Change ruthenium, ceria, barium carbonate, palladium oxide, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide, and weighs and determine
Measure organic additive polyethylene glycol (hydroxyl organic matter), polyethylene glycol uranium dioxide, simulation fission product metal oxide and
Mass percent is 1% in organic additive summation.Ball grinder is added in above-mentioned material, keeps material sufficiently mixed in ball milling on ball mill
It closes.It weighs 11 grams of mixed material to be put into cylindrical die, be suppressed in 300MPa, maintain 4 minutes, obtain cylindrical base
Material, is placed in high temperature process furnances, is passed through 1%H2/ Ar gaseous mixture is gradually heated to 1640 DEG C, is down to room temperature naturally after roasting 4h,
Obtain simulation spentnuclear fuel.
Claims (5)
1. a kind of method for preparing simulation spentnuclear fuel, it is characterised in that described method includes following steps:
1) uranium dioxide of 81%-96%, the simulation fission product metal oxide of 3%-18% and 1-10% there is into machine aided
Powder is made in ball milling mixing on ball mill in agent, and by powder tablet press machine high pressure compression moulding；
2) by the blank of compression moulding temperature be 1400-1640 DEG C at carry out high-temperature atmosphere sintering, obtain simulation spentnuclear fuel.
2. a kind of method for preparing simulation spentnuclear fuel according to claim 1, which is characterized in that the organic additive packet
Include hydroxyl organic matter, amino-contained organic matter, organic acid or ester-based organic compound.
3. a kind of method for preparing simulation spentnuclear fuel according to claim 1 or 2, which is characterized in that the simulation is split
Selling of one's property object metal oxide includes molybdenum trioxide, zirconium dioxide, neodymium oxide, ruthenic oxide, ceria, barium carbonate, oxygen
Change palladium, lanthanum sesquioxide, strontium oxide strontia, yttria and rhodium sesquioxide.
4. a kind of method for preparing simulation spentnuclear fuel according to claim 1, which is characterized in that high temperature described in step 2)
Atmosphere sintering is that high temperature sintering is carried out in air, inert atmosphere or reducing atmosphere.
5. a kind of method for preparing simulation spentnuclear fuel according to claim 4, which is characterized in that the reducing atmosphere
Refer to the gaseous mixture of one of hydrogen, carbon monoxide or ammonia with inert atmosphere, wherein hydrogen, carbon monoxide or ammonia are mixed
Closing the percent by volume in gas is 0-4%；The inert atmosphere refers to nitrogen, argon gas, helium or its gaseous mixture.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810960015.0A CN109378097B (en) | 2018-08-22 | 2018-08-22 | Method for preparing simulated spent fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201810960015.0A CN109378097B (en) | 2018-08-22 | 2018-08-22 | Method for preparing simulated spent fuel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109378097A true CN109378097A (en) | 2019-02-22 |
| CN109378097B CN109378097B (en) | 2020-09-22 |
Family
ID=65404515
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201810960015.0A Active CN109378097B (en) | 2018-08-22 | 2018-08-22 | Method for preparing simulated spent fuel |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109378097B (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110218092A (en) * | 2019-05-20 | 2019-09-10 | 中国核动力研究设计院 | A kind of UO adding microelement2-ZrO2Ceramic material and preparation method thereof |
| CN113488217A (en) * | 2021-06-22 | 2021-10-08 | 中国原子能科学研究院 | Preparation method of simulated spent fuel |
| CN113488217B (en) * | 2021-06-22 | 2024-05-14 | 中国原子能科学研究院 | Preparation method of simulated spent fuel |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4671904A (en) * | 1984-02-20 | 1987-06-09 | Kraftwerk Union Aktiengesellschaft | Method for producing oxidic sintered nuclear fuel bodies |
| JPS63214693A (en) * | 1987-03-04 | 1988-09-07 | 日本ニユクリア・フユエル株式会社 | Manufacture of nuclear fuel sintered body |
| RU2360307C2 (en) * | 2007-07-17 | 2009-06-27 | Открытое акционерное общество "Новосибирский завод химконцентратов" | Method of fuel pellet production for nuclear fuel elements |
| CN107108375A (en) * | 2014-12-18 | 2017-08-29 | 阿雷瓦核废料回收公司 | The method for producing the pellet of at least one metal oxide |
-
2018
- 2018-08-22 CN CN201810960015.0A patent/CN109378097B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4671904A (en) * | 1984-02-20 | 1987-06-09 | Kraftwerk Union Aktiengesellschaft | Method for producing oxidic sintered nuclear fuel bodies |
| JPS63214693A (en) * | 1987-03-04 | 1988-09-07 | 日本ニユクリア・フユエル株式会社 | Manufacture of nuclear fuel sintered body |
| RU2360307C2 (en) * | 2007-07-17 | 2009-06-27 | Открытое акционерное общество "Новосибирский завод химконцентратов" | Method of fuel pellet production for nuclear fuel elements |
| CN107108375A (en) * | 2014-12-18 | 2017-08-29 | 阿雷瓦核废料回收公司 | The method for producing the pellet of at least one metal oxide |
Non-Patent Citations (2)
| Title |
|---|
| H.P.NAWADA ET AL.: "OXIDATION AND PHASE BEHAVIOUR STUDIES OF THE U-Ce-0 SYSTEM", 《JOURNAL OF NUCLEAR MATERIALS》 * |
| P.C. LUCUTA ET AL.: "Microstructural features of SIMFUEL - Simulated high-burnup UO2- based nuclear fuel", 《JOURNAL OF NUCLEAR MATERIALS》 * |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110218092A (en) * | 2019-05-20 | 2019-09-10 | 中国核动力研究设计院 | A kind of UO adding microelement2-ZrO2Ceramic material and preparation method thereof |
| CN110218092B (en) * | 2019-05-20 | 2022-03-18 | 中国核动力研究设计院 | UO added with trace elements2-ZrO2Ceramic material and preparation method thereof |
| CN113488217A (en) * | 2021-06-22 | 2021-10-08 | 中国原子能科学研究院 | Preparation method of simulated spent fuel |
| CN113488217B (en) * | 2021-06-22 | 2024-05-14 | 中国原子能科学研究院 | Preparation method of simulated spent fuel |
Also Published As
| Publication number | Publication date |
|---|---|
| CN109378097B (en) | 2020-09-22 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Akie et al. | A new fuel material for once-through weapons plutonium burning | |
| Durazzo et al. | Phase studies in the UO2–Gd2O3 system | |
| Oversby et al. | Control of civilian plutonium inventories using burning in a non-fertile fuel | |
| US3504058A (en) | Process for manufacturing sintered pellets of nuclear fuel | |
| CN111039674B (en) | Gadolinium zirconate ceramic for solidifying TRPO simulation waste and preparation method thereof | |
| Boczar et al. | Thorium fuel-cycle studies for CANDU reactors | |
| JP6836992B2 (en) | How to make pellets of at least one type of metal oxide | |
| Croixmarie et al. | Fabrication of transmutation fuels and targets: the ECRIX and CAMIX-COCHIX experience | |
| JP2014529738A5 (en) | ||
| Drera et al. | Thorium fuel production and results from beginning of life irradiation | |
| CN105377763B (en) | The new material formed by uranium, gadolinium and oxygen and its purposes as consumable neutron poison | |
| CN109378097A (en) | A method of preparing simulation spentnuclear fuel | |
| RU2362223C1 (en) | High burnup nuclear uranium-gadolinium fuel on basis for uranium dioxide and method for its acquisition (versions) | |
| JPS60188881A (en) | Manufacture of oxide nuclear fuel sintered body | |
| Kang et al. | Fabrication of simulated DUPIC fuel | |
| Mukerjee et al. | Fabrication technologies for ThO2-based fuel | |
| CN101807445B (en) | Preparation method of quadrivalent uranium-cerium-oxygen solid solution | |
| KR100969640B1 (en) | A fabrication method of nuclear fuel pellet by using high burnup spent nuclear fuel containing metal impurities | |
| WO2020197435A1 (en) | Remix - fuel for a nuclear fuel cycle | |
| Duan et al. | Dissolution extraction of uranium oxides and cerium oxide with TBP-HNO3 complex in supercritical CO2 | |
| RU2396611C1 (en) | Method of preparing nuclear fuel pellets | |
| Durazzo et al. | The role of Gd2O3 phase transition on UO2-Gd2O3 fuel sintering | |
| Rhee et al. | Fabrication of boron-containing burnable absorber fuel pellet | |
| CN113488217B (en) | Preparation method of simulated spent fuel | |
| Hamilton | Removal of uranium from thorium-uranium SIMFUEL by fluoride volatility |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |