CN109979611A - A kind of enhanced uranium dioxide pellet of radial thermal conductivity and preparation method - Google Patents
A kind of enhanced uranium dioxide pellet of radial thermal conductivity and preparation method Download PDFInfo
- Publication number
- CN109979611A CN109979611A CN201910242639.3A CN201910242639A CN109979611A CN 109979611 A CN109979611 A CN 109979611A CN 201910242639 A CN201910242639 A CN 201910242639A CN 109979611 A CN109979611 A CN 109979611A
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- sintering
- uranium dioxide
- thermal conductivity
- pellet
- radial thermal
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- 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
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/623—Oxide fuels
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/62—Ceramic fuel
- G21C3/64—Ceramic dispersion fuel, e.g. cermet
-
- 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
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Ceramic Engineering (AREA)
- Manufacturing & Machinery (AREA)
- Dispersion Chemistry (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
The invention discloses a kind of enhanced uranium dioxide pellet of radial thermal conductivity and preparation methods, to solve deficiency of the uranium dioxide as commercial heap fuel ball heating conduction in the prior art, the disadvantage for the low radial heat conductivity being especially directly linked with reactor economy and safety.The enhanced uranium dioxide pellet of radial thermal conductivity of the invention, by uranium dioxide raw material powder, 70-98:2-30 is made by volume with wire mesh, in the fuel pellet, radially stratiform is uniformly distributed in uranium dioxide pellet wire mesh, plays the effect to pellet " skeleton " support.Design science of the present invention, method is concise, can substantially enhance the radial thermal conductivity of uranium dioxide；And without mixing step, environmental-friendly, process control has raising efficiency, reduces energy consumption, shorten the period, simplify the advantages such as technique.
Description
Technical field
The invention belongs to fission reactor Material Fields, and in particular to a kind of enhanced uranium dioxide fuel of radial thermal conductivity
Pellet and preparation method.
Background technique
In March, 2011, Japanese special violent earthquake, tsunami lead to Fukushima nuclear-power reactor main cooling system and emergency cooling system
Damage inactivation, reactor core dehydration, fuel pellet inside waste heat timely and effective cannot export, and cause fuel element fusing, breakage, largely
Radioactive product leaks, and forms earthquake-a chain of disaster of tsunami-nuclear accident, the more heaps for causing the superposition of extreme external event to cause
Common mode major accident.
Currently, the nuclear fuel being most widely used in commercial nuclear reactor is ceramic mould uranium dioxide, and uranium dioxide core
The significant drawback of block is that thermal conductivity is low (1000 DEG C of about 2.8W/m.k).Particularly, the radial thermal conductivity of uranium dioxide is compared with axis
It should more be paid close attention to thermal conductivity.Uranium dioxide radial thermal conductivity determines what fuel pellet was conducted heat by cladding materials to coolant
Ability；Meanwhile uranium dioxide pellet, when being on active service in heap, inside forms high radial symmetry gradient (2000-4000 DEG C/cm),
Larger thermal stress and crackle are generated, easily increases fission gas rate of release under high burnup, leads to fuel void swelling.This makes
The about service efficiency of uranium dioxide pellet and service life, and directly affect nuclear power station economy and safety.
Therefore it provides a kind of uranium dioxide pellet can improve fuel pellet with excellent radial heating conduction
Service efficiency and the service life, promoted accidental conditions under economy and the safety under accident conditions, become this field
Technical staff's urgent problem to be solved.
Summary of the invention
Technical problem solved by the present invention is providing a kind of enhanced uranium dioxide pellet of radial thermal conductivity, solve
Uranium dioxide is insufficient as commercial reactor nuclear fuel heating conduction in the prior art, especially direct with economy and safety
The disadvantage of associated low radial thermal conductivity.
The present invention also provides the preparation methods of the fuel pellet.
The technical solution adopted by the invention is as follows:
The enhanced uranium dioxide pellet of a kind of radial thermal conductivity of the present invention, by uranium dioxide raw material powder and gold
Belonging to silk screen, 70-98:2-30 is made by volume, and in the fuel pellet, radially stratiform is uniformly distributed in dioxy to wire mesh
Change in uranium pellet.
Further, it is sintered after being stacked by uranium dioxide raw material powder with wire mesh stratiform.
Further, any one of the wire mesh type in molybdenum filament net, tungsten silk screen, nickel wire net.
Further, the mesh number of the wire mesh is 10-300 mesh, and the wire diameter of the wire mesh is 10-
380μm。
The preparation method of the enhanced uranium dioxide pellet of a kind of radial thermal conductivity of the present invention, first by metal
Silk screen is cut on slicer in sintering mold according to the ratio successively alternately adds dioxy with the matched disk of mould diameter
Change uranium raw material powder and wire mesh, by being sintered at high temperature into the enhanced uranium dioxide pellet of radial thermal conductivity.
Further, specifically includes the following steps:
Step 1. uranium dioxide raw material powder and wire mesh are stacked alternately
After wire mesh ultrasound is cleaned, it is cut into the disk with sintering mold diameter matches on slicer, is being sintered
In mold, according to a certain ratio, it is stacked alternately uranium dioxide raw material powder and wire mesh disk, making wire mesh, radially stratiform is equal
Even distribution；
The densification of step 2. high temperature sintering
The mixture that step 1 is stacked to the uranium dioxide raw material powder and wire mesh that finish is sintered densification, then
Demoulding.
Further, in the step 2, sintering processing be electric discharge plasmon sintering, hot pressed sintering, without pressure atmosphere sintering
Any one.
Further, in the step 2, when sintering processing is electric discharge plasmon sintering, specific sintering condition are as follows: sintering
Atmosphere is vacuum, and sintering temperature is 1000 DEG C -1500 DEG C, and heating rate is 50-300 DEG C/min, soaking time 2-30min,
Pressure is 30-80MPa, vacuum degree 10-1-20Pa。
Further, when sintering processing is hot pressed sintering, specific sintering condition are as follows: sintering atmosphere is argon gas, sintering temperature
It is 1200 DEG C -1600 DEG C, heating rate is 5-50 DEG C/min, soaking time 0.5-4h, pressure 50-80MPa.
Further, when sintering processing is without pressure atmosphere sintering, specific sintering condition are as follows: first applying charge plasma is pre-
Thermal sintering, then by pre-sintered body without atmosphere sintering densification of calming the anger；Wherein, pre-sintering atmosphere is vacuum, and pre-sintering temperature is
600-900 DEG C, soaking time 2-10min, pressure 30-50MPa, vacuum degree 10-1-20Pa；Burning without pressure atmosphere sintering
Knot atmosphere is H2, sintering temperature is 1650-1850 DEG C, 1-10 DEG C of heating rate/min, soaking time 2-10h, and hydrogen flowing quantity is
0.2-2L/min。
Compared with prior art, the invention has the following advantages:
Design science of the present invention, method are concise.Preparation process is not necessarily to mixing step, can reduce the pollution risk to environment；
The wire mesh stratiform of high heat conductance is uniformly distributed in uranium dioxide pellet, thermally conductive is provided for the radial direction of uranium dioxide pellet
Main thoroughfare can significantly improve the disadvantage of the low radial thermal conductivity of existing uranium dioxide pellet, promote fuel pellet and reacting
Economy under heap service condition and the safety under accident conditions.
The present invention is by introducing wire mesh in uranium dioxide to realize the purpose of enhancing pellet radial thermal conductivity.Metal
Silk screen (molybdenum net, tungsten net, nickel screen) has excellent thermal conductivity, good mechanical behavior under high temperature, with stratiform edge in uranium dioxide
Radial distribution can be obviously improved pellet radial thermal conductivity, to a certain degree enhancing axial thermal conductivity, and " skeleton " branch is played in pellet
Support effect, has both the advantage for improving mechanical behavior under high temperature
Method of the invention is environmentally friendly due to not needing mixing step, and has raising efficiency, reduces energy consumption, contracting
Short cycle simplifies the advantages such as technique.
The enhanced uranium dioxide pellet of a kind of radial thermal conductivity prepared by the present invention can be used as commercial heap fuel pellet
Candidate fuel has potential application prospect.
Detailed description of the invention
The enhanced uranium dioxide pellet structure design diagram of Fig. 1 radial thermal conductivity.
Fig. 2 is the microstructure spectrogram of the enhanced uranium dioxide pellet of radial thermal conductivity prepared by the present invention.
Specific embodiment
All features disclosed in this specification or disclosed all methods or in the process the step of, in addition to mutually exclusive
Feature and/or step other than, can combine in any way.
Any feature disclosed in this specification unless specifically stated can be equivalent or with similar purpose by other
Alternative features are replaced.That is, unless specifically stated, each feature is an example in a series of equivalent or similar characteristics
?.
Embodiment 1
Present embodiment discloses the preparation of the enhanced uranium dioxide pellet of radial thermal conductivity of the invention, specifically:
After step 1. cleans molybdenum filament net ultrasound, the disk with sintering mold diameter matches is cut on slicer,
It is by volume 98:2 in sintering mold, is stacked alternately uranium dioxide raw material powder and molybdenum filament net disk, makes wire mesh radially
Stratiform is uniformly distributed, and wherein the mesh number of molybdenum filament net is 10 mesh, and the diameter of molybdenum filament is 380 μm；
The mixture of the uranium dioxide raw material powder stacked through step 1 and molybdenum filament net is carried out electric discharge plasmon by step 2.
Sintering densification, sintering atmosphere are vacuum, and sintering temperature is 1000 DEG C, and heating rate is 50 DEG C/min, soaking time 2min,
Pressure is 30MPa, vacuum degree 10-1Pa, and rear demoulding, dimensioned processing.
The structure of fuel pellet made from the present embodiment is as shown in Fig. 1, and radially stratiform is uniformly distributed in wire mesh
In uranium dioxide pellet；Microstructure spectrogram is as shown in Fig. 2.
After measured, sample manufactured in the present embodiment promotes 60% or more compared with standard uranium dioxide pellet radial thermal conductivity
(800-1200 DEG C), axial thermal conductivity improve 5% or more (800-1200 DEG C).
Embodiment 2
Present embodiment discloses the preparations of the enhanced uranium dioxide pellet of radial thermal conductivity of the invention, with embodiment
1 compares, and condition when electric discharge plasmon is sintered is different, remaining is all the same.Item when the present embodiment electric discharge plasmon sintering
Part are as follows: sintering atmosphere is vacuum, and sintering temperature is 1500 DEG C, and heating rate is 300 DEG C/min, soaking time 30min, pressure
For 80MPa, vacuum degree 20Pa.
After measured, sample manufactured in the present embodiment promotes 65% or more compared with standard uranium dioxide pellet radial thermal conductivity
(800-1200 DEG C), axial thermal conductivity improve 5% or more (800-1200 DEG C).
Embodiment 3
Present embodiment discloses the preparation of the enhanced uranium dioxide pellet of radial thermal conductivity of the invention, specifically:
After step 1. tungsten silk screen ultrasound is cleaned, it is cut into the disk with sintering mold diameter matches on slicer, is burning
It ties in mold, is by volume 80:20, is stacked alternately uranium dioxide raw material powder and tungsten silk screen disk, make wire mesh radially
Stratiform is uniformly distributed, and wherein the mesh number of tungsten silk screen is 100 mesh, and the diameter of tungsten wire is 25 μm；
The mixture of the uranium dioxide raw material powder and tungsten silk screen that stack through step 1 is carried out hot pressed sintering densification by step 2.
Change, sintering atmosphere is argon gas, and sintering temperature is 1200 DEG C, and heating rate is 5 DEG C/min, soaking time 4h, and pressure is
80MPa.And rear demoulding, dimensioned processing.
After measured, sample manufactured in the present embodiment compared with standard uranium dioxide pellet radial thermal conductivity promoted 300% with
Upper (800-1200 DEG C), axial thermal conductivity improve 30% or more (800-1200 DEG C).
Embodiment 4
Present embodiment discloses the preparations of the enhanced uranium dioxide pellet of radial thermal conductivity of the invention, with embodiment
3 compare, and condition when hot pressed sintering is different, remaining is all the same.Condition when the present embodiment hot pressed sintering are as follows: sintering atmosphere is argon
Gas, sintering temperature are 1600 DEG C, and heating rate is 50 DEG C/min, soaking time 0.5h, pressure 50MPa.
After measured, sample manufactured in the present embodiment compared with standard uranium dioxide pellet radial thermal conductivity promoted 300% with
Upper (800-1200 DEG C), axial thermal conductivity improve 30% or more (800-1200 DEG C).
Embodiment 5
Present embodiment discloses the preparation of the enhanced uranium dioxide pellet of radial thermal conductivity of the invention, specifically:
After step 1. nickel wire net ultrasound is cleaned, it is cut into the disk with sintering mold diameter matches on slicer, is burning
It ties in mold, is by volume 70:30, is stacked alternately uranium dioxide raw material powder and nickel wire net disk, makes wire mesh radially
Stratiform is uniformly distributed, and wherein the mesh number of nickel wire net is 300 mesh, and the diameter of nickel wire is 10 μm；
It is nothing that the mixture of the uranium dioxide raw material powder and tungsten silk screen that stack through step 1 is sintered mode by step 2.
Calm the anger atmosphere sintering densification, wherein applying charge plasma is pre-sintered, after pre-sintered body is sintered under atmospheric condition；Its
In, pre-sintering atmosphere is vacuum, and pre-sintering temperature is 600 DEG C, soaking time 2min, pressure 50MPa, and vacuum degree is
20Pa；Sintering atmosphere without pressure atmosphere sintering is H2, temperature is 1850 DEG C, heating rate 10 DEG C/min, soaking time 2h, hydrogen
Throughput is 0.2L/min.And rear demoulding, dimensioned processing.
After measured, sample manufactured in the present embodiment compared with standard uranium dioxide pellet radial thermal conductivity promoted 500% with
Upper (800-1200 DEG C), axial thermal conductivity improve 50% or more (800-1200 DEG C).
Embodiment 6
Present embodiment discloses the preparations of the enhanced uranium dioxide pellet of radial thermal conductivity of the invention, with embodiment
5 compare, and no to press condition when atmosphere sintering different, remaining is all the same.Condition when the present embodiment is without pressure atmosphere sintering are as follows: application
Discharge plasma be pre-sintered, after pre-sintered body is sintered under atmospheric condition；Wherein, pre-sintering atmosphere is vacuum, is pre-sintered
Temperature is 900 DEG C, soaking time 10min, pressure 30MPa, vacuum degree 10-1Pa；Sintering atmosphere without pressure atmosphere sintering
For H2, temperature is 1650 DEG C, heating rate 1 DEG C/min, soaking time 10h, hydrogen flowing quantity 2L/min.
After measured, sample manufactured in the present embodiment compared with standard uranium dioxide pellet radial thermal conductivity promoted 500% with
Upper (800-1200 DEG C), axial thermal conductivity improve 50% or more (800-1200 DEG C).
The invention is not limited to specific embodiments above-mentioned.The present invention, which expands to, any in the present specification to be disclosed
New feature or any new combination, and disclose any new method or process the step of or any new combination.
Claims (10)
1. a kind of enhanced uranium dioxide pellet of radial thermal conductivity, which is characterized in that by uranium dioxide raw material powder and metal
70-98:2-30 is made silk screen by volume, and in the fuel pellet, radially stratiform is uniformly distributed in titanium dioxide to wire mesh
In uranium pellet.
2. the enhanced uranium dioxide pellet of a kind of radial thermal conductivity according to claim 1, which is characterized in that by two
Urania raw material powder is sintered after stacking with wire mesh stratiform.
3. the enhanced uranium dioxide pellet of a kind of radial thermal conductivity according to claim 1 or 2, which is characterized in that
Any one of the wire mesh type in molybdenum filament net, tungsten silk screen, nickel wire net.
4. the enhanced uranium dioxide pellet of a kind of radial thermal conductivity according to claim 3, which is characterized in that described
The mesh number of wire mesh is 10-300 mesh, and the wire diameter of the wire mesh is 10-380 μm.
5. a kind of preparation of the enhanced uranium dioxide pellet of radial thermal conductivity according to any one of claims 1-4
Method, which is characterized in that wire mesh is cut on slicer first with the matched disk of mould diameter, in sintering mold
According to the ratio, successively alternately addition uranium dioxide raw material powder and wire mesh, enhanced by being sintered at high temperature into radial thermal conductivity
Uranium dioxide pellet.
6. a kind of preparation method of the enhanced uranium dioxide pellet of radial thermal conductivity according to claim 5, special
Sign is, specifically includes the following steps:
Step 1. uranium dioxide raw material powder and wire mesh are stacked alternately
After wire mesh ultrasound is cleaned, the disk with sintering mold diameter matches is cut on slicer, in sintering mold
In, according to a certain ratio, it is stacked alternately uranium dioxide raw material powder and wire mesh disk, making wire mesh, radially stratiform is uniformly divided
Cloth；
The densification of step 2. high temperature sintering
The mixture that step 1 is stacked to the uranium dioxide raw material powder and wire mesh that finish is sintered densification, then demoulds,
?.
7. a kind of preparation method of the enhanced uranium dioxide pellet of radial thermal conductivity according to claim 6, special
Sign is, in the step 2, sintering processing be electric discharge plasmon sintering, hot pressed sintering, without pressure atmosphere sintering it is any one
Kind.
8. a kind of preparation method of the enhanced uranium dioxide pellet of radial thermal conductivity according to claim 7, special
Sign is, in the step 2, when sintering processing is electric discharge plasmon sintering, and specific sintering condition are as follows: sintering atmosphere is true
Sky, sintering temperature are 1000 DEG C -1500 DEG C, and heating rate is 50-300 DEG C/min, soaking time 2-30min, pressure 30-
80MPa, vacuum degree 10-1-20Pa。
9. a kind of preparation method of the enhanced uranium dioxide pellet of radial thermal conductivity according to claim 7, special
Sign is, when sintering processing is hot pressed sintering, specific sintering condition are as follows: and sintering atmosphere is argon gas, sintering temperature is 1200 DEG C-
1600 DEG C, heating rate is 5-50 DEG C/min, soaking time 0.5-4h, pressure 50-80MPa.
10. a kind of preparation method of the enhanced uranium dioxide pellet of radial thermal conductivity according to claim 7, special
Sign is, when sintering processing is without pressure atmosphere sintering, specific sintering condition are as follows: and first applying charge plasma is pre-sintered forming,
Again by pre-sintered body without atmosphere sintering densification of calming the anger；Wherein, pre-sintering atmosphere is vacuum, and pre-sintering temperature is 600-900 DEG C, is protected
The warm time is 2-10min, pressure 30-50MPa, vacuum degree 10-1-20Pa；Sintering atmosphere without pressure atmosphere sintering is H2, burn
Junction temperature is 1650-1850 DEG C, 1-10 DEG C of heating rate/min, soaking time 2-10h, hydrogen flowing quantity 0.2-2L/min.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113409963A (en) * | 2021-06-17 | 2021-09-17 | 中国核动力研究设计院 | Fuel rod and fuel assembly for overcoming pellet cladding mechanical interaction |
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| CN102649328A (en) * | 2012-05-14 | 2012-08-29 | 陈建伟 | Metal wire mesh reinforced heat-conducting plastic with high strength, high corrosion resistance and high heat conductivity |
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