CN108754407A - A kind of uranium surface UC1-xNxIt is dissolved preparation, its product and application - Google Patents
A kind of uranium surface UC1-xNxIt is dissolved preparation, its product and application Download PDFInfo
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- CN108754407A CN108754407A CN201810650261.6A CN201810650261A CN108754407A CN 108754407 A CN108754407 A CN 108754407A CN 201810650261 A CN201810650261 A CN 201810650261A CN 108754407 A CN108754407 A CN 108754407A
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- C—CHEMISTRY; METALLURGY
- C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
- C23C—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; SURFACE TREATMENT OF METALLIC MATERIAL BY DIFFUSION INTO THE SURFACE, BY CHEMICAL CONVERSION OR SUBSTITUTION; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL
- C23C8/00—Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals
- C23C8/06—Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals using gases
- C23C8/28—Solid state diffusion of only non-metal elements into metallic material surfaces; Chemical surface treatment of metallic material by reaction of the surface with a reactive gas, leaving reaction products of surface material in the coating, e.g. conversion coatings, passivation of metals using gases more than one element being applied in one step
- C23C8/30—Carbo-nitriding
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Abstract
The invention discloses a kind of uranium surface UC1‑xNxIt is dissolved preparation, its product and application, it is therefore intended that it is longer there are the working time when solving to prepare UC-UN solid solution by solid-state diffusion under the conditions of 1200 DEG C as raw material using UC, UN, and it is difficult to avoid that metallic uranium, U2C3、UC2The problem of object phase.The present invention is under the premise of controlling vacuum chamber impurity, in CH4（Other carbon containing air sources, such as C2H4、C2H2 ）And N2In mixed atmosphere, using metallic uranium as matrix, UC is prepared in uranium surface using pulse laser1‑xNxSolid solution.The uranium surface UC of the present invention1‑xNxIn solid solution, x values（The ratio of C and N）It can be by changing hydrocarbon air source and N2Partial pressure is modulated, N2When intrinsic standoff ratio is in 0.7~1 section, modified layer will embody uranium matrix more excellent protecting effect.Uranium surface UC in the present invention1‑xNxSolid solution object is mutually single, can have higher application value and preferable application prospect as the raw material of candidate nuclear fuel UC-UN material system performance studies.
Description
Technical field
The present invention relates to metal protection field, especially active metal surface anticorrosion field, specially a kind of uranium surface
UC1-xNxIt is dissolved preparation, its product and application.Solid solution object prepared by the present invention is mutually single, and property is stablized, Neng Gouyou
Effect promotes the corrosion resistance of uranium material surface.
Background technology
Metallic uranium is widely used general as a kind of important material in nuclear engineering field.But uranium material character is active,
It is easy to and surrounding medium (such as O2、H2O、CO2Deng) chemistry, electrochemical action occurs, and corrode, and then influence uranium material
Physics, chemistry and nuclearity energy.Therefore, the resistance to corrosion for improving uranium metal is of great significance.
By to uranium material surface carry out nitrogen treatment preparation with UN (Yongbin Zhang etc., Pulsed laser
Nitriding of uranium.Journal of Nuclear Materials, 397 (2010) 31-35) based on protection change
Property layer, preferable help is provided for metallic uranium material surface corrosion protection.
According to solid solution correlation theory, UC1-xNxSolid solution thermodynamic stability is related to x values, and x values exist certain
Range makes UC1-xNxThermal stability is superior to UC and UN, and may be embodied in the variation of certain performances.Therefore, it prepares
The mutually single UC of object1-xNxSolid solution is research UC1-xNxBasis as uranium protection of materials protective layer.
J.WILLIAMS et al. is prepared for UC-UN by solid-state diffusion under the conditions of 1200 DEG C as raw material using UC, UN and consolidates
Solution (J.WILLIAMS, R.A.J.SAMBELL, JOURNAL OF THE LESS-COMMON METALS, 1 (1959) 217-
226), the preparation method working time was up to even 100 hours or more tens of hours, and was difficult to avoid that metallic uranium, U2C3、UC2Object
The appearance of phase.
T.NOMURA et al. utilizes UC+N2Or the reaction of UN+ graphite prepare UC-UN solid solution (T.NOMURA,
M.KATSURA and T.SAN0, ON THE FORMATION OF UC-UN SOLID SOLUTIONS, JOURNAL OF
NUCLEAR MATERIALS 43 (1972) 234-244.), the used equipment of this method is complicated, and preparation time is long, is removed in product
UC-UN solid solution, equally exists U2C3、UC2, the non-targeted object phase such as graphite, and UC-UN solid solutions prepared by different experiments group
Body impurity phase differs greatly, so that studying UC as raw material1-xNxPerformance the phenomenon that there are larger differences.
For this purpose, the present invention provides a kind of new preparation method, to solve the above problems.
Invention content
The goal of the invention of the present invention is：Under the conditions of 1200 DEG C pass through solid-state diffusion system for using UC, UN as raw material
It is longer there are the working time when standby UC-UN solid solution, and it is difficult to avoid that metallic uranium, U2C3、UC2The problem of object phase, carries
For a kind of uranium surface UC1-xNxIt is dissolved preparation, its product and application.The present invention provides a kind of uranium surface UC1-xNxSolid solution
Preparation method, and uranium material surface corrosion protective layers are prepared based on this method.The present invention under the premise of controlling vacuum chamber impurity,
In CH4(other carbon containing air sources, such as C2H4、C2H2) and N2In mixed atmosphere, using metallic uranium as matrix, existed using pulse laser
Uranium surface prepares UC1-xNxSolid solution.The uranium surface UC of the present invention1-xNxIn solid solution, x values (ratio of C and N) can pass through change
Hydrocarbon air source and N2Partial pressure is modulated, N2When intrinsic standoff ratio is in 0.7~1 section, modified layer will embody uranium matrix
More excellent protecting effect.Uranium surface UC in the present invention1-xNxSolid solution object is mutually single, can be used as candidate nuclear fuel UC-UN materials
The raw material of system performance study have higher application value and preferable application prospect.
To achieve the goals above, the present invention adopts the following technical scheme that：
A kind of uranium surface UC1-xNxIt is dissolved preparation, using metallic uranium as matrix, in containing C, N mixed atmosphere, is utilized
Pulse laser prepares UC in uranium surface1-xNxSolid solution.
Include the following steps：
(1) environment is controlled：Uranium surface oxide layer is first removed, then surface clean is carried out to metallic uranium, it then will be after cleaning
Metallic uranium is put into vacuum chamber, and will be evacuated to 20Pa or less in vacuum chamber；
(2) uranium surface UC1-xNxIt is prepared by solid solution：First use high-purity N2Vacuum chamber and pipeline are cleaned, then to step 1
Carbon source gas and N are filled in vacuum chamber2Then mixed gas scans metal uranium surface by laser comprehensively；Scanning knot
Vacuum chamber gas is discharged Shu Hou, takes out sample, completes uranium surface UC1-xNxThe preparation of solid solution.
In the step 1, the oxide layer of metal uranium surface is removed using mechanical grinding.
In the step 1, be respectively adopted alcohol, acetone, compressed nitrogen to remove surface oxide layer metallic uranium carry out table
Face is cleaned.
In the step 1, vacuum chamber is evacuated to 20Pa or less using mechanical pump.
In the step 2, carbon source gas is CH4、C2H4、C2H2In it is one or more.
In the step 2, after the end of scan, the indoor gas of vacuum is evacuated to exhaust emission system.
In the step 2, the air pressure for the mixed gas being filled with is higher than 1atm.
In the step 2, the indoor total gas pressure of vacuum is higher than 2atm.
In the step 2, when being scanned to metal uranium surface by laser comprehensively, single pulse laser energy density
For 4~25J/cm2。
Using the product prepared by preceding method.
The UC1-xNxIn solid solution, UC1-xNxSolid solution object is mutually single, other than a small amount of free metal uranium, is free of other
The carbide of uranium or the nitride of uranium.
The UC1-xNxThe thickness of solid solution is 100nm~2 μm.
The uranium surface UC1-xNxIn solid solution, ranging from the 0.01~0.99 of x.
Aforementioned uranium surface UC1-xNxSolid solution is answered as uranium surface corrosion protection body or nuclear fuel UC-UN solid solution systems
With.
For foregoing problems, the present invention provides a kind of uranium surface UC1-xNxIt is dissolved preparation, its product and application.This
Invention, using metallic uranium as matrix, high-purity containing under C, N mixed gas atmosphere, using in pulse laser and metallic uranium surface action
The rapid melting showed and quickly solidification nonequilibrium process feature, while utilizing carbide, the nitrogen of UC, UN and other uranium
The lucky moderate characteristic of the dissolving of C and N element in liquid metal uranium under the difference and high temperature of compound fusing point, in uranium surface
Preparing has certain thickness UC1-xNxSolid solution.UC prepared by the present invention1-xNxIn solid solution, in addition to containing part free metal
Uranium (can control, make free metal uranium content less than 5%), be free of the carbide or nitride of other uranium.
Further, the operating procedure of this method is as follows：
(1) environment is controlled：Uranium surface oxide layer is removed first, then alcohol, acetone, compressed nitrogen is used to aoxidize removal respectively
The metallic uranium of layer carries out surface clean, then the metallic uranium after cleaning is put into vacuum chamber, then will be evacuated in vacuum chamber
20Pa or less；
(2) uranium surface UC1-xNxIt is prepared by solid solution：First use high-purity N2Vacuum chamber and pipeline are cleaned, then to step 1
Vacuum chamber is filled with the CH of certain intrinsic standoff ratio4(or other carbon containing air sources, such as C2H4、C2H2) and N2Mixed gas sets laser
Device running parameter, and metal uranium surface is scanned comprehensively, the end of scan, vacuum chamber gas is evacuated to special exhaust gas discharge system
System takes out sample, just completes uranium surface UC1-xNxThe preparation of solid solution.
In this method, the mode that mechanical grinding may be used removes the oxide layer of metal uranium surface, will using mechanical pump
Vacuum chamber is evacuated to 20Pa or less.
Wherein, in step 2, in the case of the sources C, the sources N abundance, by adjusting laser energy density (single pulse laser
Energy density：4~25J/cm2) realize UC1-xNxIt is dissolved the control of body thickness, thickness adjustable extent is 100nm~2 μm；And pass through
Change carbon source gas and N2Partial pressure, can change UC1-xNxThe ratio of C and N in solid solution, as long as theoretically inflation system is clever enough
It is quick, CH4And N2Intrinsic standoff ratio can arbitrarily adjust, total gas pressure need to be higher than 1atm.Further, N2Intrinsic standoff ratio is in 0.7~1 section
When, UC1-xNxSolid solution has excellent anticorrosive protecting effect to uranium matrix.Meanwhile by adjusting laser energy density (i.e.
Adjust laser pulse sweep speed, laser beam overlap ratio) control UC1-xNxThe thickness of solid solution, it is (total in the case of air source abundance
Air pressure is more than 2atm), laser energy density is higher, and pool depth is bigger, and modified layer thickness is also bigger, and UC is effectively ensured1-xNx
Solid solution modified layer uniform component.
Meanwhile the present invention is in the preparation, although molten bath upper plasma temperature is up to thousands of Kelvins, substrate temperature
Basic the temperature remains within the normal range state, influences the size of precision workpiece minimum, disclosure satisfy that the process requirements of precision workpiece, have compared with
Good application prospect.
With utilize UC+N2Or the reaction of UN+ graphite prepares UC1-xNxSolid solution phase ratio, the present invention is by adjusting carbon source gas (such as
CH4、C2H4、C2H2), N2Intrinsic standoff ratio, to UC1-xNxC, N element ratio in solid solution are modulated, and preparation process is extremely
Simplify, working efficiency is improved, and requires effectively to reduce to equipment complexity, prepared UC1-xNxSolid solution is in addition to containing portion
Divide free metal uranium (can control, make free metal uranium content less than 5%), be free of the carbide or nitride of other uranium.This
Invent UC1-xNxIt is easy to be dissolved preparation, work efficiency is high, and impurity and other object phase controllabilitys are strong, has higher application
Value and preferable application prospect.
Meanwhile in the present invention, with UC1-xNxIt is dissolved preparation and manufactures metallic uranium surface corrosion protective layer, have preferable
Corrosion protection effect.In product prepared by the present invention, UC1-xNxSolid solution object is mutually single, in addition to a small amount of free metal uranium it
Outside, the carbide or nitride for being free of other uranium (are free of U2C3、UC2、U2N3、UN2Equal objects phase)；Uranium surface UC1-xNxSolid solution
Thickness can control, generally 100nm~2 μm；Uranium surface UC1-xNxSolid solution x values can regulate and control, the UC of preparation1-xNxSolid solution
(C+N)/U is~0.9 in modifies layer.
In conclusion the present invention is in carbon containing air source (such as CH4、C2H4、C2H2) and N2In mixed atmosphere, it is with metallic uranium
Matrix, it is special using the rapid melting showed in pulse laser and metallic uranium surface action and quickly solidification nonequilibrium process
Sign, and above molten bath UC is prepared in uranium surface the phenomenon that formation high pressure plasma1-xNxSolid solution, which can
As uranium material surface corrosion protection layer.Present invention process is easy, and work efficiency is high, and impurity and other object phase controllabilitys are strong, institute
The UC of preparation1-xNxPhysical efficiency is dissolved as metallic uranium surface corrosion protective layer, the corrosion for effectively solving metallic uranium material surface is asked
Topic.Meanwhile UC prepared by the present invention1-xNxSolid solution object is mutually single, serves not only as uranium surface corrosion protection body with good anti-
Effect is protected, can also provide excellent basic raw material for the performance study of next-generation nuclear fuel UC-UN solid solution systems.
Description of the drawings
Examples of the present invention will be described by way of reference to the accompanying drawings, wherein：
Fig. 1 is the UC that the embodiment of the present invention 1 is prepared in uranium surface1-xNxSolid solution XRD diffracting spectrums.
Fig. 2 is the UC that the embodiment of the present invention 1 is prepared in uranium surface1-xNxSolid solution (CH4And N2Intrinsic standoff ratio 1:2) AES at
Divide analysis chart.
Fig. 3 is the UC that the embodiment of the present invention 1 is prepared in uranium surface1-xNxSolid solution (CH4And N2Intrinsic standoff ratio 1:1) AES at
Divide analysis chart.
Fig. 4 is the UC that the embodiment of the present invention 1 is prepared in uranium surface1-xNxSolid solution (CH4And N2Intrinsic standoff ratio 2:1) AES at
Divide analysis chart.
Fig. 5 is that the embodiment of the present invention 2 prepares UC in uranium surface1-xNxSolid solution surface topography SEM observation charts.
Fig. 6 is that the embodiment of the present invention 2 prepares UC in uranium surface1-xNxSolid solution sample electrode curve graph.
It is marked in figure：
Specific implementation mode
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
UC is prepared in metal uranium surface1-xNxSolid solution, UC1-xNxSolid solution has NaCl structures, can be carbon containing by adjusting
(in the present embodiment, carbon containing air source uses CH to air source4, other such as C2H4、C2H2), N2Intrinsic standoff ratio modulates UC1-xNxIn solid solution
C, N element ratio.
In the present embodiment, uranium surface UC1-xNxSolid solution preparation parameter is as shown in table 1.
1 uranium surface UC of table1-xNxSolid solution preparation parameter
(1) preparation process is as follows.
First, uranium surface oxide layer is removed, then respectively with alcohol, acetone, compressed nitrogen to removing the metallic uranium of removing oxide layer
Surface clean is carried out, then the metallic uranium after cleaning is put into vacuum chamber.Then, 20Pa or less will be evacuated in vacuum chamber.
Secondly, high-purity N is first used2Vacuum chamber and pipeline are cleaned, then pour CH to vacuum chamber4And N2Intrinsic standoff ratio 1:2
CH4(other carbon containing air sources, such as C2H4、C2H2) and N2Mixed gas, guarantee total gas pressure are 3atm, and laser is set by table 1
Device running parameter, and metal uranium surface is scanned comprehensively.After the end of scan, vacuum chamber gas is evacuated to special exhaust gas and is discharged
System takes out sample, completes uranium surface UC1-xNxThe preparation of solid solution.
It repeats the above steps, adjusts CH4And N2Intrinsic standoff ratio is respectively 1:1 and 2:1, laser work parameter and above-mentioned technique phase
Together.
In Fig. 1,1:2,1:1,2:1 respectively represents CH in preparation process4And N2Intrinsic standoff ratio；In Fig. 2,1:2 represent preparation work
CH in skill4And N2Intrinsic standoff ratio；In Fig. 3,1:1 represents CH in preparation process4And N2Intrinsic standoff ratio；In Fig. 4,2:1 represents in preparation process
CH4And N2Intrinsic standoff ratio.
As shown in Figure 1, in CH4(other carbon containing air sources, such as C2H4、C2H2) and N2In mixed atmosphere, it is with metallic uranium
Matrix, the UC prepared in uranium surface using pulse laser1-xNxSolid solution crystals structure belongs to NaCl types, can pass through CH4And N2
Intrinsic standoff ratio modulates UC1-xNxC, N element ratio, UC in solid solution1-xNxLattice constant is located atWith
Between lattice constant, with CH in mixed gas when embodiment total gas pressure is constant substantially4Partial pressure increases, UC1-xNxLattice constant gradually becomes
UC lattice constants are bordering on (with N in mixed gas when total gas pressure is constant2Partial pressure increases, UC1-xNxLattice constant gradually level off to UN crystalline substance
Lattice constant).Obtained uranium surface UC is analyzed in conjunction with AES in Fig. 2, Fig. 3, Fig. 41-xNxSolid-solution elements distribution results, it is believed that can
With by adjusting CH4(other carbon containing air sources, such as C2H4、C2H2), N2Intrinsic standoff ratio modulates UC1-xNxC, N element in solid solution
Ratio.
Uranium surface UC prepared by the present embodiment1-xNxSolid solution acts not only as uranium surface corrosion protection body, can also be
The performance study of next-generation nuclear fuel UC-UN solid solution systems provides excellent basic raw material.
Embodiment 2
With UC prepared by metal uranium surface1-xNxSolid solution has good protection as uranium material surface corrosion protective layers
Effect, dependence test are as follows.
(1) it presses process in embodiment 1 and prepares UC in uranium surface1-xNxSolid solution obtains modified sample, and in solubility
To carry out electro-chemical test in the NaCl solution of 0.02mol/L, sample validity test area is 1cm2, obtain as shown in FIG. 6
Electric polarization curve figure.In Fig. 6,1:2,1:1,2:1 respectively represents the CH in preparation process4And N2Intrinsic standoff ratio.
The result shows that with UC is not prepared on surface1-xNxThe depleted uranium sample of solid solution is compared, and surface is prepared for UC1-xNxSolid solution
Body Sample equilibration corrosion electric current density declines, and balance corrosion potential rises, particularly with CH in mixed gas4And N2Intrinsic standoff ratio is
1:Sample prepared by 2 preparation process, balance corrosion electric current density decline close to 2 orders of magnitude, and balance corrosion potential rises
300mV。
(2) UC is prepared for surface1-xNxSolid solution sample and not surface prepare UC1-xNxThe depleted uranium sample of solid solution into
Row accelerated corrosion is examined, and is 90 DEG C in temperature, is examined 300 hours in aqueous closed container, surface is prepared for UC1-xNxSolid solution
Sample surfaces color varies slightly, and whole region keeps complete, does not occur picking phenomenon, illustrates UC1-xNxSolid solution is as metal
Uranium material surface corrosion protective layers have good protection effect.And UC is not prepared on surface1-xNxThe depleted uranium sample table of solid solution
Face color blacks, and serious picking phenomenon occurs.
Surface is prepared for UC1-xNxWhy solid solution has embodied preferable protection effect, is on the one hand due to prepared
UC1-xNxIn solid solution, when C and N element are in suitable proportional region, UC1-xNxGibbsFree energy smaller, system are more stable；
On the other hand, as shown in figure 5, uranium surface is prepared for UC1-xNxThe uranium material surface pattern crackle existence of solid solution is changed
It is kind, predict N2Partial pressure UC prepared between 0.7~11-xNxThere are superior corrosion protection effects for solid solution.In Fig. 5,
1:2,2:1 respectively represents CH in preparation process4And N2Intrinsic standoff ratio.
The invention is not limited in specific implementation modes 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 uranium surface UC1-xNxIt is dissolved preparation, which is characterized in that using metallic uranium as matrix, containing C, N mixed atmosphere
In, using pulse laser UC is prepared in uranium surface1-xNxSolid solution.
2. uranium surface UC according to claim 11-xNxIt is dissolved preparation, which is characterized in that include the following steps：
（1）Control environment：Uranium surface oxide layer is first removed, then surface clean is carried out to metallic uranium, then by the metal after cleaning
Uranium is put into vacuum chamber, and 20 Pa or less will be evacuated in vacuum chamber；
（2）Uranium surface UC1-xNxIt is prepared by solid solution：First use high-purity N2Vacuum chamber and pipeline are cleaned, then to the vacuum of step 1
Interior is filled with carbon source gas and N2Then mixed gas scans metal uranium surface by laser comprehensively；After the end of scan,
Vacuum chamber gas is discharged, sample is taken out, completes uranium surface UC1-xNxThe preparation of solid solution.
3. uranium surface UC according to claim 21-xNxIt is dissolved preparation, which is characterized in that in the step 2, carbon source
Gas is CH4、C2H4、C2H2In it is one or more.
4. uranium surface UC according to claim 21-xNxIt is dissolved preparation, which is characterized in that in the step 2, be filled with
Mixed gas air pressure be higher than 1atm.
5. according to any one of the claim 2 ~ 4 uranium surface UC1-xNxIt is dissolved preparation, which is characterized in that the step 2
In, the indoor total gas pressure of vacuum is higher than 2atm.
6. according to any one of the claim 2 ~ 5 uranium surface UC1-xNxIt is dissolved preparation, which is characterized in that the step 2
In, when being scanned to metal uranium surface by laser comprehensively, single pulse laser energy density is 4~25 J/cm2。
7. using the product prepared by any one of claim 1 ~ 6 the method.
8. product according to claim 7, which is characterized in that the UC1-xNxIn solid solution, UC1-xNxSolid solution object is mutually single
One, other than a small amount of free metal uranium, the nitride of carbide or uranium without other uranium.
9. according to claim 7 or the product, which is characterized in that the uranium surface UC1-xNxIn solid solution, x is ranging from
0.01~0.99。
10. according to any one of the claim 7 ~ 9 uranium surface UC1-xNxSolid solution is as uranium surface corrosion protection body or nuclear fuel
The application of UC-UN solid solution systems.
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| CN108754407A true CN108754407A (en) | 2018-11-06 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109518013A (en) * | 2018-11-30 | 2019-03-26 | 中国工程物理研究院材料研究所 | A kind of method of pulse laser remelting purified metal uranium surface, its device and its purification layer of preparation |
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|---|---|---|---|---|
| US3306957A (en) * | 1964-06-12 | 1967-02-28 | Atomic Energy Authority Uk | Production of nuclear fuel materials |
| CN105063547A (en) * | 2015-07-24 | 2015-11-18 | 中国工程物理研究院材料研究所 | Method and device for preparing uranium surface anti-corrosion protecting layer through atmospheric laser passivation |
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2018
- 2018-06-22 CN CN201810650261.6A patent/CN108754407B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3306957A (en) * | 1964-06-12 | 1967-02-28 | Atomic Energy Authority Uk | Production of nuclear fuel materials |
| CN105063547A (en) * | 2015-07-24 | 2015-11-18 | 中国工程物理研究院材料研究所 | Method and device for preparing uranium surface anti-corrosion protecting layer through atmospheric laser passivation |
Non-Patent Citations (2)
| Title |
|---|
| M.UGAJIN: "stabilization of uranium carbonitrides (N≤1wt%) by tungsten addition", 《JOURNAL OF NUCLEAR MATERIALS》 * |
| 陈志磊等: "脉冲激光氮化改性对金属铀表面形貌的影响", 《物理化学学报》 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109518013A (en) * | 2018-11-30 | 2019-03-26 | 中国工程物理研究院材料研究所 | A kind of method of pulse laser remelting purified metal uranium surface, its device and its purification layer of preparation |
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