CN107686364A - Cladding nuclear fuels pipe and preparation method thereof - Google Patents
Cladding nuclear fuels pipe and preparation method thereof Download PDFInfo
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- CN107686364A CN107686364A CN201710552537.2A CN201710552537A CN107686364A CN 107686364 A CN107686364 A CN 107686364A CN 201710552537 A CN201710552537 A CN 201710552537A CN 107686364 A CN107686364 A CN 107686364A
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- C04B35/515—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on non-oxide ceramics
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- C04B41/00—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
- C04B41/45—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements
- C04B41/50—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials
- C04B41/5053—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials non-oxide ceramics
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- G21C3/02—Fuel elements
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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Abstract
The invention discloses a kind of cladding nuclear fuels pipe and preparation method thereof, its tube wall is followed successively by the first FRCMC layer, the second FRCMC layer and ceramic layer from inside to outside, and the first FRCMC layer is by the first fiber preform and is filled in intrapore first ceramic matrix of the first fiber preform and forms;Second FRCMC layer is by the second fiber preform and is filled in intrapore second ceramic matrix of the second fiber preform and forms;First fiber preform is wound into after pipe by the fiber cloth for being soaked with resin glue and formed through solidifying carbonization, and the second fiber preform is woven by the multiple fibre beam for being soaked with resin glue and formed through solidifying carbonization after being wound on the circumference of fiber cloth rolling tube.Ceramic layer is prepared by chemical vapor deposition method.The forming method can batch molding long and thin FRCMC tubular element and length is unrestricted, technological feasibility is strong, equipment requirement is low.
Description
Technical field
The invention belongs to nuclear fuel protection materials field, more particularly to a kind of cladding nuclear fuels pipe and preparation method thereof.
Background technology
The survival and development of the mankind be unable to do without the energy, and with the development of social productive forces, the mankind are rapid to the demand of the energy
Increase.Nuclear energy is as a kind of cleaning, the efficient energy, it is considered to be the final main path for solving mankind energy problem.According to
The method of operation of nuclear reactor, nuclear energy can be divided into fusion reactor and fission reactor.For now, fusion reactor
Still in conceptual design and experimental verification stage, and fission-type reactor successfully achieves extensive use.In fission-type reactor, nuclear fuel
Urania is contained in cladding tubes, and nuclear reaction occurs in cladding tubes for nuclear fuel so as to discharge heat.It is on the outside of cladding tubes
Light-water cooling medium, light-water cooling medium are finally converted by circulating the heat taken away the nuclear reaction in cladding tubes and discharged
Into electric energy.
Cladding materials is operated under high temperature, high pressure and radiation parameter, and operating condition is very harsh, it is desirable to which material has small
Neutron absorption cross-section, high thermal conductivity factor, intensity height, good toughness, corrosion-resistant, Flouride-resistani acid phesphatase, heat endurance are good etc..Nuclear energy it is advanced
Property, security reliability and economy and the performance of cladding materials used are closely related.Zircaloy is the current second generation and three generations's core
The wide variety of cladding materials of reactor, but because zircaloy hardness is relatively low, easy to wear, long-term use can also be anti-because inhaling hydrogen
Should and it is brittle, can be undergone phase transition more than 450 DEG C, more than 1093 DEG C can and water the reaction of zirconium water occurs.Particularly major accident work
The zirconium water reaction occurred under condition can produce substantial amounts of hydrogen, and detonation or blast, March 12 in 2011 occur under given conditions
The accident of the day nuclear power station of Fukushima, Japan first generation has caused the seawater of cooling effect to be introduced into reactor core mainly due to tsunami, and zirconium closes
Golden fuel tube occurs zirconium water with water at high temperature and reacted, and produces substantial amounts of hydrogen, and trigger hydrogen quick-fried.Nuclear Safety is nuclear energy
The first element of development, people wish to find always a kind of cladding nuclear fuels pipe that can be more safer than zircaloy, and SiC/SiC
Composite cladding tubes are one of possible selections, and related research turns into the focus of investigation of materials in recent years.
Relative to Zirconium alloy material, SiC/SiC composites are applied to the advantage that cladding materials has following aspect:(1)
Temperature tolerance is good, can be used for a long time under 800 DEG C of environment in nuclear reactor environment as cladding materials, can bear 1200 DEG C in short term
High temperature, improve the security of reactor;(2)Slowing down absorptance is good, and parasitic thermal neutron absorbs cross section to be reduced compared with zircaloy
More than 15%, using same uranium 235 fuel(Enrichment 5%)When, fuel burn-up can be brought up to by 60000 MWD/tU
70000 MWD/tU;(3)Hardness is high, can effectively reduce due to abrasion caused by fragment in cooling agent and grid, extend fuel
Rod service life and reactor normal working hours.Just because of having these features, SiC/SiC composite fuel cans exist
Nuclear power system field has broad application prospects.
In fission-type reactor, the size requirement of cladding tubes is:Length 3.8m, 8~10mm of external diameter, wall thickness≤1.0mm.If using
SiC/SiC composites substitute existing zircaloy and are used for cladding nuclear fuels pipe, it is necessary first to which solution is exactly that SiC/SiC is answered
The shaping of condensation material cladding tubes and preparation problem.Because SiC/SiC composite hardnesses are high, plasticity is poor, it is impossible to as zircaloy
The SiC/SiC composite tubulose components of such size are prepared using drawing process like that, and the SiC/SiC of so length is answered
Condensation material tubular element also can not be by SiC/SiC compound walking spa- cial system machine-shapings.As can be seen here, prepare and disclosure satisfy that size will
The SiC/SiC composite cladding nuclear fuels pipe difficulty asked is larger.
The content of the invention
The technical problem to be solved in the present invention is overcome the deficiencies in the prior art, there is provided a kind of elongated fibers strengthen ceramic base
Composite material base cladding nuclear fuels pipe, correspondingly provide a kind of elongated fibers enhancing ceramic matric composite tubular element that is suitable to and criticize
Amount shaping, the preparation method for the cladding nuclear fuels pipe that length is unrestricted, technological feasibility is strong, equipment requirement is low.
In order to solve the above technical problems, the present invention uses following technical scheme:
A kind of cladding nuclear fuels pipe, the tube wall of the cladding nuclear fuels pipe are followed successively by the first ceramic layer, the first fiber from inside to outside
Strengthen ceramic matric composite layer, the second FRCMC layer and the second ceramic layer, first fiber increases
Strong ceramic matric composite layer is by the first fiber preform and is filled in intrapore first ceramic matrix of the first fiber preform
Composition;The second FRCMC layer is by the second fiber preform and is filled in the second fibre preforms body opening
The second ceramic matrix composition in gap;First fiber preform is wound into Guan Houjing by the fiber cloth for being soaked with resin glue and consolidated
Change-carbonization is formed, and second fiber preform is woven by the multiple fibre beam for being soaked with epoxide-resin glue and is wound in fiber cloth
Formed after on the circumference of rolling tube through solidification-carbonization.
For now, the knitting skill relative maturity of fiber, the carbon of tubulose can be obtained using the technique of three-dimensional establishment
SiClx fiber preform.Therefore, in theory three-dimensional establishment can be used to be molded tubular silicon carbide fiber preform, then using conjunction
Suitable fine and close mode, such as precursor infiltration and pyrolysis technique or chemical vapor infiltration technique, increased with preparing the fiber of elongated tubular product
Strong ceramic base composite material member.However, applicant's previous experiments grope to find:This process routes are answered in preparation SiC/SiC
Two be present in terms of condensation material cladding nuclear fuels pipe:First, in the case of no core mold support, with current weaver
Skill is difficult to ensure that preferable apparent size precision, such as smoothness of inner wall, inside and outside wall circularity, and the tubular silicon carbide after establishment is fine
It is relatively low to tie up prefabricated component intensity, is easily bent or produces along its length local bumps in later stage densification process, can influence
The geometry and dimensional accuracy of elongated tubular;Second, in the case where there is core mold support, because densification process temperature is higher,
Without the releasing agent can near this temperature also with demoulding effect, thus it is larger to be stripped difficulty;In addition, densification process
The silicon carbide ceramics matrix of middle generation is also easily filled between composite material tube and core, and plays certain connection function,
Thus the bond strength of silicon carbide fibre prefabricated component and core can increase along with the densification of fiber preform, and the two is total to
It is larger that same-action ultimately results in disengaging difficulty between composite material tube and core.As can be seen here, three-dimensional basketry approach is being made
It is apparently seemingly feasible in theory in terms of the long tubulose SiC/SiC composites of detailed information, but it is larger to put into practice difficulty.
The innovative point of the present invention is:
The present invention is by means of cylindrical mandrel, by the fiber cloth by resin glue is soaked with wound on the cylindrical mandrel of coating releasing agent
Into pipe on excircle, then by the bundle weave for being soaked with resin glue and it is wound on fiber cloth rolling tube excircle, due to operation
Temperature is low, and releasing agent can be always maintained at the effect of original, can be by the way of appropriate easily after epoxy resin cure
Fiber beam tube is taken off from mandrel surface.Further, since the outer layer multiple fibre that the fiber cloth of coiling and molding and braiding are wound is all
Resin glue is soaked with, resin glue has preferable intensity after hardening, and the size of cladding nuclear fuels pipe is can guarantee that under core auxiliary
Precision;And fiber cloth has preferable apparent size precision compared with braided part, can be further ensured that in gained cladding nuclear fuels pipe
Wall smoothness and circularity.By suitable carbonization technique after the demoulding, the residual carbon generated after resin glue carbonization is between fibre bundle
Connection, has certain combination and supporting role to fiber preform overall structure, can guarantee that in subsequent densification process
The geometry and dimensional accuracy of the SiC/SiC composite cladding nuclear fuels pipes of gained.
In addition, applicant in practice, it has been found that only with the fiber cloth for being soaked with resin glue be wound into pipe solidify afterwards be stripped, with
Fibre bundle separation, phenomenon at random occur in carbonisation afterwards, cladding nuclear fuels pipe can not be molded.And the present invention by
After weaving one layer of fibre bundle of winding outside fiber cloth rolling tube again, because fiber interfascicular is entwined mutually in winding process, it can play tight
Gu the effect of internal layer winding layer, thus in carbonisation without fibre bundle separation, it is at random phenomena such as, can successfully be molded nuclear fuel bag
Package base.Due to the winding and fastening internal layer effect of outer layer fiber beam, in addition connection and support of the residual carbon between fibre bundle
Effect so that the integral forming structure is not in that length direction bending or localized indentation are shown especially in subsequent densification process
As farthest ensure that the geometry and dimensional accuracy of the SiC/SiC composite cladding nuclear fuels pipes of gained.
Above-mentioned cladding nuclear fuels pipe, it is preferred that the braid angle of the fibre bundle is 30~60 °.Angular region is woven herein
It is interior, can guarantee that fastening effect of the outer layer fiber beam to internal layer fiber cloth coiling and molding part, and can ensure simultaneously cladding tubes ring with
The intensity of axial direction.In practical operation, angle of weave can suitably be adjusted according to performance requirement within the range.
Above-mentioned cladding nuclear fuels pipe, it is preferred that the resin glue includes epoxide-resin glue or phenolic resin glue.
Above-mentioned cladding nuclear fuels pipe, it is preferred that the thickness of the first FRCMC layer is 300
~800 μm;The thickness of the second FRCMC layer is 300~500 μm, and the thickness of the ceramic layer is
100~300 μm.
Above-mentioned cladding nuclear fuels pipe, it is preferred that the fiber of the fiber cloth is carbon fiber or silicon carbide fibre;The fibre
The fiber for tieing up beam is carbon fiber or silicon carbide fibre;First ceramic matrix is silicon carbide ceramics;Second ceramic matrix
For silicon carbide ceramics.
Above-mentioned cladding nuclear fuels pipe, it is preferred that the ceramic layer is silicon carbide layer.
The inventive concept total as one, the present invention also provide a kind of preparation method of above-mentioned cladding nuclear fuels pipe, wrap
Include following steps:
(1)By the fiber cloth for being soaked with resin glue on the excircle of cylindrical mandrel, the first fiber preform intermediate is formed;
By the bundle weave for being soaked with resin glue and it is wound on the excircle of the first fiber preform intermediate, it is pre- forms the second fiber
Product intermediate;Curing and demolding, carbonization, to form the first fiber preform and the second fiber preform, obtain nuclear fuel bag
Package base;
(2)Using ceramic precursor impregnating cracking technology, make step(1)The cladding nuclear fuels pipe densification of gained, forms the
One FRCMC layer and the second FRCMC layer, obtain cladding nuclear fuels intervalve
Body;
(3)Using chemical vapor deposition method, in step(2)The outside deposition ceramics of body among the cladding nuclear fuels of gained
Layer, obtains cladding nuclear fuels pipe.
The preparation method of above-mentioned cladding nuclear fuels pipe, it is preferred that the step(1)In, the temperature of the carbonization is 500
~800 DEG C, the time is 0.5~2h.
The preparation method of above-mentioned cladding nuclear fuels pipe, it is preferred that the step(2)In, the ceramic precursor dipping
It is 3~10 times to crack number of repetition, and ceramic precursor is low molecule liquid Polycarbosilane, 900 DEG C~1200 DEG C of cracking temperature, is protected
The warm time is 1h~3h.
The preparation method of above-mentioned cladding nuclear fuels pipe, it is preferred that the source of the gas of the chemical vapor deposition is trichloromethyl
Silane gas, carrier gas are hydrogen, and diluent gas is argon gas, and temperature is 800 DEG C~1200 DEG C;Time is 10h~40h, hydrogen stream
It is 100mL/min~300mL/min to measure as 100mL/min~250mL/min, argon flow amount.
Compared with prior art, the advantage of the invention is that:
1st, cladding nuclear fuels pipe of the present invention, after being wound into pipe using the fiber cloth for being soaked with resin glue, then epoxide-resin glue will be soaked with
The braiding of multiple fibre beam and be wound on the circumference of fiber cloth rolling tube, can be successfully stripped after solidification, then i.e. formation after being carbonized
The cladding nuclear fuels pipe being made up of the first fiber preform and the second fiber preform, cladding nuclear fuels pipe is in subsequent cause
Geometry and dimensional accuracy are unaffected in densification.The wall thickness of the cladding nuclear fuels pipe of the present invention can be as thin as 800 μm, outside
Footpath can be as small as 1mm, and length is not limited then by technique.
2nd, cladding nuclear fuels pipe of the present invention, the first FRCMC layer and the second fiber reinforced ceramic-base
Composite layer material is both preferably SiC/SiC composites, it is ensured that SiC/SiC composite cladding nuclear fuels pipes have
Higher intensity and toughness, to prevent that it is calamitous broken that SiC/SiC composite cladding nuclear fuels pipes from occurring in use
It is bad.Ceramic layer is preferably pure SiC ceramic layer, primarily serves and improves SiC/SiC composite cladding nuclear fuels pipe sealings
Effect, while its higher chemical purity can also ensure that SiC/SiC composite cladding nuclear fuels pipe has higher irradiation
Stability.
3rd, the preparation method of cladding nuclear fuels pipe of the present invention, in terms of SiC/SiC composite cladding nuclear fuels pipes are prepared
With stronger technological feasibility, and the length of prepared SiC/SiC composite cladding nuclear fuels pipes is not by preparation work
The limitation of skill.Less to equipment requirement, industrialization production feasibility is big, easily realizes mass production.
Brief description of the drawings
Fig. 1 is the cross section structure schematic diagram of the cladding nuclear fuels pipe of the embodiment of the present invention 1.
Fig. 2 is the pictorial diagram of 70cm prepared by the embodiment of the present invention 1 cladding nuclear fuels pipe.
Fig. 3 is the pictorial diagram of 70cm prepared by the embodiment of the present invention 1 cladding nuclear fuels pipe proximal port.
Fig. 4 is the pictorial diagram of 120cm prepared by the embodiment of the present invention 2 cladding nuclear fuels pipe.
Embodiment
Below in conjunction with Figure of description and specific preferred embodiment, the invention will be further described, but not therefore and
Limit the scope of the invention.
Embodiment 1:
A kind of cladding nuclear fuels pipe, as illustrated in fig. 1 and 2, internal diameter 9mm, length 70cm, tube wall gross thickness are 800 μm.It is managed
Wall internal layer is the first SiC/SiC composite layers 1, and intermediate layer is the 2nd SiC/SiC composite layers 2, and outer layer is single-phase SiC
Ceramic layer 3, wherein, the first SiC/SiC composite layers 1 by the first SiC fiber preforms and be filled in its intrapore first
SiC ceramic matrix forms, and the 2nd SiC/SiC composite layers 2 are by the 2nd SiC fiber preforms and to be filled in its intrapore
Second SiC ceramic matrix forms.After the SiC fiber cloths for being soaked with epoxide-resin glue are wound into pipe, then epoxide-resin glue will be soaked with
Multi beam SiC fibre bundles weave and be wound on the circumference of fiber cloth rolling tube with 45 ° of braid angles, it is cured-carbonization after i.e. point
Xing Cheng not the first SiC fiber preforms and the 2nd SiC fiber preforms.
In the present embodiment, the thickness of internal layer is 500 μm;The thickness in intermediate layer is 300 μm, the single-phase SiC ceramic layer of outer layer
Thickness be 200 μm.
The preparation method of the cladding nuclear fuels pipe of above-mentioned the present embodiment, comprises the following steps:
(1)Prepare cladding nuclear fuels pipe
(1.1)High-temperature mold lubricant is coated with the excircle of the stainless steel core die of pole shape(Mirror Glaze 8), then will be soaked with
The SiC fiber cloths of epoxide-resin glue are on the excircle of the stainless steel core die of pole shape, the size of the stainless steel core die of pole shape
For 9 mm of φ × 100cm, the first SiC fiber preform intermediates are formed, thickness is 500 μm or so;Epoxide-resin glue will be soaked with
SiC fibre bundles weave and be wound on the excircle of the first SiC fiber preform intermediates with 45 ° of braid angles, formed second
SiC fiber preform intermediates, thickness are 300 μm or so.Solidify with the stainless steel core die of pole shape, mould circle is removed after solidification
Bar-shaped stainless steel core die, obtain cladding nuclear fuels pipe intermediate.
Epoxy resin cure temperature is relatively low, can still have the demoulding of action and efficacy near epoxy resin cure temperature
Agent is more, thus the demoulding is relatively easy in this way.
(1.2)Cladding nuclear fuels pipe intermediate, which is placed in heat-treatment furnace, to be carbonized, and temperature is 600 DEG C, time 1h,
The epoxide-resin glue in the first SiC fiber preforms intermediate and the 2nd SiC fiber preform intermediates is set to be carbonized, to form
One fiber preform and the second fiber preform, obtain cladding nuclear fuels pipe.
Applicant was attempted after being coated with identical releasing agent on the excircle of the stainless steel core die of pole shape of identical size,
Only by the SiC fiber cloths for being soaked with epoxide-resin glue of same thickness on the excircle of the stainless steel core die of pole shape, then it is solid
Change, the demoulding, then carbonization.But practice have shown that, the SiC/SiC composite material tubes of no outer layer winding are in carbonisation, fiber
Fibre bundle in cloth rolling tube is easily separated, at random, can not be molded cladding nuclear fuels pipe.
And after the present invention by weaving one layer of fibre bundle of winding again outside fiber cloth winding layer, due to canoe fibre bundle
Between entwine mutually, can play a part of fastening internal layer winding layer, in carbonisation without fibre bundle separation, it is at random phenomena such as.
(2)Ceramic precursor infiltration pyrolysis
Using ceramic precursor impregnating cracking technology, used ceramic precursor is low molecule liquid Polycarbosilane(LPVCS),
Precursor infiltration and pyrolysis number of repetition is 8 times, and cracking every time is warming up to 1100 DEG C by 2.5 DEG C/min of heating rate, insulation
Time is 1h, makes step(1)The cladding nuclear fuels pipe densification of gained, it is compound to form the first SiC fiber reinforcement SiC ceramic bases
Material layer(That is the first SiC/SiC composite layers)With the 2nd SiC fiber reinforcement SiC ceramic based composites layers(I.e. second
SiC/SiC composite layers), obtain body among cladding nuclear fuels.
(3)Chemical vapor deposition
Using chemical vapor deposition method, source of the gas is trichloromethyl silane gas, and carrier gas is hydrogen, and hydrogen flow is 100ml/
Min, diluent gas are argon gas, and argon flow amount 150ml/min, temperature is 1000 DEG C, time 24h, in step(2)Gained
The outside deposition ceramic layer of body, forms single-phase SiC ceramic layer among cladding nuclear fuels.
The pictorial diagram of the cladding nuclear fuels pipe of 70cm prepared by the present embodiment is as shown in Figures 2 and 3, it can be seen that the core fires
Expect the uniform wall thickness of cladding tubes, surface is smooth, and does not occur the phenomenon of local buckling alongst.
Embodiment 2:
A kind of cladding nuclear fuels pipe, substantially the same manner as Example 1, it only difference is that, internal diameter is 9 mm, length 120
cm。
The preparation method of the cladding nuclear fuels pipe of above-mentioned the present embodiment is substantially the same manner as Example 1, and it only difference is that,
The size of the stainless steel core die of pole shape is the cm of mm of φ 9 × 150.
The pictorial diagram of the cladding nuclear fuels pipe of 120 cm prepared by the present embodiment is as shown in figure 4, as seen from the figure, the core fires
Expect the uniform wall thickness of cladding tubes, surface is smooth, and does not occur local buckling phenomenon along its length.
Described above is only the preferred embodiment of the present invention, and protection scope of the present invention is not limited merely to above-mentioned implementation
Example.All technical schemes belonged under thinking of the present invention belong to protection scope of the present invention.It is noted that for the art
Those of ordinary skill for, improvements and modifications under the premise without departing from the principles of the invention, these improvements and modifications also should
It is considered as protection scope of the present invention.
Claims (10)
1. a kind of cladding nuclear fuels pipe, it is characterised in that it is fine that the tube wall of the cladding nuclear fuels pipe is followed successively by first from inside to outside
Dimension enhancing ceramic matric composite layer, the second FRCMC layer and ceramic layer, first fiber reinforcement
Ceramic matric composite layer is by the first fiber preform and is filled in the intrapore first ceramic matrix group of the first fiber preform
Into;The second FRCMC layer is by the second fiber preform and is filled in the second fiber preform hole
Interior the second ceramic matrix composition;First fiber preform is wound into after pipe through solidification by the fiber cloth for being soaked with resin glue-
Carbonization is formed, and second fiber preform is woven by the multiple fibre beam for being soaked with resin glue and is wound in fiber cloth rolling tube
Formed after on circumference through solidification-carbonization.
2. cladding nuclear fuels pipe according to claim 1, it is characterised in that the braid angle of the fibre bundle be 30 °~
60°。
3. cladding nuclear fuels pipe according to claim 1, it is characterised in that the resin glue includes epoxide-resin glue or phenol
Urea formaldehyde glue.
4. the cladding nuclear fuels pipe according to any one of claims 1 to 3, it is characterised in that the first fiber reinforcement pottery
The thickness of porcelain based composites layer is 300 μm~800 μm;The thickness of the second FRCMC layer is
300 μm~500 μm, the thickness of the ceramic layer is 100 μm~300 μm.
5. the cladding nuclear fuels pipe according to any one of claims 1 to 3, it is characterised in that the fiber of the fiber cloth is
Carbon fiber or silicon carbide fibre;The fiber of the fibre bundle is carbon fiber or silicon carbide fibre;First ceramic matrix is carbon
SiClx ceramics;Second ceramic matrix is silicon carbide ceramics.
6. the cladding nuclear fuels pipe according to any one of claims 1 to 3, it is characterised in that the ceramic layer is carborundum
Layer.
7. a kind of preparation method of cladding nuclear fuels pipe as described in any one of claim 1~6, comprises the following steps:
(1)By the fiber cloth for being soaked with resin glue on the excircle of cylindrical mandrel, the first fiber preform intermediate is formed;
By the bundle weave for being soaked with resin glue and it is wound on the excircle of the first fiber preform intermediate, it is pre- forms the second fiber
Product intermediate;Curing and demolding, carbonization, to form the first fiber preform and the second fiber preform, obtain nuclear fuel bag
Package base;
(2)Using ceramic precursor impregnating cracking technology, make step(1)The cladding nuclear fuels pipe densification of gained, forms the
One FRCMC layer and the second FRCMC layer, obtain cladding nuclear fuels intervalve
Body;
(3)Using chemical vapor deposition method, in step(2)The outside deposition ceramics of body among the cladding nuclear fuels of gained
Layer, obtains cladding nuclear fuels pipe.
8. the preparation method of cladding nuclear fuels pipe according to claim 7, it is characterised in that the step(1)In, it is described
The temperature of carbonization is 500 DEG C~800 DEG C, and the time is 0.5h~2h.
9. the preparation method of cladding nuclear fuels pipe according to claim 7, it is characterised in that the step(2)In, it is described
Ceramic precursor infiltration pyrolysis number of repetition is 3~10 times, and ceramic precursor is low molecule liquid Polycarbosilane, cracking temperature
900 DEG C~1200 DEG C, soaking time is 1h~3h.
10. the preparation method of cladding nuclear fuels pipe according to claim 7, it is characterised in that the chemical vapor deposition
Source of the gas be trichloromethyl silane gas, carrier gas is hydrogen, and diluent gas is argon gas, and temperature is 800 DEG C~1200 DEG C;Time is
10h~40h, hydrogen flow are 100mL/min~250mL/min, and argon flow amount is 100mL/min~300mL/min.
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Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2009210266A (en) * | 2008-02-29 | 2009-09-17 | Ibiden Co Ltd | Tubular body |
CN103818056A (en) * | 2013-12-27 | 2014-05-28 | 西北工业大学 | Multilayer structure of SiC/SiC (silicon carbide) composite cladding tube and preparation method thereof |
CN105405474A (en) * | 2015-11-02 | 2016-03-16 | 西北工业大学 | Structure and preparation method of nuclear fuel cladding tube with crack expansion resisting capability |
CN106631078A (en) * | 2016-12-07 | 2017-05-10 | 中核北方核燃料元件有限公司 | Preparation method of silicon carbide composite cladding pipe |
CN106904984A (en) * | 2017-02-27 | 2017-06-30 | 中国核动力研究设计院 | A kind of SiC short fiber composite materials and compound cladding tubes and preparation method thereof |
-
2017
- 2017-07-07 CN CN201710552537.2A patent/CN107686364B/en active Active
Patent Citations (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2009210266A (en) * | 2008-02-29 | 2009-09-17 | Ibiden Co Ltd | Tubular body |
CN103818056A (en) * | 2013-12-27 | 2014-05-28 | 西北工业大学 | Multilayer structure of SiC/SiC (silicon carbide) composite cladding tube and preparation method thereof |
CN105405474A (en) * | 2015-11-02 | 2016-03-16 | 西北工业大学 | Structure and preparation method of nuclear fuel cladding tube with crack expansion resisting capability |
CN106631078A (en) * | 2016-12-07 | 2017-05-10 | 中核北方核燃料元件有限公司 | Preparation method of silicon carbide composite cladding pipe |
CN106904984A (en) * | 2017-02-27 | 2017-06-30 | 中国核动力研究设计院 | A kind of SiC short fiber composite materials and compound cladding tubes and preparation method thereof |
Cited By (13)
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---|---|---|---|---|
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