CN105575447B - Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition - Google Patents
Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition Download PDFInfo
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- CN105575447B CN105575447B CN201610089358.5A CN201610089358A CN105575447B CN 105575447 B CN105575447 B CN 105575447B CN 201610089358 A CN201610089358 A CN 201610089358A CN 105575447 B CN105575447 B CN 105575447B
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- nuclear fuels
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- cladding nuclear
- pipe
- fuel cladding
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- 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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- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to an experimental device for assessing nuclear fuel cladding pipe performance under the simulated LOCA working condition. The experimental device comprises a mold cavity, balancing devices and a heating device; the mold cavity comprises vacuum cavities and a quenching cavity which are formed through dividing of sealing parts, a through hole is formed in each sealing part, the nuclear fuel cladding pipe is arranged in the through holes in a sealed mode, the two ends of the nuclear fuel cladding pipe are located in the vacuum cavities, the middle of the nuclear fuel cladding pipe is located in the quenching cavity, the quenching cavity comprises a cavity body and a metal corrugated pipe which is integrally arranged with the cavity body, and the quenching cavity can telescope along with free telescoping of the metal corrugated pipe; each balancing device comprises a pulley assembly and a counterweight weight; the heating device comprises a heating rod stretching into the nuclear fuel cladding pipe and an isolating pipe arranged at the periphery of the heating rod in a sleeving mode. According to the experimental device, the fuel cladding pipe can freely expand and telescope in the pipe heating process, the expansion bending phenomenon in the nuclear fuel cladding pipe heating process can be prevented from occurring due to the fact that the metal corrugated pipe is arranged in a free telescoping mode, and therefore the nuclear fuel cladding pipe performance can be accurately assessed.
Description
Technical field
The present invention relates to the experimental provision under a kind of simulation LOCA operating modes to cladding nuclear fuels pipe performance evaluation, more particularly to
A kind of experiment when simulation LOCA operating modes occur for evaluating cladding nuclear fuels performance in high-temperature vapor is aoxidized and quenched is filled
Put.
Background technology
Cladding nuclear fuels pipe is the layer protective layer outside fuel ball, and it protects fuel pellet not invaded by coolant
Erosion, it is to avoid fission product leaks in fuel, makes coolant from pollution, while can also keep the geometry of fuel element and make
Have enough rigidity and mechanical strength.Involucrum is the most harsh vitals of operating mode in reactor.Its working condition is wrapped for which
Hold nuclear fuel, bear High Temperature High Pressure and strong neutron irradiation, by fission gas pressure, burn into fuel swelling, inhale hydrogen embrittlement etc.
Harm, by coolant pressure, washes away, vibrates and corrodes and hydrogen embrittlement etc. is threatened.Therefore the performance of cladding nuclear fuels pipe is very heavy
Will, it is related to the safety of nuclear power station.
LOCA is accident very serious during reactor operation, and the accident occurs what is mainly caused by following reason：
The pipeline breaking of piece pipeline of primary Ioops or aid system；The valve of primary Ioops or aid system pipeline is opened accidentally or can not close
Close；The axle envelope or valve rod of the pump of conveying primary Ioops medium is revealed.When LOCA accident occurs, reactor loses primary Ioops coolant, heap
Core cooling is bad to cause clad temperature quickly to raise so as to which oxidation rate is accelerated, and causes cladding materials oxide thickness quickly to increase
Plus.In the later stage of LOCA, substantial amounts of water piii reactor active region, cladding materials temperature rapid decrease is made, it is believed that the mistake
Journey is the quenching to cladding materials, if cladding materials does not have enough impact resistances that rupture will occur, causes radioactivity
Fission product discharges, and the safety of reactor is constituted a threat to.
If obtaining behavior of the fuel canning material under LOCA operating modes with in-reactor experiment, not only technical sophistication, and consume
Take larger.Therefore, substantially using out-of-pile analogue technique and device evaluating the performance of fuel kernel fuel tube.Mesh
Before, the device for being simulated involucrum behavior under LOCA operating modes is less, most of in order to the mode of external heat is taken beneficial to temperature control,
Which is inconsistent with LOCA real working conditions, it is impossible to enough performances for more really reacting material under operating mode.Meanwhile, a part
Experimental provision is unable to free wxpansion in heating process center fuel tube, therefore fuel kernel fuel tube was entirely being tested
Certain external force is born in journey, this will produce certain impact to result of the test, it is impossible to the verity of accurate reaction material
Can, some experimental provision heating process center fuel tube can free wxpansion, but its exist expansion after become
Curved problem, it is impossible to which cladding tubes are freely stretched, the more accurately performance of test material.
The content of the invention
The technical problem to be solved is to overcome the deficiencies in the prior art, there is provided right under a kind of simulation LOCA operating modes
The experimental provision of cladding nuclear fuels pipe performance evaluation.
To solve above-mentioned technical problem, the present invention is adopted the following technical scheme that：
A kind of experimental provision under simulation LOCA operating modes to cladding nuclear fuels pipe performance evaluation, which includes：
For accommodating the die cavity of cladding nuclear fuels pipe, the die cavity include by sealing member be separated to form positioned at upper and lower ends
Vacuum chamber and the quenching chamber positioned at middle part, be provided with through hole on sealing member, the cladding nuclear fuels seal of tube is arranged in through-holes, and
Two ends be located at vacuum chamber, it is middle be located at quenching intracavity, quenching chamber include the cavity consistent with cladding nuclear fuels pipe bearing of trend, with
And with the metal bellowss being wholely set along cavity direction and cavity, wherein quenching chamber can be with the freedom of metal bellowss
Stretch and stretch, the entrance and exit of the entrance and exit with vapor and quenching liquid on cavity；
Bascule, which is used to balance the stress for applying metal bellowss so that metal bellowss are in and freely stretch
State, which includes the pulley assembly and weights positioned at the top of upper end vacuum chamber；
Heater, it include stretching into heating rod in cladding nuclear fuels pipe, be set in heating rod periphery be used for will plus
The isolated tube that the inner wall insulation of hot pin and cladding nuclear fuels pipe separates, the material of the isolated tube is quartz, boron carbide or ceramics.
Preferably, metal bellowss are located at the top of cavity, and the upper end of metal bellowss is tightly connected with sealing member.
Reduce to the stress produced by metal bellowss as far as possible, be easy to the design of bascule.
Further, bascule has two groups, and is located at the left and right sides at the top of the vacuum chamber of upper end respectively.So that vacuum
The stress in chamber is relatively uniform, it is ensured that freely stretching for metal bellowss, effectively further prevents the curved of cladding nuclear fuels pipe
It is bent.
One of the invention is embodied as and preferred aspect, and pulley assembly is included above the vacuum chamber of upper end
Fixed pulley, the pull rope being wrapped on fixed pulley, wherein pull rope one end be connected positioned at upper end vacuum chamber, the other end
Portion is connected with weights.Simple structure, and it is convenient to carry out.
It is of the invention it is another be embodied as and preferred aspect, the cladding nuclear fuels are stretched out at heating rod both ends respectively
Pipe, heater also include the electrode for being separately positioned on heating rod both ends.
Preferably, electrode is tungsten electrode.
Preferably, heater also include be separately positioned on vacuum intracavity, for electrode is mutually insulated with the vacuum chamber
Insulating barrier.
Preferably, thermometric window is additionally provided with cavity.It is easy to actual manipulation.
Additionally, experimental provision also includes gas shield device, the gas shield device includes protective gas memorizer, difference
The pipeline and control valve of protective gas are passed through to vacuum intracavity.
Preferably, sealing member is water cooled seal part, and cladding nuclear fuels pipe sealed by carbon seal ring with through hole.
Due to the enforcement of above technical scheme, the present invention is had the advantage that compared with prior art：
The device design of the present invention is ingenious, rationally so that fuel tube in pipe thermal histories can with free wxpansion and
It is flexible, while by the setting of freely stretching of metal bellowss, additionally it is possible to solve cladding nuclear fuels pipe and change is expanded in heating process
Curved problem such that it is able to accurately evaluate cladding nuclear fuels pipe performance, simple structure is easy to operate, and low cost.
Description of the drawings
The present invention will be further described in detail with specific embodiment below in conjunction with the accompanying drawings.
Fig. 1 is the structural representation of the experimental provision according to the present invention；
Wherein：1st, cladding nuclear fuels pipe（Zirconium alloy cladding pipe）；2nd, die cavity；3rd, sealing member（Water cooled seal part）；4th, vacuum
Chamber；5th, quench chamber；50th, cavity；51st, metal bellowss；6th, bascule；60th, pulley assembly；600th, fixed pulley；601st, draw
Rope；61st, weights；7th, heater；70th, heating rod；71st, isolated tube；72nd, electrode；8th, gas shield device；80th, protect
The pipeline of gas；The entrance of a, vapor；The outlet of b, vapor；The entrance of c, quenching liquid；The outlet of d, quenching liquid；E, thermometric
Window.
Specific embodiment
As shown in figure 1, the present embodiment provides the experimental provision under simulation LOCA operating modes to cladding nuclear fuels pipe performance evaluation,
Which mainly includes：For accommodating the die cavity 2 of cladding nuclear fuels pipe 1, the die cavity 2 is included by being located at that sealing member 3 is separated to form
The vacuum chamber 4 of upper and lower ends and the quenching chamber 5 positioned at middle part, are provided with through hole on sealing member 3, and the sealing of cladding nuclear fuels pipe 1 sets
Put in through-holes, and two ends are located at vacuum chamber 4, middle being located at and quench in chamber 5, quenching chamber 5 includes extending with cladding nuclear fuels pipe 1
The consistent cavity 50 in direction, and with the metal bellowss 51 being wholely set along 50 direction of cavity and cavity 50, wherein quenching
Chamber 5 can be stretched with freely stretching for metal bellowss 51, on cavity 50 with vapor entrance a and outlet b and
The entrance c and outlet d of quenching liquid；
Bascule 6, which is used to balance the stress for applying metal bellowss 51 so that metal bellowss 51 are in freely
Retracted position, which includes pulley assembly 60 positioned at the top of upper end vacuum chamber 4, and weights 61；
Heater 7, which includes stretching into heating rod 70 in cladding nuclear fuels pipe 1, the periphery that is set in heating rod 70 is used
In the isolated tube 71 for separating the inner wall insulation of heating rod 70 and cladding nuclear fuels pipe 1, the material of the isolated tube 71 is quartz, carbon
Change boron or ceramics.
Specifically, sealing member 3 is water cooled seal part, and the through hole on cladding nuclear fuels pipe 1 and sealing member 3 is by carbon seal ring
Sealed.
Metal bellowss 51 are located at the top of cavity 50, and the upper end of metal bellowss 51 is tightly connected with sealing member 3.
Reduce to the stress produced by metal bellowss 51 as far as possible, be easy to the design of bascule 6.
The entrance a and outlet b of vapor is respectively positioned at the both sides of cavity 50, and the outlet b of vapor is located at vapor
The top of entrance a；The entrance c and outlet d of quenching liquid is located at positioned at the homonymy of the cavity 50, and the outlet d of quenching liquid respectively
The top of the entrance c of quenching liquid.
Further, the outlet d of the quenching liquid and outlet b of vapor is located at homonymy, and the outlet b of vapor is steamed positioned at water
The top of the outlet b of gas.
Further, thermometric window e is additionally provided with cavity 50.It is easy to actual manipulation.Thermometric window e is located at vapor
The homonymy of entrance a, and positioned at the middle and upper part of cavity 50.
In this example, bascule 6 has two groups, and is located at the left and right sides at the top of upper end vacuum chamber 4 respectively.So that vacuum
The stress in chamber 4 is relatively uniform, it is ensured that freely stretching for metal bellowss 51, effectively further prevents cladding nuclear fuels pipe 1
Bending.
Further, pulley assembly 60 includes fixed pulley 600 above upper end vacuum chamber 4, is wrapped in fixed pulley
Pull rope 601 on 600, wherein 601 one end of pull rope be connected positioned at upper end vacuum chamber 4, the other end and counterweight
Counterweight 61 is connected.Simple structure, and it is convenient to carry out.
In this example, cladding nuclear fuels pipe 1 is stretched out at 70 both ends of heating rod respectively, and heater 7 includes being separately positioned on and adds
The electrode 72 at hot 70 both ends；It is separately positioned on the 3 interior, insulating barrier for electrode 72 is mutually insulated with vacuum chamber 4 of vacuum chamber（Figure
In do not show）.
Further, electrode is tungsten electrode.Extend the service life of itself.
Meanwhile, in this example, the both ends of isolated tube 71 are also emerged the both ends of cladding nuclear fuels pipe 1, by 71 He of isolated tube
The setting of heating rod 70, leaves surplus, consequently facilitating cladding nuclear fuels pipe 1 is flexible, also further prevents cladding nuclear fuels pipe 1
It is deformed or bent.
Additionally, experimental provision also includes gas shield device 8, the gas shield device 8 includes protective gas memorizer（Figure
In do not show）, respectively be passed through into vacuum chamber 4 protective gas pipeline 80, and control valve（Do not show in figure）.
In this example, the total length in the chamber that quenches is 330mm, and the wherein length of cavity is 300mm, and the length of metal bellowss is
30mm。
In sum, fuel tube of the invention with free wxpansion and can stretch in pipe thermal histories, while by gold
The setting of freely stretching of category corrugated tube, prevents cladding nuclear fuels pipe from the phenomenon that bent is expanded in heating process and occurs, so as to more
Accurately the performance of test material, significant to improving nuclear safety level.
Above the present invention is described in detail, its object is to allow the personage for being familiar with this art to will appreciate that this
The content of invention is simultaneously carried out, and can not be limited the scope of the invention with this, all spirit institutes of the invention
The equivalence changes of work or modification, should all cover within the scope of the present invention.
Claims (8)
1. the experimental provision under a kind of simulation LOCA operating modes to cladding nuclear fuels pipe performance evaluation, it is characterised in that：Including：
For accommodating the die cavity of cladding nuclear fuels pipe, described die cavity include by sealing member be separated to form positioned at upper and lower ends
Vacuum chamber and the quenching chamber positioned at middle part, through hole is provided with the sealing member, the cladding nuclear fuels seal of tube is arranged on
In the through hole, and two ends be located at the vacuum chamber, it is middle be located at described quenching intracavity, described quenching chamber include with it is described
The consistent cavity of cladding nuclear fuels pipe bearing of trend and with the metal being wholely set with the cavity along the cavity direction
Corrugated tube, wherein described quenching chamber can be stretched with freely the stretching for metal bellowss, has on described cavity
There is an entrance and exit of the entrance and exit and quenching liquid of vapor, described sealing member is water cooled seal part, described core
Fuel tube is sealed by carbon seal ring with the through hole；
Bascule, which is used to balance the stress for applying the metal bellowss so that described metal bellowss are in certainly
By retracted position, which includes the pulley assembly and weights positioned at the top of vacuum chamber described in upper end；
Heater, which includes stretching into heating rod in the cladding nuclear fuels pipe, the periphery that is set in the heating rod is used for
The isolated tube that the inner wall insulation of the heating rod and the cladding nuclear fuels pipe is separated, the material of the isolated tube is quartz,
Boron carbide or ceramics；
Thermometric window, which is arranged on described cavity.
2. the experimental provision under simulation LOCA operating modes according to claim 1 to cladding nuclear fuels pipe performance evaluation, which is special
Levy and be：Described metal bellowss are located at the top of the cavity, and the upper end of the metal bellowss and the sealing
Part is tightly connected.
3. the experimental provision under simulation LOCA operating modes according to claim 1 to cladding nuclear fuels pipe performance evaluation, which is special
Levy and be：Described bascule has two groups, and is located at the left and right sides at the top of vacuum chamber described in upper end respectively.
4. the experimental provision under the simulation LOCA operating modes according to claim 1 or 3 to cladding nuclear fuels pipe performance evaluation, its
It is characterised by：Described pulley assembly includes fixed pulley above vacuum chamber described in upper end, is wrapped in the fixed pulley
On pull rope, wherein described pull rope one end be connected positioned at vacuum chamber described in upper end, the other end with it is described
Weights are connected.
5. the experimental provision under simulation LOCA operating modes according to claim 1 to cladding nuclear fuels pipe performance evaluation, which is special
Levy and be：The cladding nuclear fuels pipe is stretched out at described heating rod both ends respectively, and described heater also includes connecting respectively
It is connected on the electrode at the heating rod both ends.
6. the experimental provision under simulation LOCA operating modes according to claim 5 to cladding nuclear fuels pipe performance evaluation, which is special
Levy and be：Described electrode is tungsten electrode.
7. the experimental provision under simulation LOCA operating modes according to claim 5 to cladding nuclear fuels pipe performance evaluation, which is special
Levy and be：Described heater also includes being separately positioned on the vacuum intracavity, for by the electrode and the vacuum chamber
The insulating barrier for mutually insulating.
8. the experimental provision under simulation LOCA operating modes according to claim 1 to cladding nuclear fuels pipe performance evaluation, which is special
Levy and be：Described experimental provision also includes gas shield device, and the gas shield device includes protective gas memorizer, difference
The pipeline and control valve of protective gas are passed through to the vacuum intracavity.
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| CN201610089358.5A CN105575447B (en) | 2016-02-17 | 2016-02-17 | Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition |
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| CN201610089358.5A CN105575447B (en) | 2016-02-17 | 2016-02-17 | Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition |
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Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN107389467B (en) * | 2017-06-23 | 2022-09-27 | 中国核电工程有限公司 | Device for simulating spent fuel cladding high-temperature mechanical performance test |
| CN110957053B (en) * | 2019-12-18 | 2021-10-08 | 苏州热工研究院有限公司 | Test system for simulating high-fuel-consumption working condition of fuel cladding |
| CN112378764A (en) * | 2020-09-29 | 2021-02-19 | 国家电投集团科学技术研究院有限公司 | Explosion testing device and method for nuclear fuel cladding pipe |
| CN112382421B (en) * | 2020-10-09 | 2022-06-21 | 国家电投集团科学技术研究院有限公司 | Test device for simulating nuclear reactor fuel rod |
| CN113421668B (en) * | 2021-05-19 | 2024-03-22 | 中国原子能科学研究院 | Experimental system for simulating water loss accident |
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| US4326122A (en) * | 1980-07-14 | 1982-04-20 | The United States Of America As Represented By The United States Department Of Energy | Electric heater for nuclear fuel rod simulators |
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