CN105575446A - Experimental device for assessing performance of nuclear fuel cladding pipe under simulated LOCA working condition - Google Patents
Experimental device for assessing performance of nuclear fuel cladding pipe under simulated LOCA working condition Download PDFInfo
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- CN105575446A CN105575446A CN201610089338.8A CN201610089338A CN105575446A CN 105575446 A CN105575446 A CN 105575446A CN 201610089338 A CN201610089338 A CN 201610089338A CN 105575446 A CN105575446 A CN 105575446A
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- nuclear fuels
- cladding nuclear
- fuels pipe
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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 performance of a nuclear fuel cladding pipe under the simulated LOCA working condition. The experimental device comprises a mold cavity, an upper seal head, a lower seal head and a heating device; the mold cavity comprises vacuum cavities and a quenching cavity which are formed through dividing of sealing parts, the nuclear fuel cladding pipe at least comprises two sections, every two sections are connected with each other through a connecting part in a sealing mode, the two ends of each connecting part can be slidably arranged in the nuclear fuel cladding pipe, and an experimental pipe can freely telescope after being subjected to heating expansion; the heating device comprises a heating body, and the heating body is insulated from the inner wall of the nuclear fuel cladding pipe through the upper seal head, the lower seal head and the connecting parts. 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 every two adjacent nuclear fuel cladding pipe sections are movably arranged in a sealed mode through one connecting part, and therefore the performance of the nuclear fuel cladding pipe can be accurately assessed.
Description
Technical field
The present invention relates to a kind of experimental provision of simulating to cladding nuclear fuels pipe Performance Evaluation under LOCA operating mode, particularly a kind of experimental provision of simulating for assessment of cladding nuclear fuels performance in high-temperature vapor oxidation and quenching when LOCA operating mode occurs.
Background technology
Cladding nuclear fuels pipe is the layer protective layer outside fuel ball; its protection fuel pellet is not by the erosion of cooling medium; avoid fission product in fuel to leak, make cooling medium from pollution, the geometric configuration of fuel element can also be kept and make it enough rigidity and physical strength simultaneously.Involucrum is the vitals that in reactor, operating mode is the harshest.Its working condition is that it contains nuclear fuel, bears High Temperature High Pressure and strong neutron irradiation, by fission gas pressure, burn into fuel swelling, inhales hydrogen and causes the harm such as crisp, by coolant pressure, wash away, vibrate and corrode and the threat such as hydrogen embrittlement.Therefore the performance of cladding nuclear fuels pipe is very important, is related to the safety of nuclear power station.
LOCA is accident very serious in reactor operation process, and the generation of this accident causes primarily of following reason: the pipeline breaking of primary Ioops pipeline or backup system; The valve of primary Ioops or backup system pipeline is surprisingly opened and maybe can not be closed; Shaft seal or the valve rod of the pump of conveying primary Ioops medium are revealed.When LOCA accident occurs, reactor loses primary Ioops cooling medium, and the bad clad temperature that causes of Core cooling raises fast, and its oxidation rate is accelerated, and causes cladding materials oxide thickness to increase fast.In the later stage of LOCA, a large amount of water piii reactor active regions, cladding materials temperature is declined fast, can think that this process is the quenching to cladding materials, if cladding materials does not have enough impact resistances just can break, cause radioactive fission product to discharge, the safety of reactor is constituted a threat to.
If obtain the behavior of fuel canning material under LOCA operating mode with in-reactor experiment, not only technical sophistication, and expend larger.Therefore, out-of-pile analogue technique and device is substantially adopted to assess the performance of fuel kernel fuel tube.At present, it is less to carry out simulating the device of involucrum behavior under LOCA operating mode, and major part takes the mode of external heating in order to be beneficial to temperature control, which and LOCA real working condition inconsistent, the performance of material under operating mode can not be reacted more really.Simultaneously, part experimental provision can not free expansion at heating process center fuel tube, therefore fuel kernel fuel tube bears certain external force in whole process of the test, this produces certain impact by test findings, can accurately the actual performance of reaction material, some experimental provision can free expansion at heating process center fuel tube, but it becomes curved problem after being present in and expanding, cannot make cladding tubes can free-extension, the more accurately performance of test material.
Summary of the invention
Technical matters to be solved by this invention overcomes the deficiencies in the prior art, provides a kind of experimental provision of simulating to cladding nuclear fuels pipe Performance Evaluation under LOCA operating mode.
For solving the problems of the technologies described above, the present invention takes following technical scheme:
Simulate the experimental provision to cladding nuclear fuels pipe Performance Evaluation under LOCA operating mode, it comprises:
For holding the die cavity of cladding nuclear fuels pipe, this die cavity comprises the vacuum chamber being positioned at upper and lower two ends be separated to form by seal and the quenching chamber being positioned at middle part, seal is provided with through hole, cladding nuclear fuels pipe has two joints at least, be tightly connected mutually by web member between every two joints, and in more piece cladding nuclear fuels pipe, have a joint to be the experiment tube that size meets experiment demand, the both ends up and down of the more piece cladding nuclear fuels pipe after being connected are each passed through the through hole of corresponding end, and lay respectively in the vacuum chamber at upper and lower two ends, wherein the both ends of web member can be slidably arranged in cladding nuclear fuels pipe respectively, and connecting hole is offered on web member, experiment tube can free-extension after expanded by heating,
For sealing upper cover and the low head at the more piece cladding nuclear fuels pipe both ends after being connected, and on upper cover and low head, offer hole and lower opening respectively;
Heating arrangement, it comprises both ends and to penetrate respectively in hole and lower opening and the heater being arranged in connecting hole, and the inner wall insulation of heater and cladding nuclear fuels pipe separates by upper cover and low head and web member.
Preferably, web member, upper cover are identical with the material of low head, are the one in quartz, pottery or boron carbide.Wherein material boron carbide is best, is convenient to the machine-shaping of web member.
Preferably, the both ends of heater stretch out upper cover and low head respectively, and heating arrangement also comprises the electrode being connected to heater both ends.
Further, the material of electrode is copper.
Further, heating arrangement also comprises the insulation course be separately positioned in vacuum chamber, for electrode and vacuum chamber being insulated mutually.
Specifically implement and preferred aspect according to one of the present invention, the more piece cladding nuclear fuels pipe after being connected vertically is positioned at the middle part of die cavity, and is also provided with the back-up block for supporting described heater in the bottom of low head, and this back-up block is insulator.
Preferably, upper hole, lower opening, connecting hole be centrally located on same straight line, the middle part of cladding nuclear fuels pipe described in the more piece after described heater is positioned at and is connected.
Preferably, cladding nuclear fuels pipe has two joints, and experiment tube is positioned at below, and when carrying out Quenching Treatment to experiment tube, the liquid level being positioned at the hardening liquid in quenching chamber is in the below of web member.Prevent hardening liquid from infiltering the inside of experiment tube.
Specifically implement and preferred aspect according to of the present invention another, experimental provision also comprises gas shield device, and this gas shield device comprises blanket gas storer; Respectively to the pipeline passing into blanket gas in vacuum chamber, quenching chamber and cladding nuclear fuels pipe; And operation valve.
In addition, seal is water cooled seal part, and the both ends up and down of the more piece cladding nuclear fuels pipe after being connected are sealed by carbon seal ring with through hole respectively.
Chamber is also provided with thermometric window in quenching.Be convenient to actual manipulation.Meanwhile, quenching chamber is also provided with the steam entry pipeline and outlet conduit and the pipeline for passing into or discharge hardening liquid that are connected with chamber of quenching.
Due to the enforcement of above technical scheme, the present invention compared with prior art tool has the following advantages:
Apparatus design of the present invention is ingenious, rationally, make fuel tube can free expansion and flexible in pipe thermal histories, simultaneously by web member by movable for adjacent two fuel tubes and sealing setting, can also solve cladding nuclear fuels pipe to expand in heating process and become curved problem, thus can assess cladding nuclear fuels pipe performance accurately, structure is simple, easy to operate, and cost is low.
Accompanying drawing explanation
Below in conjunction with accompanying drawing and specific embodiment, the present invention will be further described in detail.
Fig. 1 is the structural representation according to experimental provision of the present invention;
Wherein: 1, cladding nuclear fuels pipe (zirconium alloy cladding pipe); 2, die cavity; 3, seal (water cooled seal part); 4, vacuum chamber; 5, quenching chamber; 6, web member; 7, upper cover; 8, low head; 9, heating arrangement; 90, heater; 91, electrode; 10, gas shield device; 100, the pipeline of blanket gas; 11, black O-ring seal; 12, thermometric window; 13, the inlet duct of water vapor; 14, the outlet conduit of water vapor; 15, the pipeline (pass into or discharge) of hardening liquid; 16, back-up block.
Embodiment
As shown in Figure 1, the present embodiment provides the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode, it mainly comprises: for holding the die cavity 2 of cladding nuclear fuels pipe 1, this die cavity 2 comprises the vacuum chamber 4 being positioned at upper and lower two ends and the quenching chamber 5 being positioned at middle part that are separated to form by seal 3, seal 3 is provided with through hole (not shown), cladding nuclear fuels pipe 1 has two joints at least, be tightly connected mutually by web member 6 between every two joints, and in more piece cladding nuclear fuels pipe 1, have a joint to be the experiment tube that size meets experiment demand, the both ends up and down of the more piece cladding nuclear fuels pipe 1 after being connected are each passed through the through hole of corresponding end, and lay respectively in the vacuum chamber 4 at upper and lower two ends, wherein the both ends of web member 6 can be slidably arranged in cladding nuclear fuels pipe 1 respectively, and connecting hole is offered on web member 6, experiment tube can free-extension after expanded by heating,
For sealing upper cover 7 and the low head 8 at more piece cladding nuclear fuels pipe 1 both ends after being connected, and on upper cover 7 and low head 8, offer hole and lower opening respectively;
Heating arrangement 9, it comprises both ends and to penetrate respectively in hole and lower opening and the heater 90 being arranged in connecting hole, and the inner wall insulation of heater 90 with cladding nuclear fuels pipe 1 separates by upper cover 7 and low head 8 and web member 6.
Web member 6, upper cover 7 are identical with the material of low head 8, are the one in quartz, pottery or boron carbide.Wherein material boron carbide is best, is convenient to the machine-shaping of web member 6.
Upper hole, lower opening, connecting hole be centrally located on same straight line, the middle part of the more piece cladding nuclear fuels pipe 1 after heater 90 is positioned at and is connected.
The both ends of heater 90 stretch out upper cover 7 and low head 8 respectively, and heating arrangement 9 also comprises the electrode 91 being connected to heater 90 both ends.In this example, the material of electrode 91 is copper.
Further, heating arrangement 9 also comprises the insulation course (not shown) be separately positioned in vacuum chamber 4, for being insulated with vacuum chamber 4 phase by electrode 91.
Further, experimental provision also comprises gas shield device 10, and this gas shield device 10 comprises blanket gas storer; Respectively to the pipeline 100 passing into blanket gas in vacuum chamber 4, quenching chamber 5 and cladding nuclear fuels pipe 1; And operation valve.
Seal 3 is water cooled seal part, and the both ends up and down of the more piece cladding nuclear fuels pipe 1 after being connected are sealed by carbon seal ring 11 with through hole respectively.
Chamber 5 is also provided with thermometric window 12 in quenching.Be convenient to actual manipulation.Meanwhile, quenching chamber 5 is also provided with the steam entry pipeline 13 and outlet conduit 14 and the pipeline 15 for passing into or discharge hardening liquid that are connected with chamber 5 of quenching.
Meanwhile, the more piece cladding nuclear fuels pipe 1 after being connected vertically is positioned at the middle part of die cavity 2, and is also provided with the back-up block 16 for supporting heater in the bottom of low head 8, and this back-up block 16 is insulator.
In addition, in this example, cladding nuclear fuels pipe 1 has two joints, and experiment tube is positioned at below, and when carrying out Quenching Treatment to experiment tube, the liquid level being positioned at the hardening liquid in quenching chamber 5 is in the below of web member 6.Prevent hardening liquid from infiltering the inside of experiment tube.
In this example, the length 250mm of experiment tube, the spacing between two joint cladding nuclear fuels pipes 1 is 10-20mm, and the height in quenching chamber is 350mm.
In sum, fuel tube of the present invention can free expansion and flexible in pipe thermal histories, simultaneously by web member by movable for adjacent two fuel tubes and sealing setting, prevent from cladding nuclear fuels pipe from expanding in heating process becoming curved phenomenon occurring, thus the performance of test material more accurately, significant to raising nuclear safety level.
Above to invention has been detailed description; its object is to allow the personage being familiar with this art can understand content of the present invention and be implemented; can not limit the scope of the invention with this; the equivalence change that all Spirit Essences according to the present invention are done or modification, all should be encompassed in protection scope of the present invention.
Claims (10)
1. simulate the experimental provision to cladding nuclear fuels pipe Performance Evaluation under LOCA operating mode, it is characterized in that: comprising:
For holding the die cavity of cladding nuclear fuels pipe, described die cavity comprises the vacuum chamber being positioned at upper and lower two ends be separated to form by seal and the quenching chamber being positioned at middle part, described seal is provided with through hole, described cladding nuclear fuels pipe has two joints at least, be tightly connected mutually by web member between every two joints, and in cladding nuclear fuels pipe described in more piece, have a joint to be the experiment tube that size meets experiment demand, described in more piece after being connected, the both ends up and down of cladding nuclear fuels pipe are each passed through the described through hole of corresponding end, and lay respectively in the described vacuum chamber at upper and lower two ends, the both ends of wherein said web member can be slidably arranged in described cladding nuclear fuels pipe respectively, and connecting hole is offered on described web member, described experiment tube can free-extension after expanded by heating,
For sealing upper cover and the low head at cladding nuclear fuels pipe both ends described in the more piece after being connected, and on described upper cover and low head, offer hole and lower opening respectively;
Heating arrangement, it comprises both ends and to penetrate respectively in described upper hole and lower opening and the heater being arranged in described connecting hole, and the inner wall insulation of described heater and described cladding nuclear fuels pipe separates by described upper cover and low head and described web member.
2. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, is characterized in that: described web member, upper cover are identical with the material of low head, is the one in quartz, pottery or boron carbide.
3. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, it is characterized in that: the both ends of described heater stretch out described upper cover and low head respectively, and described heating arrangement also comprises the electrode being connected to described heater both ends.
4. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 3, is characterized in that: the material of described electrode is copper.
5. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 3, is characterized in that: described heating arrangement also comprises the insulation course be separately positioned in described vacuum chamber, for being insulated mutually with described vacuum chamber by described electrode.
6. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, it is characterized in that: described in the more piece after being connected, cladding nuclear fuels pipe is vertically positioned at the middle part of described die cavity, and the back-up block be also provided with in the bottom of described low head for supporting described heater, described back-up block is insulator.
7. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, it is characterized in that: described upper hole, lower opening, connecting hole be centrally located on same straight line, the middle part of cladding nuclear fuels pipe described in the more piece after described heater is positioned at and is connected.
8. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, it is characterized in that: described cladding nuclear fuels pipe has two joints, described experiment tube is positioned at below, when carrying out Quenching Treatment to described experiment tube, the liquid level being positioned at the hardening liquid in described quenching chamber is in the below of described web member.
9. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, it is characterized in that: described experimental provision also comprises gas shield device, this gas shield device comprises blanket gas storer; Respectively to the pipeline passing into blanket gas in described vacuum chamber, quenching chamber and described cladding nuclear fuels pipe; And operation valve.
10. the experimental provision to cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode according to claim 1, it is characterized in that: described seal is water cooled seal part, the both ends up and down of cladding nuclear fuels pipe described in the more piece after being connected are sealed by carbon seal ring with described through hole respectively.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201610089338.8A CN105575446B (en) | 2016-02-17 | 2016-02-17 | Simulate under LOCA operating modes to the experimental provision of cladding nuclear fuels pipe Performance Evaluation |
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| CN201610089338.8A CN105575446B (en) | 2016-02-17 | 2016-02-17 | Simulate under LOCA operating modes to the experimental provision of cladding nuclear fuels pipe Performance Evaluation |
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| CN105575446B CN105575446B (en) | 2017-11-14 |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106018138A (en) * | 2016-07-22 | 2016-10-12 | 中国核动力研究设计院 | Insulation structure fragment characteristic identifying system and method based on jet experiment |
| CN107863161A (en) * | 2017-10-31 | 2018-03-30 | 岭澳核电有限公司 | Zirconium alloy cladding surface treatment method and zirconium alloy cladding |
| CN110957053A (en) * | 2019-12-18 | 2020-04-03 | 苏州热工研究院有限公司 | Test system for simulating high-fuel-consumption working condition of fuel cladding |
| CN113658727A (en) * | 2021-07-30 | 2021-11-16 | 中山大学 | Device for simulating overheating in fuel cladding pipe of nuclear power station |
| CN113776936A (en) * | 2021-08-17 | 2021-12-10 | 中国原子能科学研究院 | Testing device for simulating mechanical interaction of core block cladding outside stack |
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| CN205354674U (en) * | 2016-02-17 | 2016-06-29 | 苏州热工研究院有限公司 | Experimental device for to aassessment of nuclear fuel cladding pipe performance under simulation LOCA operating mode |
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Patent Citations (4)
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| US20120215444A1 (en) * | 2011-02-18 | 2012-08-23 | Mitsubishi Heavy Industries, Ltd. | Resonance calculation program and analyzing apparatus |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN106018138A (en) * | 2016-07-22 | 2016-10-12 | 中国核动力研究设计院 | Insulation structure fragment characteristic identifying system and method based on jet experiment |
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| CN110957053A (en) * | 2019-12-18 | 2020-04-03 | 苏州热工研究院有限公司 | Test system for simulating high-fuel-consumption working condition of fuel cladding |
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| CN113658727A (en) * | 2021-07-30 | 2021-11-16 | 中山大学 | Device for simulating overheating in fuel cladding pipe of nuclear power station |
| CN113776936A (en) * | 2021-08-17 | 2021-12-10 | 中国原子能科学研究院 | Testing device for simulating mechanical interaction of core block cladding outside stack |
| CN113776936B (en) * | 2021-08-17 | 2022-10-28 | 中国原子能科学研究院 | Test device for simulating mechanical interaction of pellet cladding outside reactor |
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| CN105575446B (en) | 2017-11-14 |
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