CN105070331A - Experiment apparatus for performance evaluation of nuclear fuel cladding pipe under LOCA simulation working condition - Google Patents
Experiment apparatus for performance evaluation of nuclear fuel cladding pipe under LOCA simulation working condition Download PDFInfo
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- CN105070331A CN105070331A CN201510465507.9A CN201510465507A CN105070331A CN 105070331 A CN105070331 A CN 105070331A CN 201510465507 A CN201510465507 A CN 201510465507A CN 105070331 A CN105070331 A CN 105070331A
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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
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- 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
Abstract
The present invention relates to an experiment apparatus for the performance evaluation of a nuclear fuel cladding pipe under an LOCA simulation working condition. The experiment apparatus comprises a molding cavity separated into an upper portion vacuum chamber and a lower portion quenching chamber through a sealing member, a heating device, a water vapor circulating device, a cooling device and a control system, wherein the control system comprises a first control unit for controlling a vacuumizing pump to vacuumize, a second control unit for controlling a liquid feeding unit to inject a cooling liquid, and a detecting and monitoring unit respectively for detecting and monitoring the pressure change in the vacuum chamber and the quenching chamber, and when the detecting and monitoring unit displays that the pressure in the vacuum chamber or quenching chamber decreases, the nuclear fuel cladding pipe is damaged so as to fail. According to the present invention, the design of the apparatus is delicate and reasonable, can well simulate the performance evaluation of the nuclear fuel cladding pipe under the LOCA working condition, and further has characteristics of simple structure, easy operation, and low cost.
Description
Technical field
The present invention relates to the experimental provision of a kind of cladding nuclear fuels pipe performance evaluation under simulation LOCA operating mode, when particularly a kind of LOCA of simulation operating mode occurs in high-temperature vapor oxidation and quenching for evaluating the experimental provision of cladding nuclear fuels performance.
Background technology
As everyone knows, LOCA(LossOfCoolantAccident) be one of accident the most serious in operational process of nuclear power plant.The generation of this accident, mainly because reactor-loop cooling medium runs off, causes core temperature sharply to rise, and in simultaneous reactions heap, pressure declines rapidly, causes safety injection system to water filling in heap, to cool the reactor core be rapidly heated.
Under LOCA operating mode (for zircaloy), when cladding nuclear fuels temperature is more than 600 DEG C, the decline due to external pressure causes fuel can generation swelling, breaks; When temperature is increased to more than 850 DEG C, can there is violent zirconium water reaction in fuel can zircaloy, involucrum external oxidation film thickness increases sharply, and simultaneous reactions discharges hydrogen.When carrying out water filling to reactor core, being equivalent to quench to zirconium alloy cladding, involucrum can being caused to become fragile and even break, radioactive fission product can be caused and leak.
For LOCA operating mode, CFR 10CFR50.65 has formulated the critical condition of fuel can integrality, namely, when maximum temperature 1204 DEG C, ECR (Equivalentcladdingreacted) are up to 17%, during cladding nuclear fuels quenching, integrality will be kept.Reach certain value ECR required time to be drawn by Baker-Just formulae discovery.The oxidation hydrogen output of involucrum be no more than all zirconium water reactions of hypothesis discharge 1% of hydrogen amount.China ECCS acceptance criteria is also with reference to this regulation.(1) the fuel can maximum temperature calculated should be no more than 1204 DEG C; (2) the maximum amount of oxidation of the fuel can calculated should not exceed 17% of involucrum original wall thickness; (3) 1% of reactor core involucrum general assembly (TW) (not comprising the weight of element rod chamber portion) should not be exceeded with the zirconium of the generation chemical reaction of water vapour or water.
If obtain the behavior of zircaloy fuel canning material under LOCA operating mode with in-reactor experiment, not only technical sophistication, and expend larger.Therefore, substantially adopt out-of-pile analogue technique and device, evaluate the performance of fuel kernel fuel tube.At present, the experimental provision of cladding nuclear fuels under simulation LOCA operating mode mainly contains two kinds: one is heated fuel kernel fuel tube by resistance furnace, then pass into water vapor, after the specific oxidization time of arrival, fuel can is dropped in water and quench.This experimental provision heats from outside cladding nuclear fuels, and nuclear reactor heap in actual condition be fuel pellet in cladding nuclear fuels inner heat, therefore this experimental provision differs far away with actual condition; The second experimental provision is researched and developed by atomic energy science institute of Korea S, adopts cladding nuclear fuels pipe inside to insert heater and heat, at cladding nuclear fuels pipe two ends holding electrode.Due to this LOCA device center fuel tube expanding with heat and contract with cold in heating process, electrode clamped by cladding nuclear fuels pipe upper end and the general assembly (TW) of accessory power line are in continuous change, therefore fuel kernel fuel tube bears certain external force in whole process of the test, and this produces certain impact by test findings.In addition, above-mentioned two kinds of equipment all can not realize the atmosphere protection function to cladding nuclear fuels pipe.
Summary of the invention
Technical matters to be solved by this invention overcomes the deficiencies in the prior art, provides the experimental provision of a kind of cladding nuclear fuels pipe performance evaluation under simulation LOCA operating mode.
For solving the problems of the technologies described above, the present invention takes following technical scheme:
An experimental provision for cladding nuclear fuels pipe performance evaluation under simulation LOCA operating mode, it comprises:
For holding the die cavity of cladding nuclear fuels pipe, die cavity comprises the superposed vacuum chamber be separated to form by seal and the quenching chamber being positioned at bottom, seal is provided with through hole, and the cladding nuclear fuels seal of tube is arranged in through-holes, and top is positioned at vacuum chamber, bottom is positioned at quenching chamber; Heating arrangement, it comprises the heating rod stretched into from cladding nuclear fuels tube opening in cladding nuclear fuels pipe, be set in auxiliary hot cell heat for the sleeve pipe that separated by the inner wall insulation of heating rod and cladding nuclear fuels pipe and auxiliary heating rod the periphery of heating rod, and the material of sleeve pipe is quartzy or ceramic; Water steam device, it comprises the steam evaporator and water vapor condenser that are connected with quenching chamber respectively; Vacuum extractor, it comprises vacuum pumping pump, the pipeline be connected with chamber of quenching with vacuum chamber respectively and operation valve; Cooling device, it comprises can respectively to feed liquor unit and the discharge opeing unit injecting liquid coolant in vacuum chamber and quenching chamber; Control system, it comprises for controlling the first control module that vacuum pumping pump vacuumizes, injecting the second control module of liquid coolant for controlling feed liquor unit and be respectively used to detect and monitor the prosecution unit that vacuum chamber and quenching cavity pressure change, wherein when prosecution unit display vacuum chamber or quenching cavity pressure decline, cladding nuclear fuels pipe damages and lost efficacy.
Concrete, the bottom of cladding nuclear fuels pipe is unsettled in quenching chamber, and comprise body, be welded at the bottom of the pipe of its bottom, the top of lower end part weld at the bottom of its bottom and pipe of heating rod, and the bottom of heating rod is greater than the height of weld apart from the distance bottom quenching chamber.Namely there is certain spacing between the weld of fuel tube and heating rod, prevent the weld temperature of fuel tube too high, lost efficacy prior to fuel tube, thus affect the accuracy of cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode.
Further, the sidewall in quenching chamber is respectively equipped with steam entry and steam outlet, respectively steam entry is connected with water vapor condenser with steam evaporator, steam outlet by pipeline, wherein the height of steam entry be greater than weld height, be less than heating rod bottom apart from quenching chamber bottom distance.Namely steam entry is positioned at more than fuel tube weld, position below heating rod, avoid the vigorous oxidation of fuel tube weld, lost efficacy prior to fuel tube, thus affect the accuracy of cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode.
Specifically implement and preferred aspect according to one of the present invention, seal is the close metal sealing of water-cooled, and the close metal sealing of water-cooled is connected with feed liquor unit; Cladding nuclear fuels pipe and through hole are sealed by carbon seal ring.
Preferably, in the close metal sealing of water-cooled and vacuum chamber, be equipped with the cavity volume holding liquid coolant, feed liquor unit comprises reservoir; The input duct be connected with the cavity volume of the cavity volume of vacuum chamber, chamber of quenching, the close metal sealing of water-cooled respectively; And the feed liquor controller to be connected with the second control module, wherein feed liquor controller can receive the instruction of the second control module and inject liquid coolant in cavity volume respectively to the cavity volume of vacuum chamber, quenching chamber, the close metal sealing of water-cooled.
Preferably, second control module comprises message handler, the thermometric window be arranged on quenching chamber, can through the infrared detector of thermometric windows detecting cladding nuclear fuels pipe temperature, for recording infrared detector detected temperatures value and information being passed to the watch-dog of message handler, wherein by message handler according to receiving cladding nuclear fuels pipe temperature information and assigning instruction.
Preferably, auxiliary hot cell comprises heating controller, heating source, the first wire for being connected with heating rod by heating source; And one end be connected to the second wire that information is passed on the branch road of watch-dog by infrared detector, the other end is connected with heating controller, the information that wherein heating controller detects according to receiving infrared-ray detector assigns heating instructions to heating rod.
Preferably, discharge opeing unit comprise be positioned at quenching chamber bottom discharging tube and tapping valve.
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 and the operation valve that pass into blanket gas in vacuum chamber and quenching chamber.
Preferably, control system also comprises the 3rd control module passing into vacuum chamber and quenching intracavity gas flow for controlling gas shield device.
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, and rationally, it can simulate the evaluation of cladding nuclear fuels pipe performance under LOCA operating mode well, and 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 (broken section) according to experimental provision of the present invention;
Wherein: 1, cladding nuclear fuels pipe (zirconium alloy cladding pipe); 2, die cavity; 20, seal (the close metal sealing of water-cooled); 21, vacuum chamber; 22, quenching chamber; 3, heating arrangement; 30, heating rod; 31, sleeve pipe (quartz socket tube); 32, auxiliary hot cell; 320, heating controller; 321, the first wire; 322, the second wire; 4, water steam device; 40, steam evaporator; 41, water vapor condenser; 5, vacuum extractor; 50, vacuum pumping pump: 6, cooling device; 60, feed liquor unit; 600, reservoir; 602, feed liquor controller; 61, discharge opeing unit; 610, discharging tube; 611, tapping valve; 7, gas shield device; 70, gas reservoir; 8, control system; 80, the first control module; 800, control processor; 801, wire; 81, the second control module; 810, processor is ceased; 811, thermometric window; 812, infrared detector (double color infrared temperature measuring instrument); 813, watch-dog (computer); 82, the 3rd control module; 820, traffic handler; 83, prosecution unit; 830,831, vacuum meter; 42,51,601,71,821, pipeline; 43,44,52,53,54,603,72, operation valve.
Embodiment
As shown in Figure 1; this example provides the experimental provision of a kind of cladding nuclear fuels pipe performance evaluation under simulation LOCA operating mode, and it mainly comprises die cavity 2, heating arrangement 3, water steam device 4, vacuum extractor 5, cooling device 6, gas shield device 7, control system 8 for holding cladding nuclear fuels pipe 1.Below various piece is described in detail.
At the bottom of the pipe that cladding nuclear fuels pipe 1 comprises body 10, be welded on bottom body 10 11.
Die cavity 2 is extended along vertical direction, it comprises the superposed vacuum chamber 21 be separated to form by seal 20 and the quenching chamber 22 being positioned at bottom, seal 20 is provided with through hole, the insertion through hole of cladding nuclear fuels pipe 1 from bottom top is positioned at vacuum chamber 21, bottom is positioned at quenching chamber 22, and cladding nuclear fuels pipe 1 and through hole are tightly connected.
Further, the bottom of cladding nuclear fuels pipe 1 is unsettled in quenching chamber 22, and seal 20 is horizontally disposed with, and through hole is positioned at the middle part of seal 20, cladding nuclear fuels pipe 1 is arranged in through hole along die cavity 2 short transverse, then cladding nuclear fuels pipe 1 and through hole is sealed by carbon seal ring.Seal 20 is the close metal sealing of water-cooled, is equipped with the cavity volume of the heat eliminating medium (liquid coolant) that can hold cooling device 6 in the close metal sealing of this water-cooled and vacuum chamber 21.
Heating arrangement 3 comprises the heating rod 30 stretched into from cladding nuclear fuels pipe 1 opening in cladding nuclear fuels pipe 1, be set in the auxiliary hot cell 32 heated for the sleeve pipe 31 that heating rod 30 and the inner wall insulation of cladding nuclear fuels pipe 1 separated and auxiliary heating rod 30 periphery of heating rod 30, the material of its middle sleeve 31 is quartz or ceramic, its performance: insulate, high temperature resistant, thermal conductivity good.
Concrete, the top of the lower end part of heating rod 30 11 welds bottom body 10 and at the bottom of pipe, and the bottom of heating rod 30 is greater than the height of weld apart from the distance bottom quenching chamber 22.Namely there is certain spacing between the weld of fuel tube 1 and heating rod 30, prevent the weld temperature of fuel tube 1 too high, lost efficacy prior to the body 10 of fuel tube 1, thus affected the accuracy of cladding nuclear fuels pipe 1 Performance Evaluation under simulation LOCA operating mode.
Further, heating rod 30 is made up of tungalloy, and sleeve pipe 31 is quartz socket tube.
Water steam device 4 comprises the steam evaporator 40 and water vapor condenser 41 that are connected with quenching chamber 22 respectively, and connecting pipe 42 and operation valve 43, 44, wherein steam evaporator 40 and water vapor condenser 41 are conventional design, simultaneously, the sidewall in quenching chamber 22 is respectively equipped with steam entry and steam outlet, pipeline 42 is respectively by steam entry and steam evaporator 40, steam outlet is connected with water vapor condenser 41, wherein the height of steam entry is greater than the height of weld, be less than heating rod 30 bottom apart from the distance bottom quenching chamber 22.Namely steam entry is positioned at more than fuel tube 1 weld, the position of heating rod less than 30, avoid the vigorous oxidation of fuel tube weld, lost efficacy prior to the body 10 of fuel tube 1, thus affect the accuracy of cladding nuclear fuels pipe Performance Evaluation under simulation LOCA operating mode.
Vacuum extractor 5 comprises vacuum pumping pump 50, the pipeline 51 be connected with chamber 22 of quenching with vacuum chamber 21 respectively and operation valve 52,53,54.
Cooling device 6 comprises can respectively to feed liquor unit 60 and the discharge opeing unit 61 injecting liquid coolant in the cavity volume of the cavity volume of vacuum chamber 21, quench chamber 22 and the close metal sealing of water-cooled, and its liquid coolant is water.
Gas shield device 7 comprises blanket gas storer 70, respectively to the pipeline 71 and the operation valve 72 that pass into blanket gas in vacuum chamber 21 and quenching chamber 22.
Control system 8; it comprises for controlling the first control module 80 that vacuum pumping pump 50 vacuumizes, the second control module 81 injecting liquid coolant for controlling feed liquor unit 60, passing into the 3rd control module 82 of gas flow in vacuum chamber 21 and quenching chamber 22 for controlling gas shield device 7 and be respectively used to detect and monitor the prosecution unit 83 that in vacuum chamber 21 and quenching chamber 22, pressure changes; wherein when prosecution unit 83 shows pressure drop in vacuum chamber 21 or quenching chamber 22, cladding nuclear fuels pipe 1 damages and lost efficacy.
Concrete, feed liquor unit 60 comprises reservoir 600; The input duct 601 be connected with the cavity volume of the cavity volume of vacuum chamber 21, chamber 22 of quenching, the close metal sealing of water-cooled respectively; The feed liquor controller 602 be connected with the second control module 81; And operation valve 603; Wherein feed liquor controller 602 can receive the second control module 81 instruction and respectively to vacuum chamber 21 cavity volume, quenching chamber 22, the close metal sealing of water-cooled cavity volume in inject liquid coolant, this feed liquor controller 602 is with water flow controller simultaneously, can be quantitative carry out water filling.
Further, the first control module 80 mainly comprises can assign the control processor 800 vacuumizing instruction and the wire 801 be connected with vacuum pumping pump 50 by control processor 800 to vacuum pumping pump 50, is also conventional design; Second control module 81 comprises message handler 810, the thermometric window 811 be arranged on quenching chamber 22, can through thermometric window 811 detect cladding nuclear fuels pipe 1 temperature infrared detector 812, for recording infrared detector 812 detected temperatures value and information being passed to the watch-dog 813 of message handler 810, wherein by message handler 810 according to receiving cladding nuclear fuels pipe 1 temperature information and assigning instruction; 3rd control module 82 mainly comprises the pipeline 821 that traffic handler 820 and traffic handler 820 are connected, and is also conventional design.
Further, auxiliary hot cell 32 comprises heating controller 320, heating source, the first wire 321 for being connected with heating rod 30 by heating source; And one end be connected to the second wire 322 that information is passed on the branch road of watch-dog 813 by infrared detector 812, the other end is connected with heating controller 320, the information that wherein heating controller 320 detects according to receiving infrared-ray detector 812 assigns heating instructions to heating rod 30.
Concrete, discharge opeing unit 61 comprises and is positioned at discharging tube 610 bottom quenching chamber 22 and tapping valve 611.
Prosecution unit 83 comprises the vacuum meter 830,831 laying respectively at and pipeline 42,71 can detect vacuum pressure in vacuum chamber 21 and quenching chamber 22.
In addition, all in this example valves are solenoid electric valve.
This test unit selects the sampling period to be the cladding nuclear fuels pipe temperature of data collecting card as data logging computers of 0.1s, the signal input of external and internal pressure, records the temperature of very short time kernel fuel tube, external and internal pressure and the time dependent curve of pipe internal hydrogen content.This test unit center fuel tube (for zirconium alloy cladding pipe) maximum temperature can reach 1500 DEG C, the fastest heating rate is 400 DEG C/min, realize steam oxidation and quenching function simultaneously, the LOCA requirement of experiment of Nuclear Power Station fuel zirconium alloy cladding can be met.
The operating process following (by reference to the accompanying drawings) of physical simulation LOCA operating mode:
First, the through hole of the bottom of cladding nuclear fuels pipe 1 on the close metal sealing 20 of water-cooled is stretched into quenching chamber 22, the top of cladding nuclear fuels pipe 1 is made to be positioned at vacuum chamber 21, bottom is positioned at quenching chamber 22, then quartz socket tube 31 is adopted heating rod 30 and cladding nuclear fuels pipe 1 inner wall insulation to be separated, make the lower end part of heating rod 30 in the top of cladding nuclear fuels pipe 1 weld, then airtight die cavity 2, respectively quenching chamber 22 and vacuum chamber 21 are vacuumized, now operation valve 52, 53, 54 are in opening, operation valve 72, 44, 603 are in closed condition, first control module 80 is assigned to vacuum pumping pump 50 and is vacuumized instruction, realization quenching chamber 21 and vacuum chamber 22 vacuumize, then, open cold radiator cooler 6, cools vacuum chamber 21 and water-cooled metal seal 20, after the vacuum tightness in quench chamber 22 and vacuum chamber 21 reaches certain value, blanket gas is passed in vacuum chamber 22, now operation valve 52 is in closed condition, operation valve 72,53,54 is in opening, under the 3rd control module 82 acts on, control charge flow rate, regulate the air pressure in vacuum chamber 21, make it higher than atmospheric pressure, then closed control valve 72, fills the depressed bundle of protection, open heating auxiliary unit 32 pairs of heating rods 30 subsequently to heat, fuel tube 1 thereupon temperature raises, the temperature of fuel tube 1 is by infrared detector 812(double color infrared temperature measuring instrument) carry out thermometric, after fuel tube 1 temperature arrives assigned temperature, to fetch boiling water steam generator 40 and operation valve 43,54, make water vapor enter quenching chamber 22 discharging from condenser 41, realize the evaluation to fuel tube performance under the environment of steam oxidation, when the chamber 22 inner water flowing steam time of quenching arrives the fixed time, open operation valve 603 by the second control module, quantitatively carry out water filling to quenching chamber 22, the evaluation to fuel tube performance under realization quenching environment.
The conclusion of the present embodiment experimental provision is: once fuel tube 1, breakage occurs, and fuel tube 1 internal pressure can sharply decline, and pressure drop by vacuum meter 830 reading, now can judge that fuel tube 1 lost efficacy.
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. an experimental provision for cladding nuclear fuels pipe performance evaluation under simulation LOCA operating mode, is characterized in that: comprising:
For holding the die cavity of cladding nuclear fuels pipe, described die cavity comprises the superposed vacuum chamber be separated to form by seal and the quenching chamber being positioned at bottom, described seal is provided with through hole, and the described cladding nuclear fuels seal of tube is arranged on that in described through hole and top is positioned at described vacuum chamber, bottom is positioned at described quenching chamber;
Heating arrangement, it comprises the heating rod stretched into from described cladding nuclear fuels tube opening in described cladding nuclear fuels pipe, be set in auxiliary hot cell heat for the sleeve pipe that separated by the inner wall insulation of described heating rod and described cladding nuclear fuels pipe and auxiliary described heating rod the periphery of described heating rod, and the material of described sleeve pipe is quartzy or ceramic;
Water steam device, it comprises the steam evaporator and water vapor condenser that are connected with described quenching chamber respectively;
Vacuum extractor, it comprises vacuum pumping pump, the pipeline be connected with chamber of quenching with described vacuum chamber respectively and operation valve;
Cooling device, it comprises can respectively to feed liquor unit and the discharge opeing unit injecting liquid coolant in described vacuum chamber and quenching chamber;
Control system, it comprises for controlling the first control module that described vacuum pumping pump vacuumizes, injecting the second control module of liquid coolant for controlling described feed liquor unit and be respectively used to detect and monitor the prosecution unit that described vacuum chamber and described quenching cavity pressure change, wherein when the vacuum chamber described in described prosecution unit display or described quenching cavity pressure decline, described cladding nuclear fuels pipe damages and lost efficacy.
2. the experimental provision of cladding nuclear fuels pipe according to claim 1 performance evaluation under simulation LOCA operating mode, it is characterized in that: the bottom of described cladding nuclear fuels pipe is unsettled in described quenching chamber, and comprise body, be welded at the bottom of the pipe of described its bottom, the top of lower end part weld at the bottom of described its bottom and described pipe of described heating rod, and the bottom of described heating rod is greater than the height of described weld apart from the distance bottom described quenching chamber.
3. the experimental provision of cladding nuclear fuels pipe according to claim 2 performance evaluation under simulation LOCA operating mode, it is characterized in that: on the sidewall in described quenching chamber, be respectively equipped with steam entry and steam outlet, be connected with water vapor condenser with described steam evaporator, described steam outlet by described steam entry respectively by pipeline, the height of wherein said steam entry is greater than the height of described weld, is less than described heating rod bottom apart from the distance bottom described quenching chamber.
4. the experimental provision of cladding nuclear fuels pipe according to claim 1 performance evaluation under simulation LOCA operating mode, is characterized in that: described seal is the close metal sealing of water-cooled, and described water-cooled close metal sealing is connected with described feed liquor unit; Described cladding nuclear fuels pipe and described through hole are sealed by carbon seal ring.
5. the experimental provision of cladding nuclear fuels pipe according to claim 4 performance evaluation under simulation LOCA operating mode, it is characterized in that: in described water-cooled close metal sealing and described vacuum chamber, be equipped with the cavity volume holding described liquid coolant, described feed liquor unit comprises reservoir; The input duct be connected with the cavity volume of the cavity volume of described vacuum chamber, chamber of quenching, the close metal sealing of water-cooled respectively; And the feed liquor controller to be connected with described second control module, wherein said feed liquor controller can receive the instruction of described second control module and inject described liquid coolant in cavity volume respectively to the cavity volume of described vacuum chamber, quenching chamber, water-cooled close metal sealing.
6. the experimental provision of cladding nuclear fuels pipe according to claim 5 performance evaluation under simulation LOCA operating mode, it is characterized in that: the second described control module comprises message handler, be arranged on the thermometric window on described quenching chamber, can through the infrared detector of cladding nuclear fuels pipe temperature described in described thermometric windows detecting, for recording described infrared detector detected temperatures value and information being passed to the watch-dog of described message handler, wherein by described message handler according to receiving described cladding nuclear fuels pipe temperature information and assigning described instruction.
7. the experimental provision of cladding nuclear fuels pipe according to claim 6 performance evaluation under simulation LOCA operating mode, is characterized in that: described auxiliary hot cell comprises heating controller, heating source, the first wire for being connected with described heating rod by described heating source; And one end be connected to the second wire that information is passed on the branch road of described watch-dog by described infrared detector, the other end is connected with described heating controller, wherein said heating controller assigns heating instructions according to receiving the information that described infrared detector detects to described heating rod.
8. the experimental provision of cladding nuclear fuels pipe according to claim 1 performance evaluation under simulation LOCA operating mode, is characterized in that: described discharge opeing unit comprises and is positioned at discharging tube bottom described quenching chamber and tapping valve.
9. the experimental provision of cladding nuclear fuels pipe according to claim 1 performance evaluation under simulation LOCA operating mode; 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 and the operation valve that pass into blanket gas in described vacuum chamber and quenching chamber.
10. the experimental provision of cladding nuclear fuels pipe according to claim 9 performance evaluation under simulation LOCA operating mode, is characterized in that: described control system also comprises the 3rd control module passing into described vacuum chamber and quenching intracavity gas flow for controlling described gas shield device.
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| CN105575447A (en) * | 2016-02-17 | 2016-05-11 | 苏州热工研究院有限公司 | Experimental device for assessing nuclear fuel cladding pipe performance under simulated LOCA working condition |
| CN105575446A (en) * | 2016-02-17 | 2016-05-11 | 苏州热工研究院有限公司 | Experimental device for assessing performance of nuclear fuel cladding pipe under simulated LOCA working condition |
| CN105761768A (en) * | 2016-04-12 | 2016-07-13 | 苏州热工研究院有限公司 | Performance evaluation system for integrity of zirconium alloy fuel cladding for nuclear power station under LOCA (Loss-Of-Coolant Accident) working condition |
| CN107167488A (en) * | 2017-05-09 | 2017-09-15 | 中国原子能科学研究院 | Reactor cladding materials pyrogenic steam oxidation quenching experimental apparatus and its test method |
| 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 |
| CN109147970A (en) * | 2018-08-10 | 2019-01-04 | 中广核研究院有限公司 | Fuel can LOCA simulation test device |
| 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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