CN106328226A - Nuclear reactor fuel rod simulating electric heating device and assembly process - Google Patents
Nuclear reactor fuel rod simulating electric heating device and assembly process Download PDFInfo
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- CN106328226A CN106328226A CN201610838185.2A CN201610838185A CN106328226A CN 106328226 A CN106328226 A CN 106328226A CN 201610838185 A CN201610838185 A CN 201610838185A CN 106328226 A CN106328226 A CN 106328226A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/002—Detection of leaks
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/04—Detecting burst slugs
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
- G21C17/07—Leak testing
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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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- General Engineering & Computer Science (AREA)
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear reactor fuel rod simulating electric heating device and an assembly process. The device comprises a simulation jacket and simulation fuel element pellets, each simulation fuel element pellet is provided with 16 through holes axially extending along the simulation fuel element pellet, thermocouple wire anodes are mounted in part of the through holes, thermocouple wire cathodes are mounted in part of the through holes, and inert gas is stored in the rest through holes. Electric heating rods are mounted in an inner cavity of each simulation fuel element pellet, and a plurality of external wall temperature thermocouples are mounted on the outer side of the simulation jacket. The electric heating device is used for laboratory simulation of nuclear reactor fuel rods to carry out high-temperature degradation and reflooding behavioral experiments of fuel rods for pressurized water reactors under severe accident conditions. A working medium is an aqueous medium, a steam medium or an inert gas medium, a working pressure is 5MPa, a long-term working temperature is 1800 DEG C, and a short-term working temperature is 2400 DEG C.
Description
Technical field
The present invention relates to a kind of electrician tool, be specifically related to a kind of electric heater unit simulating nuclear reactor fuel rod and dress
Allotment of labor's skill.
Background technology
The safety improving reactor operation is thick-and-thin task during nuclear energy application development.After Fukushima accident,
Proposition one after another such as nuclear technology the developed country such as U.S., France etc. is alleviated of equal importance with prevention in the world, little particularly with some
The major accident phenomenon of probability Risks have to cause enough attention.In Severe accident management, it is the heaviest that reactor core is flooded in water filling
The coping strategy wanted, termination accident is developed by it, alleviates damage sequence and plays an important role, and the importance of this strategy is at Fukushima
Nuclear accident is embodied.But, before successfully cooling down fuel assembly, the injection of water may result in zircaloy and sends out with water
The zirconium water reaction of raw heat release, thus cause the generation of core temperature rapid increase and hydrogen.This phenomenon is in Three Mile Island accident
Post analysis and the multinomial international cooperation carried out subsequently are verified in testing.
In order to grasp the impact of waterflood timing, injection flow and material type etc., correct for presurized water reactor loss of-coolant accident (LOCA)
Intervene and reference is provided, it is necessary to carry out presurized water reactor fuel element high temperature and degrade and flood behavioral experiment again.Accordingly, it would be desirable to a kind of mould
The electric heater unit of nucleoid reactor fuel rod, to realize electrical heating power controllable precise, it is achieved nuclear reactor under major accident
The simulation of the phenomenons such as the zirconium water that fuel rod occurs reacts, top layer ruptures, under the conditions of the top layer breakage of analog fuel rod, may continue to
Heating is used for simulating decay heat, can tolerate 2400 DEG C of high temperature above and measures wall temperature etc. the most in real time.
With key word high temperature (High temperature), analog (Simulator), electrical heating (Electric
Heating), zirconium water reacts (zirconium-steam/water reaction), floods (Reflooding), fuel rod again
(Fuel Rod), quenching (Quench) are retrieved on the net at patent network and Chinese and English periodical, do not retrieve and relate to the party
The record of surface technology.Realize electrical heating power controllable precise, it is achieved the zirconium water that under major accident, nuclear reactor fuel rod occurs is anti-
Should, top layer the technical bottleneck that the analogue technique of phenomenon is this area such as rupture, it would be highly desirable to solve.
Summary of the invention
It is an object of the invention to provide a kind of electric heater unit simulating nuclear reactor fuel rod and assembly technology, it is achieved
Electrical heating power controllable precise, it is achieved the phenomenons such as the zirconium water that under major accident, nuclear reactor fuel rod occurs reacts, top layer ruptures
Simulation, reach under the conditions of the top layer breakage of analog fuel rod, may continue to heating for simulating decay heat, can tolerate 2400 DEG C
High temperature above measures the purpose of wall temperature the most in real time.
The present invention is achieved through the following technical solutions:
A kind of electric heater unit simulating nuclear reactor fuel rod, including simulation involucrum, is provided with in simulation involucrum
The multiple analog fuel element pellets stacked in the axial direction of simulation involucrum, the cross section of analog fuel element pellet is ring-type knot
Structure, is provided with on analog fuel element pellet along its axially extended 16 through holes, is provided with in the through hole described in part
Thermocouple wire positive pole, thermocouple wire negative pole is installed in the through hole described in part, in through hole remaining described, stores inertia
Gas；In the internal cavities of analog fuel element pellet, electrically heated rod is installed；Simulation involucrum outside be provided with multiple outside
Put formula wall temperature thermocouple.The electric heater unit electrical heating power controllable precise of the present invention, heater can tolerate 3000 DEG C of high temperature,
Under the conditions of the clad failure of analog fuel rod top layer, may continue to generate heat for simulating decay heat, analog fuel pellet is "dead"
And similar to Uranous oxide physical property, can the thermal characteristics of preferable analog fuel pellet, core under major accident can be simulated
The phenomenons such as the zirconium water that reactor fuel rod occurs reacts, top layer ruptures；When involucrum occurs damaged, special noble gas can occur
Leakage, the special noble gas leaked out can be used for the real-time monitoring that top layer is damaged.Arrange in analog fuel rod involucrum external welding
Wall temperature thermocouple, uses embedded thermocouple simultaneously, and the measuring point that can arrange is more, and heatproof is higher, measures 0 DEG C～2400 DEG C in real time
Wall surface temperature.Present invention is mainly used for laboratory simulation nuclear reaction fuel rod, carry out presurized water reactor fuel under severe accident conditions
Rod high temperature degrades and floods behavioral experiment again.Working media is aqueous medium, steam medium or noble gas medium, and operating pressure is normal
Pressure～5MPa, Long-term service temperature is room temperature～1800 DEG C, and short-term job temperature is room temperature～2400 DEG C.
Described electrically heated rod uses tungsten, molybdenum, tungsten-molybdenum alloy or molybdenum-copper to make club shaped structure, and its one end is plane,
The other end is spherical end surface, carries out cutting processing from the planar ends of club shaped structure and forms gap, installs insulating barrier in this gap.
Further, metal bar of the present invention uses split-type structure, can increase swell increment under heating condition so that metal bar and simulation combustion
Material pellet contact is the tightst, reduces heat transfer resistance, reduces metal bar temperature, extend electricity under the conditions of identical simulation clad temperature
In the heating rod life-span, expand operating temperature range；The metal bar of the present invention, as electric heater, uses and arranges insulation in the middle of split-type
The structure of layer, can realize the single-ended turnover of cable, reduces the sealing difficulty of analog fuel rod.
Use ZrO2Material simulation fuel pellet, "dead" and physical property is similar, can preferable analog fuel core
The thermal characteristics of block.Top layer involucrum uses analog fuel rod involucrum same material, can simulate nuclear reactor fuel under major accident
The phenomenons such as the zirconium water that rod occurs reacts, top layer ruptures；It is provided with special noble gas storage area in simulation involucrum, sends out at involucrum
Special noble gas can be occurred to leak during raw breakage, the special noble gas leaked out can be used for the real-time monitoring that top layer is damaged；
Arranging wall temperature thermocouple in analog fuel rod involucrum external welding, use embedded thermocouple simultaneously, the measuring point that can arrange is more, resistance to
Wen Genggao, measures 0 DEG C～2400 DEG C of wall surface temperatures in real time.
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod, comprises the following steps:
The processing of (a) simulation involucrum；
The processing of (b) analog fuel element pellet；
(c) electrically heated rod and the processing of insulating barrier；
(d) analog fuel element pellet and the assembling of high temperature thermoelectric thermo wires；
The assembling of (e) electrically heated rod；
The filling of (f) noble gas；
The assembling of (g) external wall temperature thermocouple.
It is a further object to provide the assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod,
Based on above-mentioned new equipment, and it specifically uses environment and requirement, therefore the proposition of creativeness and optimize the life of this device
Production. art, can reproduce the purpose of the present invention with high-repetition-rate according to above-mentioned technique, with it, that produces adds hot charging
Put repeatable high, there is the highest practical value.
The processing of described step (a) simulation involucrum comprises the following steps:
(a1) determining nuclear reactor fuel rod to be simulated, if its involucrum external diameter is D, a length of L, outer diameter tolerance is
TD, outer surface roughness is Ra；
(a2) light-wall pipe, a length of L are made in the materials processing choosing material identical with its involucrum, and OD of Thin Wall Welded Pipe is Do1,
Internal diameter is Di1；OD of Thin Wall Welded Pipe Do1 with D is equal, and internal diameter Di1=Do1-d1, d1 are the light-wall pipe wall thickness of twice, span
It is 1.0～1.8mm；
(a3) light-wall pipe outer surface uses glossing to process, and roughness is identical with Ra, and inner surface uses at glossing
Reason, roughness is not more than 1.6 μm；OD of Thin Wall Welded Pipe tolerance and TDIdentical, id tolerance is not more than 0.04mm, and ovality is not more than
0.01mm。
The processing of described step (b) analog fuel element pellet comprises the following steps:
(b1) material selection ZrO of analog fuel element pellet2、HfO2Or Al2O3Or three's mixture, the system of being processed
Circularizing pellet, the external diameter of Annular pellet is Do2, and internal diameter is Di2；Annular pellet outer diameter D o2=Di1-d12, internal diameter Di2=
Do2-d2；D12 is assemblage gap and thermal expansion preset clearance, and span is 0.1～0.2mm；D2 is the Annular pellet of twice
Wall thickness, span is 2.5～4.5mm；The a length of Lxin of single-unit Annular pellet, according to analog fuel rod total length and required peace
Dress temperature point position determines the value of Lxin, it is ensured that temperature point position is in the interface of two joint Annular pellets, and Lxin takes
Value scope is 50～200mm；Annular pellet end surface uses blasting treatment, and roughness is not more than 0.8 μm；
(b2) Annular pellet is often saved at diameter DStorageCircle on uniformly process 16 diameter DHoleThrough hole；DStorage=Do2-
DHole, DHoleFor the diameter of through hole, DHole=dThermocouple wire+dGap, dThermocouple wireFor the diameter of high temperature thermoelectric thermo wires, span is 0.1～0.5mm；
dGapFor assemblage gap, span is 0.15～0.3mm；
(b3) Annular pellet outer surface uses blasting treatment, and roughness is not more than 3.2 μm, and inner surface is also adopted by sandblasting
Reason, roughness is not more than 3.2 μm；Annular pellet outer diameter tolerance is not more than 0.04mm, and id tolerance is not more than 0.04mm, ovality
It is not more than 0.01mm.
The processing of described step (c) electrically heated rod and insulating barrier comprises the following steps:
(c1) choose tungsten, molybdenum, tungsten-molybdenum alloy or molybdenum-copper as electrically heated rod material, and be processed into bar-shaped, one
End is plane, and the other end is spherical end surface, and metal bar overall diameter is D3, a length of L+D3/2, the diameter of metal bar spherical end surface
For D3；D3=Di2-d23, d23 are assemblage gap and thermal expansion preset clearance, and span is 0.1～0.2mm, outside metal bar
Surface uses glossing to process, and roughness is not more than 3.2 μm；
(c2) carrying out cutting processing from one end of metal bar plane, processing an interspace width is DTungsten gapGap,
The gap degree of depth is L, and bottom gap, a diameter of (0.5 × D is processed in terminationTungsten gap+ 0.2mm) semicircle, DTungsten gap=0.2～0.5mm；
(c3) ZrO is chosen2、HfO2Or Al2O3Or three's mixture is as insulating layer material, and insulating barrier is processed into width
For (D3-0.05mm), thickness is (DTungsten gap-0.05mm), the flat board of a length of (L-0.1mm), the insulating barrier setting-in that will process
Enter the gap of electrically heated rod so that insulating barrier keeps concordant with electrically heated rod upper end.
Described step (d) analog fuel element pellet comprises the following steps with the assembling of high temperature thermoelectric thermo wires:
(d1) analog fuel element pellet is embedded in into simulation involucrum, a joint analog fuel element pellet is installed every time, makes
Use diameter DLocationMetal bar as alignment pin, it is ensured that each joint 16 diameter D of analog fuel pelletHoleThe position one_to_one corresponding of through hole,
DLocation=DHole-0.15mm；
(d2) high temperature thermoelectric thermo wires thermometric end being curved quarter bend, the centerline length of right angle curved segment is LSurvey, LSurvey=DHole-
0.5×dThermocouple wire+0.5×d12；First analog fuel pellet is installed to needing to arrange the height of temperature point, temperature is set at needs
Two thermocouple wire inlaid hole positions near at degree measuring point, extract alignment pin out and arrange a pair high temperature thermoelectric thermo wires；Follow-up
The one inlaid hole position saving two thermocouple wires on analog fuel pellet at corresponding temperature measuring point, respectively one diameter of processing
DHole, deep 0.5 × DHoleSemicircle orifice, this joint analog fuel pellet is embedded in into simulation involucrum so that a pair diameter DHole, deep 0.5 ×
DHoleThe position of semicircle orifice correspondence high temperature thermoelectric thermo wires thermometric end quarter bend, a pair high temperature thermoelectric thermo wires is respectively by corresponding
Two thermocouple wire inlaid holes are drawn；Installing follow-up analog fuel pellet the most again, a pair high temperature thermoelectric thermo wires passes through respectively
Two corresponding thermocouple wire inlaid holes are drawn；
(d3) from low to high, high temperature thermoelectric thermo wires is installed successively, until all temperature measuring thermocouple silk installations, so
Rear installation follow-up residue analog fuel element pellet, after all analog fuel element pellet installations, will remain alignment pin
Extract out, complete analog fuel element pellet and the setting-in of high temperature thermoelectric thermo wires.
The assembling of described step (e) electrically heated rod comprises the following steps: at analog fuel element pellet and pyrometer couple
After the setting-in of silk completes, electrically heated rod is embedded in into the cavity within analog fuel element pellet so that electrically heated rod and simulation
Fuel element pellet, simulation involucrum three upper end concordant.
The filling of described step (f) noble gas comprises the following steps:
(f1) use welding manner by electrically heated rod analog fuel element pellet, the two ends of simulation involucrum three's common end
Seal, only reserve injecting hole at the other end；
(f2) injecting special noble gas from injecting hole, the purity injecting noble gas is not less than 95%；
(f3) after special noble gas has injected, by welding manner, injecting hole is sealed, completes noble gas and fill out
Fill.
The assembling of described step (g) external wall temperature thermocouple comprises the following steps:
(g1) on the premise of meeting certainty of measurement demand and capacity of resisting disturbance, according to thermocouple heat resistance and thermometric need
Ask for value, select the armoured thermocouple that diameter is minimum, a diameter of d of armoured thermocoupleThermocouple, dThermocoupleSpan be 0.5～3mm；
(g2) need to arrange the position of temperature point, armoured thermocouple thermometric end is being touched with measured point, keep armour
Dress thermocouple remainder is away from testee, by electric pulse welding manner, by armoured thermocouple thermometric end and measured point
Weld.
The present invention compared with prior art, has such advantages as and beneficial effect:
1, a kind of electric heater unit simulating nuclear reactor fuel rod of the present invention and assembly technology, electric heater unit electrical heating
Power controllable precise, heater can tolerate 3000 DEG C of high temperature, under the conditions of the clad failure of analog fuel rod top layer, may continue to send out
Heat is used for simulating decay heat, and analog fuel pellet is "dead" and similar to Uranous oxide physical property, can preferably simulate
The thermal characteristics of fuel pellet, can simulate the zirconium water reaction of nuclear reactor fuel rod generation under major accident, top layer ruptures etc. shows
As；Special noble gas can be occurred to leak when involucrum occurs damaged, it is damaged that the special noble gas leaked out can be used for top layer
Real-time monitoring.Wall temperature thermocouple is set in analog fuel rod involucrum external welding, uses embedded thermocouple simultaneously, can arrange
Measuring point is more, and heatproof is higher, measures 0 DEG C～2400 DEG C of wall surface temperatures in real time.Present invention is mainly used for laboratory simulation nuclear reaction
Fuel rod, carries out presurized water reactor fuel rod high temperature under severe accident conditions and degrades and flood behavioral experiment again.Working media is water
Medium, steam medium or noble gas medium, operating pressure normal pressure～5MPa, Long-term service temperature is room temperature～1800 DEG C, short
Phase operating temperature is room temperature～2400 DEG C；
2, a kind of electric heater unit simulating nuclear reactor fuel rod of the present invention and assembly technology, metal bar uses split-type
Structure, can increase swell increment so that metal bar contacts the tightst with analog fuel pellet under heating condition, reduce heat transfer heat
Resistance, reduces metal bar temperature under the conditions of identical simulation clad temperature, extends the electrically heated rod life-span, expand operating temperature range；
The metal bar of the present invention, as electric heater, uses the structure arranging insulating barrier in the middle of split-type, can realize the single-ended turnover of cable,
Reduce the sealing difficulty of analog fuel rod；
3, a kind of electric heater unit simulating nuclear reactor fuel rod of the present invention and assembly technology, uses ZrO2Material simulation
Fuel pellet, "dead" and physical property is similar, can the thermal characteristics of preferable analog fuel pellet.Top layer involucrum uses mould
Intend fuel rod clad same material, zirconium water reaction that nuclear reactor fuel rod under major accident occurs can be simulated, top layer ruptures
Etc. phenomenon；It is provided with special noble gas storage area in simulation involucrum, when involucrum occurs damaged, special indifferent gas can occur
Body leaks, and the special noble gas leaked out can be used for the real-time monitoring that top layer is damaged；Set in analog fuel rod involucrum external welding
Putting wall temperature thermocouple, use embedded thermocouple simultaneously, the measuring point that can arrange is more, and heatproof is higher, measures 0 DEG C～2400 in real time
DEG C wall surface temperature.
Accompanying drawing explanation
Accompanying drawing described herein is used for providing being further appreciated by the embodiment of the present invention, constitutes of the application
Point, it is not intended that the restriction to the embodiment of the present invention.In the accompanying drawings:
Fig. 1 is electric heater unit cross-sectional structure schematic diagram of the present invention；
Fig. 2 is the A-A cross-sectional view in Fig. 1 of the present invention
Fig. 3 is the B-B cross-sectional view in Fig. 1 of the present invention；
Fig. 4 is the C-C cross-sectional view in Fig. 1 of the present invention.
The parts title of labelling and correspondence in accompanying drawing:
1-simulates involucrum；2-analog fuel element pellet；3-electrically heated rod；4-high temperature thermoelectric thermo wires positive pole；5-insulating barrier；
6-high temperature thermoelectric thermo wires negative pole；7-external wall temperature thermocouple；8-through hole.
Detailed description of the invention
For making the object, technical solutions and advantages of the present invention clearer, below in conjunction with embodiment and accompanying drawing, to this
Invention is described in further detail, and the exemplary embodiment of the present invention and explanation thereof are only used for explaining the present invention, do not make
For limitation of the invention.
Embodiment
As shown in Figures 1 to 4, a kind of electric heater unit simulating nuclear reactor fuel rod of the present invention, including simulation involucrum 1,
The multiple analog fuel element pellets 2 stacked in the axial direction of simulation involucrum 1, analog fuel unit it is provided with in simulation involucrum 1
The cross section of part pellet 2 is circulus, is provided with along its axially extended 16 through holes 8 on analog fuel element pellet 2,
Thermocouple wire positive pole 4 is installed in the through hole 8 described in part, in the through hole 8 described in part, thermocouple wire negative pole is installed
6, in through hole remaining described 8, store noble gas；In the internal cavities of analog fuel element pellet 2, electrical heating is installed
Rod 3；Electrically heated rod 3 uses tungsten, molybdenum, tungsten-molybdenum alloy or molybdenum-copper to make club shaped structure, and its one end is plane, and the other end is ball
Shape end face, carries out cutting processing and forms gap from one end of metal bar plane, installs insulating barrier 5 in this gap, at simulation bag
Multiple external wall temperature thermocouple 7 is installed outside shell 1.
A kind of electric heater unit simulating nuclear reactor fuel rod of the present invention assembles according to following technique:
(a1) determining nuclear reactor fuel rod to be simulated, if its involucrum external diameter is D, a length of L, outer diameter tolerance is
TD, outer surface roughness is Ra；
(a2) light-wall pipe, a length of L are made in the materials processing choosing material identical with its involucrum, and OD of Thin Wall Welded Pipe is Do1,
Internal diameter is Di1；OD of Thin Wall Welded Pipe Do1 with D is equal, and internal diameter Di1=Do1-d1, d1 are the light-wall pipe wall thickness of twice, span
It is 1.0～1.8mm；
(a3) light-wall pipe outer surface uses glossing to process, and roughness is identical with Ra, and inner surface uses at glossing
Reason, roughness is not more than 1.6 μm；OD of Thin Wall Welded Pipe tolerance and TDIdentical, id tolerance is not more than 0.04mm, and ovality is not more than
0.01mm；
(b1) material selection ZrO of analog fuel element pellet2、HfO2Or Al2O3Or three's mixture, the system of being processed
Circularizing pellet, the external diameter of Annular pellet is Do2, and internal diameter is Di2；Annular pellet outer diameter D o2=Di1-d12, internal diameter Di2=
Do2-d2；D12 is assemblage gap and thermal expansion preset clearance, and span is 0.1～0.2mm；D2 is the Annular pellet of twice
Wall thickness, span is 2.5～4.5mm；The a length of Lxin of single-unit Annular pellet, according to analog fuel rod total length and required peace
Dress temperature point position determines the value of Lxin, and Lxin value is variable, it is ensured that temperature point position is in two joint Annular pellets
Interface, Lxin span is 50～200mm；Annular pellet end surface uses blasting treatment, and roughness is not more than 0.8 μ
m；
(b2) Annular pellet is often saved at diameter DStorageCircle on uniformly process 16 diameter DHoleThrough hole；DStorage=Do2-
DHole, DHoleFor the diameter of through hole, DHole=dThermocouple wire+dGap, dThermocouple wireFor the diameter of high temperature thermoelectric thermo wires, span is 0.1～0.5mm；
dGapFor assemblage gap, span is 0.15～0.3mm；
(b3) Annular pellet outer surface uses blasting treatment, and roughness is not more than 3.2 μm, and inner surface is also adopted by sandblasting
Reason, roughness is not more than 3.2 μm；Annular pellet outer diameter tolerance is not more than 0.04mm, and id tolerance is not more than 0.04mm, ovality
It is not more than 0.01mm；
(c1) choose tungsten, molybdenum, tungsten-molybdenum alloy or molybdenum-copper as electrically heated rod material, and be processed into bar-shaped, one
End is plane, and the other end is spherical end surface, the W-Re pyrometer couple using Graduation Number to be WRe3-WRe25, high temperature thermoelectric thermo wires
Positive pole material nominal composition is tungstenic 97%, rhenium 3%, and high temperature thermoelectric thermo wires negative pole material nominal composition is tungstenic 75%, rhenium
25%, a high temperature thermoelectric thermo wires positive pole and a high temperature thermoelectric thermo wires negative pole are a pair high temperature thermoelectric thermo wires；Outside metal bar directly
Footpath is D3, a length of L+D3/2, a diameter of D3 of metal bar spherical end surface；D3=Di2-d23, d23 be assemblage gap and heat swollen
Swollen preset clearance, span is 0.1～0.2mm, and metal bar outer surface uses glossing to process, and roughness is not more than 3.2 μ
m；
(c2) carrying out cutting processing from one end of metal bar plane, processing an interspace width is DTungsten gapGap,
The gap degree of depth is L, and bottom gap, a diameter of (0.5 × D is processed in terminationTungsten gap+ 0.2mm) semicircle, DTungsten gap=0.2～0.5mm；
(c3) ZrO is chosen2、HfO2Or Al2O3Or three's mixture is as insulating layer material, and insulating barrier is processed into width
For (D3-0.05mm), thickness is (DTungsten gap-0.05mm), the flat board of a length of (L-0.1mm), the insulating barrier 5 processed is embedded in
Enter the gap of electrically heated rod 3 so that insulating barrier 5 keeps concordant with both electrically heated rods 3 upper end；
(d1) analog fuel element pellet 2 is embedded in into simulation involucrum 1, a joint analog fuel element pellet 2 is installed every time,
Use diameter DLocationMetal bar as alignment pin, it is ensured that each joint 16 diameter D of analog fuel pelletHoleOne a pair, the position of through hole
Should, DLocation=DHole-0.15mm；
(d2) high temperature thermoelectric thermo wires thermometric end being curved quarter bend, the centerline length of right angle curved segment is LSurvey, LSurvey=DHole-
0.5×dThermocouple wire+0.5×d12；First analog fuel pellet is installed to needing to arrange the height of temperature point, temperature is set at needs
Two thermocouple wire inlaid hole positions near at degree measuring point, extract alignment pin out and arrange a pair high temperature thermoelectric thermo wires；Follow-up
The one inlaid hole position saving two thermocouple wires on analog fuel pellet at corresponding temperature measuring point, respectively one diameter of processing
DHole, deep 0.5 × DHoleSemicircle orifice, this joint analog fuel pellet is embedded in into simulation involucrum so that a pair diameter DHole, deep 0.5 ×
DHoleThe position of semicircle orifice correspondence high temperature thermoelectric thermo wires thermometric end quarter bend, a pair high temperature thermoelectric thermo wires is respectively by corresponding
Two thermocouple wire inlaid holes are drawn；Installing follow-up analog fuel pellet the most again, a pair high temperature thermoelectric thermo wires passes through respectively
Two corresponding thermocouple wire inlaid holes are drawn；
(d3) from low to high, high temperature thermoelectric thermo wires is installed successively, until all temperature measuring thermocouple silk installations, so
Rear installation follow-up residue analog fuel element pellet 2, after the installation of all analog fuel element pellets 2, positions residue
Pin is extracted out, completes analog fuel element pellet 2 and the setting-in of high temperature thermoelectric thermo wires；
After the setting-in of analog fuel element pellet 2 and high temperature thermoelectric thermo wires completes, electrically heated rod 3 is embedded in and fires into simulation
Material cavity within element pellet 2 so that electrically heated rod 3 and analog fuel element pellet 2, the upper end of simulation involucrum 1 three
Concordant；
(f1) use welding manner by electrically heated rod 3 analog fuel element pellet 2, simulate involucrum 1 three's common end
Two ends seal, and only reserve injecting hole at the other end；
(f2) injecting special noble gas from injecting hole, the purity injecting noble gas is not less than 95%；
(f3) after special noble gas has injected, by welding manner, injecting hole is sealed, completes noble gas and fill out
Filling, special noble gas needs to be different from the noble gas of simulation nuclear reactor fuel rod flows outside, optional helium, neon
One in gas, argon, Krypton, xenon, radon gas etc.；
(g1) on the premise of meeting certainty of measurement demand and capacity of resisting disturbance, according to thermocouple heat resistance and thermometric need
Ask for value, select the armoured thermocouple that diameter is minimum, a diameter of d of armoured thermocoupleThermocouple, dThermocoupleSpan be 0.5～3mm；
(g2) need to arrange the position of temperature point, armoured thermocouple thermometric end is being touched with measured point, keep armour
Dress thermocouple remainder is away from testee, by electric pulse welding manner, by armoured thermocouple thermometric end and measured point
Weld.
Above-described detailed description of the invention, has been carried out the purpose of the present invention, technical scheme and beneficial effect further
Describe in detail, be it should be understood that the detailed description of the invention that the foregoing is only the present invention, be not intended to limit the present invention
Protection domain, all within the spirit and principles in the present invention, any modification, equivalent substitution and improvement etc. done, all should comprise
Within protection scope of the present invention.
Claims (10)
1. the electric heater unit simulating nuclear reactor fuel rod, it is characterised in that: include simulating involucrum (1), at simulation bag
The multiple analog fuel element pellets (2) stacked in the axial direction of simulation involucrum (1), analog fuel element it is provided with in shell (1)
The cross section of pellet (2) is circulus, is provided with along its axially extended 16 through holes on analog fuel element pellet (2)
(8) thermocouple wire positive pole (4), is installed in the through hole (8) described in part, in the through hole (8) described in part, heat is installed
Thermocouple wire negative pole (6), stores noble gas in through hole remaining described (8)；Empty in the inside of analog fuel element pellet (2)
Chamber is provided with electrically heated rod (3)；In simulation involucrum (1) outside, multiple external wall temperature thermocouple (7) is installed.
A kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 1 and assembly technology, its feature
It is: described electrically heated rod (3) uses tungsten, molybdenum, tungsten-molybdenum alloy or molybdenum-copper to make club shaped structure, and its one end is plane,
The other end is spherical end surface, carries out cutting processing from the planar ends of club shaped structure and forms gap, installs insulating barrier in this gap
(5)。
3. the assembly technology of the electric heater unit simulating nuclear reactor fuel rod, it is characterised in that comprise the following steps:
The processing of (a) simulation involucrum (1)；
The processing of (b) analog fuel element pellet (2)；
(c) electrically heated rod (3) and the processing of insulating barrier (5)；
(d) analog fuel element pellet (2) and the assembling of high temperature thermoelectric thermo wires；
The assembling of (e) electrically heated rod (3)；
The filling of (f) noble gas；
The assembling of (g) external wall temperature thermocouple (7).
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that the processing of described step (a) simulation involucrum (1) comprises the following steps:
(a1) determining nuclear reactor fuel rod to be simulated, if its involucrum external diameter is D, a length of L, outer diameter tolerance is TD, outward
Surface roughness is Ra；
(a2) light-wall pipe, a length of L are made in the materials processing choosing material identical with its involucrum, and OD of Thin Wall Welded Pipe is Do1, internal diameter
For Di1；OD of Thin Wall Welded Pipe Do1 with D is equal, and internal diameter Di1=Do1-d1, d1 are the light-wall pipe wall thickness of twice, and span is 1.0
～1.8mm；
(a3) light-wall pipe outer surface uses glossing to process, and roughness is identical with Ra, and inner surface uses glossing to process, slightly
Rugosity is not more than 1.6 μm；OD of Thin Wall Welded Pipe tolerance and TDIdentical, id tolerance is not more than 0.04mm, and ovality is not more than
0.01mm。
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that the processing of described step (b) analog fuel element pellet (2) comprises the following steps:
(b1) material selection ZrO of analog fuel element pellet2、HfO2Or Al2O3Or three's mixture, it is processed into annular
Pellet, the external diameter of Annular pellet is Do2, and internal diameter is Di2；Annular pellet outer diameter D o2=Di1-d12, internal diameter Di2=Do2-d2；
D12 is assemblage gap and thermal expansion preset clearance, and span is 0.1～0.2mm；D2 is the Annular pellet wall thickness of twice, takes
Value scope is 2.5～4.5mm；The a length of Lxin of single-unit Annular pellet, according to analog fuel rod total length and required installation temperature
Point position determines the value of Lxin, it is ensured that temperature point position is in the interface of two joint Annular pellets, Lxin span
It is 50～200mm；Annular pellet end surface uses blasting treatment, and roughness is not more than 0.8 μm；
(b2) Annular pellet is often saved at diameter DStorageCircle on uniformly process 16 diameter DHoleThrough hole；DStorage=Do2-DHole, DHole
For the diameter of through hole, DHole=dThermocouple wire+dGap, dThermocouple wireFor the diameter of high temperature thermoelectric thermo wires, span is 0.1～0.5mm；dGapFor
Assemblage gap, span is 0.15～0.3mm；
(b3) Annular pellet outer surface uses blasting treatment, and roughness is not more than 3.2 μm, and inner surface is also adopted by blasting treatment, slightly
Rugosity is not more than 3.2 μm；Annular pellet outer diameter tolerance is not more than 0.04mm, and id tolerance is not more than 0.04mm, and ovality is little
In 0.01mm.
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that the processing of described step (c) electrically heated rod (3) and insulating barrier (5) comprises the following steps:
(c1) choosing tungsten, molybdenum, tungsten-molybdenum alloy or molybdenum-copper as electrically heated rod material, and be processed into bar-shaped, its one end is
Plane, the other end is spherical end surface, and metal bar overall diameter is D3, a length of L+D3/2, a diameter of D3 of metal bar spherical end surface；
D3=Di2-d23, d23 are assemblage gap and thermal expansion preset clearance, and span is 0.1～0.2mm, and metal bar outer surface is adopted
Processing with glossing, roughness is not more than 3.2 μm；
(c2) carrying out cutting processing from one end of metal bar plane, processing an interspace width is DTungsten gapGap, gap is deep
Degree is L, and bottom gap, a diameter of (0.5 × D is processed in terminationTungsten gap+ 0.2mm) semicircle, DTungsten gap=0.2～0.5mm；
(c3) ZrO is chosen2、HfO2Or Al2O3Or three's mixture is as insulating layer material, it is (D3-that insulating barrier is processed into width
0.05mm), thickness is (DTungsten gap-0.05mm), the flat board of a length of (L-0.1mm), the insulating barrier (5) processed is embedded in into electricity
The gap of heating rod (3) so that both upper ends of insulating barrier (5) and electrically heated rod (3) keep concordant.
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that described step (d) analog fuel element pellet (2) comprises the following steps with the assembling of high temperature thermoelectric thermo wires:
(d1) analog fuel element pellet (2) is embedded in into simulation involucrum (1), a joint analog fuel element pellet is installed every time
(2), diameter D is usedLocationMetal bar as alignment pin, it is ensured that each joint 16 diameter D of analog fuel pelletHoleThe position one of through hole
One is corresponding, DLocation=DHole-0.15mm；
(d2) high temperature thermoelectric thermo wires thermometric end being curved quarter bend, the centerline length of right angle curved segment is LSurvey, LSurvey=DHole-0.5
×dThermocouple wire+0.5×d12；First analog fuel pellet is installed to needing to arrange the height of temperature point, temperature is set at needs and surveys
Two thermocouple wire inlaid hole positions near at Dian, extract alignment pin out and arrange a pair high temperature thermoelectric thermo wires；Save follow-up one
The inlaid hole position of two thermocouple wires at corresponding temperature measuring point on analog fuel pellet, respectively one diameter D of processingHole, deep
0.5×DHoleSemicircle orifice, this joint analog fuel pellet is embedded in into simulation involucrum so that a pair diameter DHole, deep 0.5 × DHoleHalf
The position of circular hole correspondence high temperature thermoelectric thermo wires thermometric end quarter bend, a pair high temperature thermoelectric thermo wires is respectively by two corresponding warm
Thermocouple wire inlaid hole is drawn；Installing follow-up analog fuel pellet the most again, a pair high temperature thermoelectric thermo wires is respectively by correspondence
Two thermocouple wire inlaid holes are drawn；
(d3) from low to high, high temperature thermoelectric thermo wires is installed successively, until all temperature measuring thermocouple silk installations, then pacifies
Fill follow-up residue analog fuel element pellet (2), after the installation of all analog fuel element pellets (2), residue is positioned
Pin is extracted out, completes analog fuel element pellet (2) and the setting-in of high temperature thermoelectric thermo wires.
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that the assembling of described step (e) electrically heated rod (3) comprises the following steps: at analog fuel element pellet (2) and high temperature thermoelectric
After the setting-in of thermo wires completes, electrically heated rod (3) is embedded in the cavity into analog fuel element pellet (2) inside so that electrical heating
Rod (3) is concordant with the upper end of analog fuel element pellet (2), simulation involucrum (1) three.
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that the filling of described step (f) noble gas comprises the following steps:
(f1) use welding manner by electrically heated rod (3) analog fuel element pellet (2), simulation involucrum (1) three's common end
Two ends seal, only reserve injecting hole at the other end；
(f2) injecting special noble gas from injecting hole, the purity injecting noble gas is not less than 95%；
(f3) after special noble gas has injected, by welding manner, injecting hole is sealed, complete noble gas and fill.
The assembly technology of a kind of electric heater unit simulating nuclear reactor fuel rod the most according to claim 3, its feature
It is that the assembling of described step (g) external wall temperature thermocouple (7) comprises the following steps:
(g1) on the premise of meeting certainty of measurement demand and capacity of resisting disturbance, take according to thermocouple heat resistance and thermometric demand
Value, selects the armoured thermocouple that diameter is minimum, a diameter of d of armoured thermocoupleThermocouple, dThermocoupleSpan be 0.5～3mm；
(g2) need to arrange the position of temperature point, armoured thermocouple thermometric end is being touched with measured point, keep armouring heat
Armoured thermocouple thermometric end, away from testee, by electric pulse welding manner, is welded by galvanic couple remainder with measured point
Get up.
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| CN107945895A (en) * | 2017-06-19 | 2018-04-20 | 重庆大学 | A kind of non-homogeneous electrically heated nuclear fuel simulation rod |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3988565A (en) * | 1973-06-11 | 1976-10-26 | Varian Associates | Nuclear reactor fuel rod thermal simulator |
| US20070201608A1 (en) * | 2006-02-27 | 2007-08-30 | Areva Np Gmbh | Method for testing a fuel rod cladding tube and associated device |
| CN102539083A (en) * | 2012-02-07 | 2012-07-04 | 中国核动力研究设计院 | Krypton-85 (Kr-85) leakage detection method for detecting damage of fuel assembly or fuel rod |
| CN202350992U (en) * | 2011-12-20 | 2012-07-25 | 中国核动力研究设计院 | Device for section helium spectrum leakage detecting for power reactor irradiated fuel rod |
| US20150323390A1 (en) * | 2012-10-17 | 2015-11-12 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Rod thermometer device for detecting a temperature, use for the electrical simulation of nuclear fuel rods |
-
2016
- 2016-09-21 CN CN201610838185.2A patent/CN106328226B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3988565A (en) * | 1973-06-11 | 1976-10-26 | Varian Associates | Nuclear reactor fuel rod thermal simulator |
| US20070201608A1 (en) * | 2006-02-27 | 2007-08-30 | Areva Np Gmbh | Method for testing a fuel rod cladding tube and associated device |
| CN202350992U (en) * | 2011-12-20 | 2012-07-25 | 中国核动力研究设计院 | Device for section helium spectrum leakage detecting for power reactor irradiated fuel rod |
| CN102539083A (en) * | 2012-02-07 | 2012-07-04 | 中国核动力研究设计院 | Krypton-85 (Kr-85) leakage detection method for detecting damage of fuel assembly or fuel rod |
| US20150323390A1 (en) * | 2012-10-17 | 2015-11-12 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Rod thermometer device for detecting a temperature, use for the electrical simulation of nuclear fuel rods |
Cited By (19)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107945895A (en) * | 2017-06-19 | 2018-04-20 | 重庆大学 | A kind of non-homogeneous electrically heated nuclear fuel simulation rod |
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| CN110110340A (en) * | 2018-02-01 | 2019-08-09 | 国家电投集团科学技术研究院有限公司 | The tracking and system of reactor three-dimensional micromodule information |
| CN109243641A (en) * | 2018-10-18 | 2019-01-18 | 中国核动力研究设计院 | Reactor pressure vessel for presurized water reactor loss of-coolant accident (LOCA) tests analogue body |
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| CN109243641B (en) * | 2018-10-18 | 2022-04-22 | 中国核动力研究设计院 | Reactor pressure vessel experiment simulator for loss of coolant accident of pressurized water reactor |
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| CN110867263A (en) * | 2019-11-07 | 2020-03-06 | 西安交通大学 | Experimental device and method for researching failure behavior of fuel element in severe accident of nuclear reactor |
| CN110867263B (en) * | 2019-11-07 | 2021-06-11 | 西安交通大学 | Experimental device and method for researching failure behavior of fuel element in severe accident of nuclear reactor |
| CN111477364A (en) * | 2020-02-27 | 2020-07-31 | 中国原子能科学研究院 | Nuclear reactor assembly |
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| CN115101224A (en) * | 2022-04-11 | 2022-09-23 | 国家电投集团科学技术研究院有限公司 | Electric heating simulated fuel rod |
| CN115101224B (en) * | 2022-04-11 | 2024-09-06 | 国家电投集团科学技术研究院有限公司 | Electric heating simulated fuel rod |
| CN117807777A (en) * | 2023-12-27 | 2024-04-02 | 东北电力大学 | Test piece design method for realizing axial non-uniform heating of nuclear reactor fuel rod |
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