CN105225709B - The reactor core electrical heating elements method for designing of Natural Circulation and forced circulation circuit system - Google Patents
The reactor core electrical heating elements method for designing of Natural Circulation and forced circulation circuit system Download PDFInfo
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- CN105225709B CN105225709B CN201510531954.XA CN201510531954A CN105225709B CN 105225709 B CN105225709 B CN 105225709B CN 201510531954 A CN201510531954 A CN 201510531954A CN 105225709 B CN105225709 B CN 105225709B
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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
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Abstract
The invention discloses a kind of Natural Circulation and the reactor core electric heating system method for designing of forced circulation circuit system, the design of single electrical heating elements, the simulation of a box fuel assembly and structure and the assembling of fuel assembly analogue body in including reactor core analogue body, the method is according to Natural Circulation and the design parameter and functional requirement of forced circulation experimental loop, the hydraulics core heat release of accurate simulation prototype, experimental data can reflect the correlation properties of reactor prototype, to reach the purpose of learning prototype hydraulic characteristic.The method makes experimental provision be easier to realize using drop altitude simulation；Runner physical dimension is consistent with prototype, reduces flowing distortion；One box fuel assembly analogue body is divided into four areas, is connected to form series circuit from beginning to end, increase its resistance, the matching of electric current and voltage when realizing direct current electrical heating, it is possible to increase the security reliability of passive residual heat removal system design, with construction value very high.
Description
Technical field
Returned the invention belongs to the design field of pressurized water reactor core analogue body, more particularly to a kind of Natural Circulation and forced circulation
The reactor core electrical heating elements method for designing of road system.
Background technology
The safe and reliable of passive residual heat removal system design needs the corresponding experimental study of income, anti-for current power station
Answer heap, its geometric scale and flow scale are very big, and cost is higher, it is impossible to realize the experimental study of prototype scale, it is necessary to
Carry out model simplification.Whether rationally modelling, determines that can experimental data reflect the correlation properties of reactor prototype.Only
When flow of fluid correctly simulates prototype in model, experimental data just has engineering use value and meaning.
To the key that reactor core is designed needed on a model for smaller geometric scale, realize the hydraulics to prototype
Simulation and the simulation of core heat release, to reach the purpose of learning prototype hydraulic characteristic.When reducing flowing distortion, solving direct current electrical heating
The matching of electric current and voltage, make device be easier to realize be reactor core electrical heating elements design technical barrier.
In consideration of it, being necessary to provide a kind of reactor core electrical heating elements for Natural Circulation and forced circulation circuit system
Method for designing.
The content of the invention
The purpose of the embodiment of the present invention is by using the theory of similarity, with AFA3G as prototype, there is provided a kind of Natural Circulation
And the method for designing of the reactor core electrical heating elements of forced circulation circuit system, it is therefore an objective in a model for smaller geometric scale
On, hydraulic analogy and core the heat release simulation to prototype are realized, to reach the purpose of learning prototype hydraulic characteristic.
The present invention is achieved in that a kind of setting for the reactor core electrical heating elements of Natural Circulation and forced circulation circuit system
Meter method includes the design of single electrical heating elements, the simulation of a box fuel assembly and fuel assembly simulation in reactor core analogue body
The method for designing root of the reactor core electrical heating elements of the structure and assembly method of body, the Natural Circulation and forced circulation circuit system
According to Natural Circulation and the design parameter and functional requirement of forced circulation experimental loop, mode of heating, the list of electrical heating elements are determined
The structure and assembly method of the design parameter of root heating element heater and a box fuel assembly analogue body.
Further, it is simulated by prototype of AFA3G, the Natural Circulation primary Ioops correlation where reactor core electrical heating elements sets
Counting parameter is：
Design pressure：17.2MPa
Operating pressure：15.5MPa
Design temperature：360℃
Maximum operating temperature：320℃
Reactor core analogue body peak power：1000kW.
Further, electrical heating elements using stainless steel tube as heating element heater, using grid spacer fixed by electrical heating elements,
Grid spacer is intended using the grid spacer in prototype, and the upper and lower side of electrical heating elements is connected with copper coin, copper coin respectively with power supply
Both positive and negative polarity is connected, and the mode of heating of electrical heating elements uses direct current electrical heating, and electrical heating elements are repeatable to be utilized.
Further, the design height of single fuel rod is than choosing 1:The a length of 4.0m of 4, AFA3G fuel rods, using direct current plus
The stainless steel tube analog fuel rod core heat release of heat 1.0m long, the specification of stainless steel tube is, its external diameter and FA3G
Fuel rod is identical, with oneCopper rod connection stainless steel tube one end and positive source, with anotherCopper rod connection not
The other end and power cathode of rust steel pipe, connected mode are welded using argentalium.
Further, the structure and assembling mode of a box fuel assembly analogue body are used and for a case assembly to be divided into four areas, and
Connect this four areas, specific way is：The upper end in the firstth area and positive source are connected, the lower end in the first area lower end and the secondth area
Be connected, the upper end in the second area upper end and the 3rd area is connected, and the lower end in the 3rd area lower end and the 4th area is connected, the upper end in the 4th area and
Power cathode is connected, and is isolated with ceramic rod between Qu Yuqu, and runner physical dimension is identical with AFA3G fuel assemblies.
The present invention improves the variation of the reliability and npp safety system of the measure of beyond design basis accident setting,
With construction value very high.
Brief description of the drawings
Fig. 1 is single electrical heating elements design drawing provided in an embodiment of the present invention；
Fig. 2 is electrical heating elements design total figure provided in an embodiment of the present invention；
Fig. 3 is electrical heating elements design total figure top view provided in an embodiment of the present invention；
Fig. 4 is the A-A views of Fig. 3 provided in an embodiment of the present invention；
Fig. 5 is the B-B views of Fig. 2 provided in an embodiment of the present invention.
In figure：1- bolts；2- nuts；3- packing rings；The upper copper bars of 4-；5- copper billets；6- ceramic rods；7- stainless steel tubes；Copper under 8-
Rod；Copper bar under 9-；10- connects copper coin；11 ceramic blocks；12- ceramic blocks；13- nuts；14- packing rings；15- screws；The upper copper rods of 16-.
Specific embodiment
In order to make the purpose , technical scheme and advantage of the present invention be clearer, with reference to embodiments, book is sent out
It is bright to be further elaborated.It should be appreciated that the specific embodiments described herein are merely illustrative of the present invention, and without
It is of the invention in limiting.
For there is 157 box fuel assemblies in prototype (ACPR1000), this reactor core intends one box fuel assembly main analog of simulation
Core heat release and drag characteristic.Specific simulation implementation process is as follows：
1. core heat release form simulation
Electrical heating elements are using stainless steel tube as heating element heater.The mode of heating of electrical heating elements is added using direct current
Heat, each laboratory person has large-sized DC power supply, and it provides the ability of high current that can be fine-tuned, without needing to reconfigure phase
Powered-down source, and the repeatable utilization of electrical heating elements, when heating element heater quantity is a lot, this kind of mode of heating advantage is more convex
It is aobvious.
2. the design of single fuel rod
As shown in figure 1, according to the simulation of reactor core, the design height of single fuel rod is than choosing 1:4.AFA3G fuel rods are long
About 4.0m, the design is using the stainless steel tube of direct current electrical heating 1.0m long come analog fuel rod core heat release.The rule of stainless steel tube
Lattice are, its external diameter is identical with FA3G fuel rods, thus can be by controlling direct current heating amount come real
The simulation of existing nuclear fuel rod surface thermal load.With oneCopper rod 16 connection stainless steel tube 7 one end and positive source, use
AnotherLower copper rod 8 connect stainless steel tube 7 the other end and power cathode, its connected mode using argentalium weld.
The resistance of nuclear fuel element analogue body is calculated by the following method：
Reactor core out temperature is respectively tin=280 DEG C and tout=320 DEG C, takes fluid mean temperature then
tf,av=(tout+tin)/2=(280+320)/2=300 DEG C (1)
The sectional area of stainless steel tube is
If wall mean temperature is so that higher than the 50 DEG C of calculating of fluid mean temperature, heating tube wall surface temperature is according to 300+50=
350 DEG C of considerations, at such a temperature, its resistivity is：
ρ=0.775+0.00055tw,av=0.775+0.00055 × 350=0.9675 Ω mm2/m (3)
The each resistance of heating tube：
R=ρ L/Sw=0.9675 × 1.0/23.58=0.041 Ω (4)
3. a box fuel assembly
There are 157 box fuel assemblies in prototype, one box fuel assembly of simulation is intended in this experiment.In AFA3G fuel assemblies, nuclear fuel
The arrangement mode of rod is 17 × 17, it is considered to control drive mechanism, it is so much that its nuclear fuel rod does not have 17 × 17.If the design
In take 17 × 17 arrangement, with direct current electrical heating stainless steel tube simulate core heat release, and height ratio take 1:4, that there will be analogue body
Resistance is too small, it is impossible to realize matching for its electric current and voltage.To solve this problem, used a case assembly subregion in this example
The mode of series connection.
Electrical heating elements design total figure top view as shown in Figure 3, using by a case assembly be divided into four areas (I, II, III,
IV), each region is 8 × 8 arrangements, connects this four areas to realize increase resistance (resistance is about original 16 times).Specifically
Way is：The upper end in the first area I and positive source are connected, and the lower end in the lower end of the firstth area I and the second area II is connected, in the second area II
End and the upper end in the 3rd area III are connected, and the lower end in the lower end of the 3rd area III and the 4th area IV is connected, the upper end in the 4th area IV and power supply
Negative pole is connected.Isolated with ceramic rod 6 between Qu Yuqu, and runner physical dimension is identical with AFA3G fuel assemblies, so reduces stream
The distortion of dynamic characteristic.
The resistance of one box fuel assembly analogue body is about：
(wherein R=ρ L/Sw=0.041 Ω is the resistance of single electrical heating elements)
According to analog parameter power：Q=1MW, calculates
Electric current：I=19754.59A
Voltage：U=50.62V.
4. fuel assembly analogue body assembling
The fuel assembly analogue body as shown in Fig. 2, Fig. 3, Fig. 4, Fig. 5 includes I, II, III, IV 4 regions, including bolt 1；
Nut 2；Packing ring 3；Upper copper bar 4；Copper billet 5；Ceramic rod 6；Stainless steel tube 7；Lower copper rod 8；Lower copper bar 9；Connection copper coin 10；Ceramic block
11；Ceramic block 12；Nut 13；Packing ring 14；Screw 15；Upper copper rod 16.
As shown in figure 3, described I, II, III, IVth area by upper copper bar 4, upper copper rod 16, lower copper rod 8, stainless steel tube 7, under
Copper bar 9 is constituted, and has 64 stainless steel tubes 7 per area, is arranged by 8 × 8 modes, and the upper end of stainless steel tube 7 is connected with upper copper rod 16, upper copper
Rod 16 and then it is connected with upper copper bar 4, the lower end of stainless steel tube 7 is connected with lower copper rod 8, lower copper rod 8 and then is connected with lower copper bar 9, on
Connection is stated to be connected using silver brazing.Connected using connection copper coin 10 between Qu Yuqu, described the Ith area lower end and the IIth area
Lower end same connection copper coin 10 is connected, and the upper end in the IIth area upper end and the IIIth area connects with same connection copper coin 10, and the IIIth
The lower end in area lower end and the IVth area is connected with same copper coin 10, upper copper bar 4 be connected copper coin 10 and lower copper bar 9 and be connected copper coin 10
Between connected by nut 13, packing ring 14, screw 15, it is and then described I, II, III, IV area's fuel tandem compound is integral.
As shown in Fig. 2 the Ith described area upper end is connected by bolt 1, nut 2, packing ring 3 with copper billet 5, and then and power supply
Positive pole is connected；The IVth described area upper end is connected with copper billet 5, and then is connected with power cathode by bolt 1, nut 2, packing ring 3,
Complete the connection of fuel assembly and power supply.
As shown in Figure 4, Figure 5, insulated with ceramic block 11,12 and ceramic rod 6 between described Qu Yuqu, the two ends of ceramic rod 6
Respectively insertion ceramic block 11, in 12 preformed holes, coordinated apart from gap with upper and lower copper bar using the length of ceramic rod 6, by combination after 4
Cross gap area between group ceramic rod 6 and ceramic block 11,12 insert districts and area.Recycle ceramic block 11,12 and upper copper bar 4,
Lower copper bar 9 coordinates step that ceramic block 11,12 and ceramic rod 6 is spacing, completes the assembling of a box fuel assembly.
Presently preferred embodiments of the present invention is the foregoing is only, is not intended to limit the invention, it is all in essence of the invention
Any modification, equivalent and improvement made within god and principle etc., should be included within the scope of the present invention.
Claims (4)
1. a kind of method for designing of the reactor core electrical heating elements of Natural Circulation and forced circulation circuit system, it is characterised in that bag
Include the structure of the design of single electrical heating elements, the simulation of a box fuel assembly and fuel assembly analogue body in reactor core analogue body
And assembly method, the method for designing of the reactor core electrical heating elements of the Natural Circulation and forced circulation circuit system according to following naturally
Ring and the design parameter and functional requirement of forced circulation experimental loop, determine the mode of heating of electrical heating elements, single heating unit
The structure and assembly method of the design parameter of part and a box fuel assembly analogue body；
It is simulated by prototype of AFA3G, the Natural Circulation primary Ioops relevant design parameter where reactor core electrical heating elements is：
Design pressure：17.2MPa
Operating pressure：15.5MPa
Design temperature：360℃
Maximum operating temperature：320℃
Reactor core analogue body peak power：1000kW.
2. the method for designing of the reactor core electrical heating elements of Natural Circulation as claimed in claim 1 and forced circulation circuit system,
Characterized in that, electrical heating elements use stainless steel tube as heating element heater, electrical heating elements are fixed using grid spacer, positioning
Screen work is intended using the grid spacer in prototype, and the upper and lower side of electrical heating elements is connected with copper coin, and copper coin is positive and negative with power supply respectively
Extremely it is connected, the mode of heating of electrical heating elements uses direct current electrical heating, and electrical heating elements are repeatable to be utilized.
3. the method for designing of the reactor core electrical heating elements of Natural Circulation as claimed in claim 1 and forced circulation circuit system,
Characterized in that, the design height of single fuel rod is than choosing 1:4, AFA3G fuel rods a length of 4.0m, it is long using direct current electrical heating
The stainless steel tube analog fuel rod core heat release of 1.0m, the specification of stainless steel tube is 9.5 × 0.87mm of φ, its external diameter and FA3G fuel
Rod is identical, and one end and the positive source of stainless steel tube are connected with a copper rod of φ 5, connects stainless with another copper rod of φ 5
The other end and power cathode of steel pipe, connected mode are welded using argentalium.
4. the method for designing of the reactor core electrical heating elements of Natural Circulation as claimed in claim 1 and forced circulation circuit system,
Characterized in that, the structure and assembling mode of a box fuel assembly analogue body are used is divided into four areas by a case assembly, and connect
This four areas, specific way is：The upper end in the firstth area and positive source are connected, the lower end phase in the first area lower end and the secondth area
Connection, the upper end in the second area upper end and the 3rd area is connected, and the lower end in the 3rd area lower end and the 4th area is connected, the upper end in the 4th area and electricity
Source negative pole is connected, and is isolated with ceramic rod between Qu Yuqu, and runner physical dimension is identical with AFA3G fuel assemblies.
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| CN201510531954.XA CN105225709B (en) | 2015-08-26 | 2015-08-26 | The reactor core electrical heating elements method for designing of Natural Circulation and forced circulation circuit system |
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| CN105513653A (en) * | 2016-02-01 | 2016-04-20 | 西南石油大学 | Degassing device for natural circulation and forced circulation experiment loops and degassing method thereof |
| CN106653111B (en) * | 2016-09-21 | 2017-12-15 | 中国核动力研究设计院 | A kind of new pressure compensation structure for being used for electrical heating simulating piece under hyperbaric environment |
| CN106297918B (en) * | 2016-10-31 | 2018-01-30 | 中国核动力研究设计院 | A kind of output control device of overcritical electrical heating simulation transient state core heat release |
| CN107527664A (en) * | 2017-07-31 | 2017-12-29 | 中国核动力研究设计院 | A kind of method for simulating nuclear reactor fluid natural circulation stream dynamic characteristic |
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| WO2012156474A1 (en) * | 2011-05-18 | 2012-11-22 | Commissariat à l'énergie atomique et aux énergies alternatives | Electrical heating device for heating a liquid, method for producing same, and use in the electrical simulation of nuclear fuel rods |
| CN104269196A (en) * | 2014-08-27 | 2015-01-07 | 上海发电设备成套设计研究院 | Device and method for carrying out tests for stimulating environment in high energy pipeline rupture accident in nuclear power plant |
| CN104599728A (en) * | 2015-01-09 | 2015-05-06 | 东南大学 | Device and method for simulating reactor core decay heat of nuclear power station |
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Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| WO2012156474A1 (en) * | 2011-05-18 | 2012-11-22 | Commissariat à l'énergie atomique et aux énergies alternatives | Electrical heating device for heating a liquid, method for producing same, and use in the electrical simulation of nuclear fuel rods |
| CN104269196A (en) * | 2014-08-27 | 2015-01-07 | 上海发电设备成套设计研究院 | Device and method for carrying out tests for stimulating environment in high energy pipeline rupture accident in nuclear power plant |
| CN104599728A (en) * | 2015-01-09 | 2015-05-06 | 东南大学 | Device and method for simulating reactor core decay heat of nuclear power station |
Non-Patent Citations (2)
| Title |
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| AFA3G;陈宝山等;《轻水堆燃料元件》;化学工业出版社;20070630;第353-355页 * |
| AFA3G燃料组件骨架导向管与格架的压力电阻焊工艺研究;刘波等;《核动力工程》;20021031;第23卷(第5期);第70-75页 * |
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