CN103544997A - Positioning grid rack and reactor fuel assembly - Google Patents

Positioning grid rack and reactor fuel assembly Download PDF

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Publication number
CN103544997A
CN103544997A CN201310515646.9A CN201310515646A CN103544997A CN 103544997 A CN103544997 A CN 103544997A CN 201310515646 A CN201310515646 A CN 201310515646A CN 103544997 A CN103544997 A CN 103544997A
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China
Prior art keywords
grid spacer
grill unit
grid
guide vane
wing
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CN201310515646.9A
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CN103544997B (en
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卢志威
李伟才
禹文池
胡海翔
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
China Nuclear Power Engineering Co Ltd
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China General Nuclear Power Corp
China Nuclear Power Technology Research Institute Co Ltd
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    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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Abstract

The invention discloses a positioning grid rack. The positioning grid rack comprises an outer stripe and a plurality of first inner stripes and second inner stripes, wherein the first inner stripes and the second inner stripes are parallel to one another and are arranged at equal intervals; the first inner stripes and the second inner stripes are mutually crossed to form a latticed grating; the grating comprises a plurality of grating units in hollow structures; the outer stripes surround the periphery of the grating and are connected with the first inner stripes and the second inner stripes; the upper edge or/and the lower edge of the outer stripe is/are in a zigzag structure; a tooth portion of the zigzag structure forms a vertical guiding wing; the transverse cross section of each outer stripe is in a periodic bending structure bending towards the grating structure. The guiding wing is vertical and is in a bending structure bending towards the grating structure, thus the defects caused by the bent guiding wing in the prior art are solved, the positioning grid rack is high in strength and high in hooking prevention capability, and the coolant pressure is reduced. Moreover, the invention also discloses a reactor fuel assembly with the positioning grid rack.

Description

Grid spacer and reactor fuel assemblies
Technical field
The present invention relates to a kind of reactor component, relate in particular to a kind of reactor fuel assemblies and grid spacer thereof.
Background technology
The fuel rod of some is arranged (as: 15 * 15 or 17 * 17 etc.) according to certain intervals and is fixed to a branch ofly, is called reactor fuel assemblies, and reactor fuel assemblies is mainly comprised of base, upper bottom nozzle, grid spacer, guide pipe and fuel rod.The time that general reactor fuel assemblies is used 3-5 in nuclear reactor, because it is in persistent erection subfield, need stand washing away of high temperature, high pressure, high flow rate cooling medium, need to bear fission product chemistry effect and complicated mechanical load, so condition of work be very harsh simultaneously.
Water is one of preferred materials making the neutron degradation that produces in nuclear reactor, therefore water is widely used in moderator and the cooling medium of nuclear reactor, with light-water, as the nuclear reactor of moderator and cooling medium, be called as light-water reactor (English: Light Wate-r Reactor, be called for short: LWR), light-water is general water (H namely 2o), light-water reactor is to using water and steam water interface as the nuclear reactor of cooling medium and moderator, is a kind of mode of the peaceful utilization of atomic energy, and the mode that light-water reactor just sets out nuclear fission heat energy in heap can be divided into two kinds of presurized water reactor and boiling-water reactors, with heavy water (D 2o) compare, light-water has cheap remarkable advantage, and its retardation efficiency is also very high in addition, so presurized water reactor and boiling-water reactor are two kinds of heap types that most nuclear power stations adopt in the world at present; The feature of boiling-water reactor is that water vapour is generated electricity without the direct pushing turbine generator of heat exchanger, thereby has prevented the low of the thermal efficiency; Presurized water reactor suppresses boiling with high pressure, light-water is generally added to 100 to 160 standard atmospheric pressures (atm), thereby heat exchanger is kept apart a cooling system (taking out the heat that reactor core produces) and secondary cooling system (being sent to the steam of turbine) completely, thereby utilize the generating of Steam Actuation turbodynamo.
Its principle of work of light-water reactor is mainly, at the reactor core of light-water reactor, there is controlled chain reaction in fuel rod, produce amount of heat, these heats directly promote turbodynamo by transforming, thereby realize the utilization of nuclear energy, as everyone knows, chain reaction meeting in nuclear reactor produces a large amount of harmful radiomaterials, as iodine 131, Ce 137 etc., for fear of these radiomaterials, leak, nuclear reactor is provided with multiple protective layers outward: ground floor, zircaloy shell, radiomaterial in fuel rod contacts with chilled water, in fuel rod outer wrapping one deck zircaloy shell, this zircaloy shell can bear the high temperature of 1200 ℃, the second layer, reactor pressure vessel, this reactor pressure vessel is for accommodating the reactor core of nuclear reactor, during reactor work, can produce huge vapor pressure, so reactor pressure vessel is made by high strength alloy steel, its protective action is, at the zircaloy shell of fuel rod, occurs when damaged, guarantees that radiomaterial can not reveal on a large scale, the 3rd layer, concrete Secure Shell, cover in outside reactor pressure vessel, its Main Function is, after reactor pressure vessel blast or breakage, prevent that a large amount of radiomaterials, radioactive wastewater are leaked to the external world, it is worth mentioning that, the reactor of USSR (Union of Soviet Socialist Republics) Qie Erruo Baily nuclear power station is due to this Secure Shell not, therefore cause easily factory building being blown after reactor blast, thereby cause a large amount of radioactive ashes directly to enter atmosphere, cause the long-time serious nuclear pollution of surrounding environment, form the serious consequence in depopulated zone.
From the above, the fundamental purpose that nuclear reactor is arranged to multilayer proofing is to guarantee that nuclear reactor is blasted etc. after mishap, make the external world that leaks to that radiomaterial in nuclear reactor can be not a large amount of, and guarantee the deciding factor that nuclear reactor is not blasted, control exactly chain reaction speed and temperature in nuclear reactor, therefore the flow control of the light-water of the interior moderator of fuel assembly and cooling medium is just concerning important, therefore the grid spacer of fuel assembly is particularly important with regard to what become for the circulation of light-water, in order to allow light-water pass through, so grid spacer need to form some water stream channels, and simultaneously in order can to support and to locate fuel rod and bearing washing away of high-velocity flow, so grid spacer also must have enough intensity, separately, because fuel assembly has very high lateral flexibility, so the lifting of fuel assembly can only vertically be carried out, prevent excessive lateral deformation, in actual fuel assembly dress discharge process, during due to lifting, between fuel assembly, only has very little spacing, be approximately 1mm, fuel assembly is easy to interfere with fuel assembly in place, interference may cause due to the manufacturing tolerance of the distortion of fuel assembly irradiation and fuel assembly and hanging device, so it is particularly important that the design of grid spacer becomes, grid spacer must have good guide function, can lead to adjacent fuel assembly, make it mutually to pass through, so generally guide vane can be set on grid spacer, the shape of guide vane now, bending angle, the parameters such as intensity can affect the guide function of grid spacer.
China Patent No. CN200580040936.6 discloses the grid spacer of the guide vane with bending, it specifically discloses a kind of pencil support grid for fuel assembly and corresponding assembly, maintenance grid in this patent of invention (, above-mentioned grid spacer) due to cross one another interior band and enclose periphery enclosing (that is: outer band) outside interior band and form, the webbed lattice of cross one another interior band shape are deleted structure, on its China and foreign countries' band, be provided with to the guiding fin every grid internal bend, by this guiding fin fuel limitation assembly two adjacent fuel assembly generation hooks in dress discharge process.But, because the guiding fin of above-mentioned maintenance grid is to the inner bending of grid, make to guide fin and can be in reactor produce projected area on the flow direction of cooling medium, thereby make cooling medium after the grid of flowing through, produce the larger pressure loss, pressure drop is increased, thereby reduced greatly the efficiency of reactor operation; Separately, the guiding fin of above-mentioned maintenance grid also connects a knee wall, when fuel assembly is in dress discharge process, adjacent fuel assembly is easy to bump, because adjacent fuel assembly bumps, thereby it is inner to grid to make to guide the direction of power of collision that fin bears, when this impact force surpasses the power that guiding fin can resist, to make to guide fin to the outside turnover of grid, thereby make fuel assembly generation hook.
Therefore,, in order solving the problems of the technologies described above, to need high, the anti-hook ability of a kind of intensity badly by force and make the little grid spacer of cooling medium pressure drop.
Summary of the invention
The object of the present invention is to provide high, the anti-hook ability of a kind of intensity strong and make the little grid spacer of cooling medium pressure drop.
Another object of the present invention is to provide a kind of reactor fuel assemblies, described reactor fuel assemblies has high, the anti-hook ability of intensity by force and makes the little grid spacer of cooling medium pressure drop.
For achieving the above object, the invention provides a kind of grid spacer, comprise outer band and some the first interior band and the second interior bands, described the first interior band is parallel to each other and equally spaced arrangement, described the second interior band is parallel to each other and equally spaced arrangement, described the first interior band and described the second interior band intersect to form latticed grid mutually, described grid comprises the grill unit of some hollow structures, described outer band encloses peripheral in described grid and is connected with described the first interior band and described the second interior band, wherein, the coboundary of described outer band is or/and lower limb indention structure, the tooth portion of described zigzag structure forms the guide vane that is vertical shape, the lateral cross section of described outer band is the periodic bending structure to grill unit inner bending.
Preferably, form the targeting port being communicated with grill unit between adjacent described guide vane, described guide vane is positioned at the bent area of described bending structure, and described targeting port is positioned at the flat region of described bending structure; Because described guide vane is positioned at the bent area of described bending structure, make guide vane across the bent area of bending structure and there is the bending degree corresponding with this bent area, strengthen greatly the intensity of guide vane, effectively raised the guiding of guide vane, the ability that anti-collision hits anti-hook; Also due to described targeting port, be positioned at the flat region of described bending structure simultaneously, thereby the bent area with respect to guide vane place is spirogyrate, when adjacent fuel assembly is bumped, under the effect of the vertical guide vane of shape, the summit of guide vane can not be embedded in the grill unit of adjacent fuel assembly, thereby has guaranteed the guide effect of guide vane.
Preferably, described guide vane is positioned at adjacent described grill unit junction; Described guide vane is arranged to adjacent described grill unit junction, has strengthened the intensity of grid spacer of the present invention, further avoided the situation of fuel assembly two adjacent fuel assembly generation hooks in dress discharge process to occur.
Preferably, described guide vane interval is positioned at adjacent described grill unit junction; By the adjacent grill unit junction of being arranged at of described guide vane interval, guaranteed the cooling medium exchange between reactor fuel assemblies, guaranteed that grid spacer of the present invention has stronger intensity and anti-hook ability, makes grid spacer of the present invention more practical simultaneously.
Preferably, described the first interior band has and protrudes into first in described grill unit and mix the wing; Described first mixes the performance of mixing that the wing effectively raises grid spacer of the present invention, has further guaranteed carrying out smoothly of nuclear reaction.
Preferably, described first mix the wing and be stretching in described grill unit of the bending of tilting.
Preferably, described the second interior band has and protrudes into second in described grill unit and mix the wing, and described second mixes the performance of mixing that the wing effectively raises grid spacer of the present invention, has further guaranteed carrying out smoothly of nuclear reaction.
Preferably, described second mix the wing and be stretching in described grill unit of the bending of tilting.
Preferably, adjacent described first mix the wing and second and mix the wing corresponding stretching in different grill unit respectively; Guaranteed to only have one to mix the wing in each grill unit, guaranteed that grid spacer of the present invention has higher when mixing performance, also there is stronger anti-hook ability and pressure drop and can obviously not reduce, further guaranteed carrying out smoothly of nuclear reaction.
Preferably, described the first interior band and the mutually orthogonal formation of described the second interior band are foursquare latticed described grid.
A kind of reactor fuel assemblies provided by the invention, comprise bottom nozzle, upper base, grid spacer, guide pipe and fuel rod, described fuel rod and guide pipe are inserted in respectively in described grid spacer, the upper end of described grid spacer is connected with described upper base coupling, the lower end of described grid spacer is connected with described bottom nozzle coupling, described grid spacer comprises outer band and some the first interior band and the second interior bands, described the first interior band is parallel to each other and equally spaced arrangement, described the second interior band is parallel to each other and equally spaced arrangement, described the first interior band and described the second interior band intersect to form latticed grid mutually, described grid comprises the grill unit of some hollow structures, described outer band encloses peripheral in described grid and is connected with described the first interior band and the second interior band, wherein, the coboundary of described outer band is or/and lower limb indention structure, the tooth portion of described zigzag structure forms the guide vane that is vertical shape, the lateral cross section of described outer band is the periodic bending structure to grill unit inner bending.
Compared with prior art, because the coboundary of the outer band of grid spacer of the present invention and reactor fuel assemblies is or/and lower limb indention structure, the tooth portion of described zigzag structure forms the guide vane that is vertical shape, the lateral cross section of described outer band is the periodic bending structure to grill unit inner bending, the lateral cross section that is vertical shape and outer band due to the guide vane of grid spacer of the present invention and reactor fuel assemblies is the bending structure to grill unit inner bending, and the guiding fin intensity of comparing existing bending is larger, when fuel assembly is in dress discharge process, adjacent fuel assembly directly leads by being the guide vane of vertical shape, effectively avoided hook mutual between fuel assembly and bumped, even and when bumping, also because the vertical shape of its guide vane and the lateral cross section of outer band are bending structure, the direction that makes the power of collision that guide vane bears is vertical direction and can be inner to grill unit, even if therefore the guide vane of grid spacer of the present invention and reactor fuel assemblies is also difficult for occurring to destroy and distortion when bumping, make grid spacer of the present invention there is stronger anti-hook ability, separately, on the flow direction of the guide vane of grid spacer of the present invention and reactor fuel assemblies cooling medium in reactor, do not produce projected area, therefore make cooling medium pressure drop after flow through grid spacer of the present invention and reactor fuel assemblies little, therefore, high, the anti-hook ability of grid spacer of the present invention and reactor fuel assemblies intensity is strong and make cooling medium pressure drop little.
Accompanying drawing explanation
Fig. 1 is the planar structure schematic diagram of grid spacer of the present invention.
Fig. 2 is the structural representation of continuous three grill unit of grid spacer of the present invention.
Fig. 3 is the planar structure schematic diagram of Fig. 2.
Fig. 4 is the sectional view along A-A line in Fig. 3.
Fig. 5 is the schematic diagram that adjacent fuel assembly leads.
Fig. 6 is that grid spacer of the present invention has first and mixes the structural representation that the wing and second is mixed continuous three grill unit of the wing.
Fig. 7 is the planar structure schematic diagram of Fig. 6.
Fig. 8 is the structural representation of reactor fuel assemblies of the present invention.
Embodiment
With reference now to accompanying drawing, describe embodiments of the invention, in accompanying drawing, similarly element numbers represents similar element.
As Figure 1-Figure 4, for achieving the above object, the invention provides a kind of grid spacer, comprise outer band 10 and some the first interior band 20 and the second interior bands 30, described the first interior band 20 is parallel to each other and equally spaced arrangement, described the second interior band 30 is parallel to each other and equally spaced arrangement, described the first interior band 20 intersects to form latticed grid mutually with described the second interior band 30, described grid comprises the grill unit 40 of some hollow structures, described outer band 10 encloses peripheral in described grid and is connected with described the first interior band 20 and the second interior band 30, wherein, the coboundary 11 of described outer band 10 is or/and lower limb 12 indention structures, the tooth portion of described zigzag structure forms the guide vane 13 that is vertical shape, the lateral cross section of described outer band 10 is the periodic bending structure 15 to grill unit 40 inner bendings, Fig. 4 is the horizontal sectional drawing view of grill unit 40, particularly, the coboundary 11 of described outer band 10 is indention structure separately, the lower limb 12 of described outer band 10 is indention structure separately also, the coboundary 11 of certain described outer band 10 and lower limb 12 be indention structure simultaneously, described zigzag structure is specifically positioned on the coboundary 11 of described outer band 10, still be positioned on the lower limb 12 of described outer band 10, still be positioned on the coboundary 11 and lower limb 12 of described outer band 10 simultaneously, according to actual conditions needs, those skilled in the art can make one's options without any performing creative labour, therefore, at this, be not described in detail.Below in conjunction with Fig. 3-Fig. 7, grid spacer of the present invention is described in further detail, specific as follows:
Continuation, in conjunction with shown in Fig. 3 and Fig. 4, forms the targeting port 14 being communicated with grill unit between adjacent described guide vane 13, described guide vane 13 is positioned at the bent area 15a of described bending structure 15, and described targeting port 14 is positioned at the flat region 15b of described bending structure 15; Have the outer band 10 that lateral cross section is the periodic bending structure 15 to grill unit 40 inner bendings, this bending structure 15 is improved outer band 10 intensity greatly; Because described guide vane 13 is positioned at the bent area 15a of described bending structure 15, make guide vane 13 across the bent area 15a of bending structure 15 and there is the bending degree corresponding with this bent area 15a, strengthen greatly the intensity of guide vane 13, effectively raised the guiding of guide vane 13, the ability that anti-collision hits anti-hook; Also due to described targeting port 14, be positioned at the flat region 15b of described bending structure 15 simultaneously, thereby the bent area 15a with respect to guide vane 13 places is spirogyrate, when adjacent fuel assembly is bumped, under the effect of the vertical guide vane 13 of shape, the summit of guide vane 13 can not be embedded in the grill unit 40 of adjacent fuel assembly, thereby has guaranteed the guide effect of guide vane 13.
Particularly, as shown in Figure 5, the schematic diagram of adjacent fuel assembly guiding, in dress discharge process, when the fuel assembly that is positioned at Fig. 5 top moves downward (arrow F direction as shown in Figure 5) with respect to the fuel assembly of the below being positioned, now because the existence of guide vane 13 can force two adjacent fuel assemblies to produce the mutual movement locus away from the other side, thereby effectively avoid two adjacent fuel assembly generation hooks.Because the flat region 15b of described bending structure 15 is spirogyrate with respect to the bent area 15a at guide vane 13 places, be that flat region 15b is also spirogyrate with respect to the grill unit 40 at its place, as shown in Figure 5, height D is that this spirogyrate is with respect to the height of grill unit evagination, this height D is also the degree of depth of the bent area 15a of outer band 10, therefore guaranteed the existence of this spirogyrate, height D is always on the occasion of (inciting somebody to action, in grill unit 40, be set as negative value), formation just because of the flat region 15b of this evagination, even if make when two fuel assemblies bump in dress discharge process, under effect due to the guide vane 13 at vertical shape, the summit 13a of guide vane 13 can not be embedded in the grill unit 40 of adjacent fuel assembly, thereby further guaranteed the guide effect of guide vane 13.
Preferably, described guide vane 13 is positioned at adjacent described grill unit junction 23; Described guide vane is arranged to adjacent described grill unit junction, has strengthened the intensity of grid spacer of the present invention, further avoided the situation of fuel assembly two adjacent fuel assembly generation hooks in dress discharge process to occur.
Preferably, described guide vane interval be positioned at adjacent described grill unit junction; By the adjacent grill unit junction of being arranged at of described guide vane interval, guaranteed the cooling medium exchange between reactor fuel assemblies, guaranteed that grid spacer of the present invention has stronger intensity and anti-hook ability, makes grid spacer of the present invention more practical simultaneously.
Continuation is in conjunction with shown in Fig. 6 and Fig. 7, and described the first interior band 20 has and protrudes into first in described grill unit 40 and mix the wing 21; Described first mixes the performance of mixing that the wing 21 effectively raises grid spacer of the present invention, has further guaranteed carrying out smoothly of nuclear reaction; Particularly, described first mix the wing 21 and be stretching in described grill unit 40 of the bending of tilting.
Continuation is in conjunction with shown in Fig. 6 and Fig. 7, described the second interior band 40 has and protrudes into second in described grill unit 40 and mix the wing 31, described second mixes the performance of mixing that the wing 31 effectively raises grid spacer of the present invention, has further guaranteed carrying out smoothly of nuclear reaction; Particularly, described second mix the wing 40 and be stretching in described grill unit 40 of the bending of tilting.
Preferably, adjacent described first mixes the wing 21 and second mixes the wing 31 corresponding stretching in different grill unit 40 respectively; Guaranteed to only have one to mix the wing in each grill unit 40, guaranteed that grid spacer of the present invention has higher when mixing performance, also there is stronger anti-hook ability and pressure drop and can obviously not reduce, further guaranteed carrying out smoothly of nuclear reaction; Certainly, according to actual conditions, each grill unit 40 can arrange a plurality of first and mix the wing 21 or/and second mix the wing 31; Each grill unit 40 arranges first and mixes the quantity that the wing 21 and second is mixed the wing 31, and those skilled in the art, on the basis of technical scheme provided by the present invention, according to the demand of actual conditions, can make decision without any performing creative labour.
Preferably, described the first interior band 20 is foursquare latticed described grid with the mutually orthogonal formation of described the second interior band 30.
Continuation is in conjunction with shown in Fig. 8, the invention provides the reactor fuel assemblies 1 with above-mentioned grid spacer 100, comprise grid spacer 100, bottom nozzle 200, upper base 300, guide pipe 400 and fuel rod 500, described fuel rod 500 and guide pipe 400 are inserted in respectively in described grid spacer 100, the upper end of described grid spacer 100 is connected with described upper base 300 couplings, the lower end of described grid spacer 100 is connected with described bottom nozzle 200 couplings, cooling medium is shown in the interior flow direction arrows U of grid spacer 100, i.e. vertical direction from the bottom up.
Shown in Fig. 7 and Fig. 8, in Fig. 7, the direction shown in arrow T is the ANALYSIS OF COOLANT FLOW direction between adjacent reactor fuel assemblies 1, be that the direction shown in arrow T is horizontal direction, what technical scheme of the present invention was related first mixes the wing 21 and second and mixes the wing 31 and can make the ANALYSIS OF COOLANT FLOW between reactor fuel assemblies 1 more smooth, also increased the effect of mixing between reactor fuel assemblies 1 simultaneously, by first, mix the flow direction that the wing 21 and the second layout of mixing the wing 31 have maintained the cooling medium between reactor fuel assemblies 1, realized the cooling medium exchange between reactor fuel assemblies 1, further guaranteed carrying out smoothly of nuclear reaction.
Shown in Fig. 1-Fig. 8, because grid spacer 100 of the present invention and the coboundary 11 of outer band 10 of reactor fuel assemblies 1 with this grid spacer 100 are or/and lower limb 12 indention structures, the tooth portion of described zigzag structure forms the guide vane 13 that is vertical shape, the lateral cross section of described outer band 10 is the periodic bending structure 15 to grill unit 40 inner bendings, because grid spacer 100 of the present invention and the guide vane 13 with the reactor fuel assemblies 1 of this grid spacer 100 are the bending structures 15 that the lateral cross section of vertical shape and outer band 10 is 40 bendings in grill unit, the guiding fin intensity of comparing existing bending is larger, when fuel assembly is in dress discharge process, adjacent fuel assembly directly leads by being the guide vane 13 of vertical shape, effectively avoided hook mutual between fuel assembly and bumped, even and when bumping, also because the vertical shape of its guide vane 13 and the lateral cross section of outer band 10 are bending structure 15, the direction that makes the power of collision that guide vane 13 bears is vertical direction and can be to grill unit 40 inside, therefore even if grid spacer 100 of the present invention and the guide vane 13 with the reactor fuel assemblies 1 of this grid spacer 100 are also difficult for occurring to destroy and distortion when bumping, the reactor fuel assemblies 1 that makes grid spacer 100 of the present invention and have this grid spacer 100 has stronger anti-hook ability: another, grid spacer 100 of the present invention and have on the flow direction of guide vane 13 cooling medium in reactor of this grid spacer 100 and do not produce projected area, therefore make cooling medium flow through grid spacer 100 of the present invention and to have the rear pressure drop of this grid spacer 100 little, therefore, grid spacer 100 of the present invention and to have high, the anti-hook ability of reactor fuel assemblies 1 intensity of this grid spacer 100 strong and make cooling medium pressure drop little.
Separately, the flow direction of cooling medium in structure, principle of work and the nuclear reaction of bottom nozzle 200 involved in the present invention, upper base 300, guide pipe 400 and fuel rod 500, is well known to those of ordinary skill in the art, at this, is no longer described in detail.
Above disclosed is only the preferred embodiments of the present invention, certainly can not limit with this interest field of the present invention, and the equivalent variations of therefore doing according to the present patent application the scope of the claims, still belongs to the scope that the present invention is contained.

Claims (10)

1. a grid spacer, comprise outer band and some the first interior band and the second interior bands, described the first interior band is parallel to each other and equally spaced arrangement, described the second interior band is parallel to each other and equally spaced arrangement, described the first interior band and described the second interior band intersect to form latticed grid mutually, described grid comprises the grill unit of some hollow structures, described outer band encloses peripheral in described grid and is connected with described the first interior band and described the second interior band, it is characterized in that: the coboundary of described outer band is or/and lower limb indention structure, the tooth portion of described zigzag structure forms the guide vane that is vertical shape, the lateral cross section of described outer band is the periodic bending structure to grill unit inner bending.
2. grid spacer as claimed in claim 1, is characterized in that: between adjacent described guide vane, form the targeting port being communicated with grill unit, described guide vane is positioned at the bent area of described bending structure, and described targeting port is positioned at the flat region of described bending structure.
3. grid spacer as claimed in claim 1, is characterized in that: described guide vane is positioned at adjacent described grill unit junction.
4. grid spacer as claimed in claim 1, is characterized in that: described guide vane interval be positioned at adjacent described grill unit junction.
5. grid spacer as claimed in claim 1, is characterized in that: described the first interior band has and protrudes into first in described grill unit and mix the wing.
6. grid spacer as claimed in claim 5, is characterized in that: described first mixes the wing is to tilt stretching in described grill unit of bending.
7. grid spacer as claimed in claim 5, is characterized in that: described the second interior band has and protrudes into second in described grill unit and mix the wing.
8. grid spacer as claimed in claim 7, is characterized in that: described second mixes the wing is to tilt stretching in described grill unit of bending.
9. grid spacer as claimed in claim 7, is characterized in that: adjacent described first mixes the wing and second mixes the wing corresponding stretching in different grill unit respectively.
10. a reactor fuel assemblies, comprise bottom nozzle, upper base, grid spacer, guide pipe and fuel rod, described fuel rod and guide pipe are inserted in respectively in described grid spacer, the upper end of described grid spacer is connected with described upper base coupling, the lower end of described grid spacer is connected with described bottom nozzle coupling, it is characterized in that: described grid spacer is as described in claim 1-9 any one.
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Cited By (13)

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CN104036830A (en) * 2014-06-20 2014-09-10 中科华核电技术研究院有限公司 Low pressure drop holding grid and fuel component with holding grid
WO2016086810A1 (en) * 2014-12-05 2016-06-09 中广核研究院有限公司 Fairing-type guiding vane structure and stirring-mixing lattice
CN105869681A (en) * 2016-05-26 2016-08-17 中广核研究院有限公司 Fuel assembly and outer-strip-free positioning grid frame and strips thereof
WO2016127527A1 (en) * 2015-02-13 2016-08-18 中国科学院近代物理研究所 Heat exchange system and nuclear reactor system
CN106409346A (en) * 2016-09-23 2017-02-15 中广核研究院有限公司 Outer strip, location grid of nuclear reactor fuel subassembly, and nuclear reactor fuel subassembly
CN107230502A (en) * 2017-06-09 2017-10-03 岭东核电有限公司 Fuel assembly and its screen work and support insert
WO2018053812A1 (en) * 2016-09-23 2018-03-29 中广核研究院有限公司 Outer strip, spacer grid for nuclear reactor fuel assembly and nuclear reactor fuel assembly
CN108492895A (en) * 2018-03-09 2018-09-04 西南交通大学 A kind of anti-hook mechanical testing equipment of fuel assembly screen work
CN110164567A (en) * 2018-03-30 2019-08-23 吉林农业大学 A kind of PWR fuel assembly screen work and the fuel assembly with this screen work
CN112071441A (en) * 2020-08-10 2020-12-11 岭东核电有限公司 Novel fuel assembly with spiral structure fuel rod
CN113450931A (en) * 2021-04-12 2021-09-28 中广核研究院有限公司 Fuel assembly positioning grid, fuel assembly and reactor core
CN114220558A (en) * 2021-11-18 2022-03-22 中国核动力研究设计院 Fuel assembly grillwork, fuel assembly and pressurized water reactor core
WO2023283971A1 (en) * 2021-07-13 2023-01-19 中广核研究院有限公司 Positioning lattice and fuel assembly

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0631753B2 (en) * 1988-10-11 1994-04-27 三菱原子燃料株式会社 Support grid
CN1458653A (en) * 2002-05-15 2003-11-26 西屋电气有限责任公司 Fuel device and relative grid for nuclear reactor
CN101069242A (en) * 2004-11-30 2007-11-07 阿海珐核能公司 Pencil support grid for nuclear fuel assembly and corresponding assembly
CN202948733U (en) * 2012-12-20 2013-05-22 中国核动力研究设计院 Positioning grillwork with hooking prevention and blending action for nuclear fuel assembly
CN203134386U (en) * 2013-01-15 2013-08-14 上海核工程研究设计院 Grid for enhancing rigidity and reducing snag-on risk of fuel assembly

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0631753B2 (en) * 1988-10-11 1994-04-27 三菱原子燃料株式会社 Support grid
CN1458653A (en) * 2002-05-15 2003-11-26 西屋电气有限责任公司 Fuel device and relative grid for nuclear reactor
CN101069242A (en) * 2004-11-30 2007-11-07 阿海珐核能公司 Pencil support grid for nuclear fuel assembly and corresponding assembly
CN202948733U (en) * 2012-12-20 2013-05-22 中国核动力研究设计院 Positioning grillwork with hooking prevention and blending action for nuclear fuel assembly
CN203134386U (en) * 2013-01-15 2013-08-14 上海核工程研究设计院 Grid for enhancing rigidity and reducing snag-on risk of fuel assembly

Cited By (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104036830A (en) * 2014-06-20 2014-09-10 中科华核电技术研究院有限公司 Low pressure drop holding grid and fuel component with holding grid
GB2549641B (en) * 2014-12-05 2020-09-02 China Nuclear Power Technology Res Inst Co Ltd Deflecting vane structure and mixing grid
WO2016086810A1 (en) * 2014-12-05 2016-06-09 中广核研究院有限公司 Fairing-type guiding vane structure and stirring-mixing lattice
GB2549641A (en) * 2014-12-05 2017-10-25 China Nuclear Power Technology Res Inst Co Ltd Deflecting vane structure and mixing grid
WO2016127527A1 (en) * 2015-02-13 2016-08-18 中国科学院近代物理研究所 Heat exchange system and nuclear reactor system
CN105869681A (en) * 2016-05-26 2016-08-17 中广核研究院有限公司 Fuel assembly and outer-strip-free positioning grid frame and strips thereof
CN106409346A (en) * 2016-09-23 2017-02-15 中广核研究院有限公司 Outer strip, location grid of nuclear reactor fuel subassembly, and nuclear reactor fuel subassembly
WO2018053812A1 (en) * 2016-09-23 2018-03-29 中广核研究院有限公司 Outer strip, spacer grid for nuclear reactor fuel assembly and nuclear reactor fuel assembly
CN107230502A (en) * 2017-06-09 2017-10-03 岭东核电有限公司 Fuel assembly and its screen work and support insert
CN108492895A (en) * 2018-03-09 2018-09-04 西南交通大学 A kind of anti-hook mechanical testing equipment of fuel assembly screen work
CN108492895B (en) * 2018-03-09 2024-05-14 西南交通大学 Anti-hooking mechanical test device for fuel assembly grillwork
CN110164567A (en) * 2018-03-30 2019-08-23 吉林农业大学 A kind of PWR fuel assembly screen work and the fuel assembly with this screen work
CN110164567B (en) * 2018-03-30 2023-01-17 吉林农业大学 Pressurized water reactor fuel assembly grillwork
CN112071441A (en) * 2020-08-10 2020-12-11 岭东核电有限公司 Novel fuel assembly with spiral structure fuel rod
CN112071441B (en) * 2020-08-10 2021-09-07 岭东核电有限公司 Fuel assembly with fuel rod of helical structure
CN113450931A (en) * 2021-04-12 2021-09-28 中广核研究院有限公司 Fuel assembly positioning grid, fuel assembly and reactor core
WO2023283971A1 (en) * 2021-07-13 2023-01-19 中广核研究院有限公司 Positioning lattice and fuel assembly
CN114220558A (en) * 2021-11-18 2022-03-22 中国核动力研究设计院 Fuel assembly grillwork, fuel assembly and pressurized water reactor core

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