CN103117098A - Square fuel assembly structure suitable for supercritical water-cooled reactor - Google Patents
Square fuel assembly structure suitable for supercritical water-cooled reactor Download PDFInfo
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- CN103117098A CN103117098A CN2013100429347A CN201310042934A CN103117098A CN 103117098 A CN103117098 A CN 103117098A CN 2013100429347 A CN2013100429347 A CN 2013100429347A CN 201310042934 A CN201310042934 A CN 201310042934A CN 103117098 A CN103117098 A CN 103117098A
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Abstract
The invention discloses a square fuel assembly structure suitable for a supercritical water-cooled reactor. The structure mainly comprises a plurality of subassemblies, an upper tube seat and a lower tube seat, wherein the subassemblies are arranged to be square, the upper tube seat and the lower tube seat are simultaneously connected with two ends of the subassemblies, and a moderator channel and a cooling water channel which are separated from each other are arranged in a fuel assembly. The square fuel assembly structure suitable for the supercritical water-cooled reactor has the advantages and the beneficial effects that as the moderator channel and the cooling water channel which are separated from each other are arranged, the effective shunting of cooling water and moderators is realized; the structure stability is strong; and as the structure is provided with a compression mechanism, the structure is stably mounted.
Description
Technical field
The present invention relates to a kind of reactor core internals, be specifically related to a kind of fuel assembly.
Background technology
The advantages such as Supercritical-Pressure Light Water Cooled Reactor (SCWR) has that the thermal efficiency is high, good economy performance, system are simple, compact conformation, as the 4th selected reactor concept heap type of international nuclear reactor forum (GIF) of generation, be have most at present application prospect the 4th generation one of reactor type.
Supercritical-Pressure Light Water Cooled Reactor core exit temperature higher (more than 500 ℃), and the reactor core import/export temperature difference also higher (more than 220 ℃), the huge challenge of bringing for the design of supercritical fuel assembly.The higher Core cooling agent import/export temperature difference causes coolant density to alter a great deal, the moderation of neutrons wretched insufficiency on reactor core top, higher core exit temperature has also increased the complicacy of core structure flow process, and similar present presurized water reactor one-flow core design can not be satisfied the requirement of SCWR.In order to solve the temperature difference problem of reactor core existence, be necessary to design the reactor core of two flow processs or three flow processs, this has increased the complicacy of fuel assembly design undoubtedly.
Now, the country that carries out fuel assembly detailed design research for Supercritical-Pressure Light Water Cooled Reactor is mainly Japan and European Union.
In Japan, Supercritical-Pressure Light Water Cooled Reactor is called as overcritical light water reactor (SCLWR-H), adopts the two-flow core design.The fuel assembly cross section as shown in Figure 1.The reactor fuel assembly comprises 300 fuel rod A101,102 and 24 border rectangle water rods 103 of 36 square water rods, gauge pipe 104 is positioned at the center of assembly, 16 square water rod 102 intermediate arrangement control rod guide pipes 105, also have an assembly housing 106 in the periphery at the center.Involucrum and structured material all adopt nickel-base alloy.In this scheme, water rod box quantity is many, and cooling medium and moderator split ratio are more difficult, the modular construction less stable, and need more structured material.
In European Union, Supercritical-Pressure Light Water Cooled Reactor is called high performance light water-water reactor (HPLWR).Surpass the high temperature of 500 ℃ in order to reach outlet, European Union has proposed three flow process Core Designs (namely dividing for three steps heat and the Core Design of band middle mixing).European Union's supercritical fuel assembly xsect as shown in Figure 2, each fuel assembly has water gap 109 by 9 sub-module compositions between sub-component.Each sub-component has a stainless steel square box, comprises 40 fuel rod B107 in it, has been wound around a wrapping wire 108 around every fuel rod B107, leaves respectively the gap between wrapping wire 108 and fuel rod B107 or box wall 111.Every root assembly center also has a moderator container 110.In this scheme, sub-component quantity is more, fuel assembly syndeton design relative complex.
In order to address the above problem, the inventor is through having researched and proposed a kind of adaptation two-flow core structure, square fuel assembly structure simple and reliable for structure.
Summary of the invention
Purpose of the present invention namely is to provide a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor, to overcome the deficiency of existing Supercritical-Pressure Light Water Cooled Reactor fuel assembly cooling medium and moderator shunting difficulty.
Purpose of the present invention is achieved through the following technical solutions:
A kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor, mainly consisted of by the upper base and the bottom nozzle that are arranged in square a plurality of sub-components, be connected with a plurality of sub-components two ends simultaneously, be provided with separate moderator passage and cooling-water duct in described fuel assembly.In this technical scheme, for chilled water and moderator respectively provide a passage, chilled water and moderator are thoroughly shunted, fuel rod in sub-component can mainly be heated chilled water, improve the efficiency of heating surface, made the outlet temperature of fuel assembly can reach predetermined temperature through less flow process.
As the first prioritization scheme of the present invention, also comprise and be arranged at a plurality of upper moderator pipe in described upper base and be arranged at the interior a plurality of lower moderator pipe of described bottom nozzle, described sub-component comprises sub-component box, moderator box and fuel rod, the moderator box is arranged in the middle part of the sub-component box, fuel rod is arranged between moderator box and sub-component box, upper moderator pipe and lower moderator pipe are communicated with the moderator box and form the moderator passage, and upper base and bottom nozzle are communicated with the sub-component box and form cooling-water duct.In this prioritization scheme, the inventor limits moderator passage and cooling-water duct.The moderator passage is communicated with a plurality of moderator boxes by a plurality of upper and lower moderator pipes and forms, and a moderator passage is namely all arranged in each sub-component, has guaranteed the homogeneity of slowing down.Cooling-water duct is communicated with by upper base, bottom nozzle the spatial composing that obtains with sub-component, namely each sub-component has the cooling-water duct of a correspondence, to separately heating of chilled water, so more easily realizes the control to coolant water temperature.
Further optimization as the first prioritization scheme of the present invention, also comprise the upper junction plate and the lower connecting plate that are arranged at respectively two ends, described sub-component box up and down, the two ends of described fuel rod are fixed on upper junction plate and lower connecting plate, offer on upper junction plate be communicated with sub-component and with the cooling water hole of upper base, offer on lower connecting plate be communicated with sub-component and with the cooling water hole of bottom nozzle, upper moderator pipe passes upper junction plate and is connected with the moderator box, and lower moderator pipe passes lower connecting plate and is connected with the moderator box.The fundamental purpose of upper junction plate and lower connecting plate is fixed fuel rod and sub-component box.
As the second prioritization scheme of the present invention, also comprise the base web member, described each sub-component is communicated with upper base and bottom nozzle by the base web member.The base web member makes each sub-component be connected to be connected with bottom nozzle with upper base and is more prone to.
As the third prioritization scheme of the present invention, also comprise pressure strip, holddown spring and pin, offer vertical stopper slot on described upper base, be provided with limited step on upper base, pressure strip is placed in the base top, pin runs through pressure strip and is arranged in vertical stopper slot, and holddown spring is between pressure strip and limited step.Said structure is hold-down mechanism, and when installation was of the present invention, the reactor core upper junction plate can compress holddown spring by pressure strip, realizes compression of the present invention, prevents that the present invention from play occurring when work, improved the stability of reactor core.And the mode of employing spring compression can also obtain certain deflection yoke, also can not cause reactor core to damage when making expanded by heating of the present invention.
As the 4th kind of prioritization scheme of the present invention, also comprise screen work, comprise a plurality of grids on screen work, described sub-component is fixed in described grid.Screen work realized between sub-component radially, axial location and support, guaranteed lateral stiffness of the present invention, and can keep the spacing between sub-component, greatly improved stability of the present invention.Described screen work periphery is provided with fixedly tongue, described sub-component and fixedly tongue be connected and fixed.This fixed form is simple, easily keeps bearing accuracy.Usually adopt the mode of sub-component and fixedly tongue welding to fix.
As the 5th kind of prioritization scheme of the present invention, also comprise the register pin that is provided with the bottom nozzle periphery, circumferential location is provided in reactor for the present invention.
As the 6th kind of prioritization scheme of the present invention, on the basis of above-mentioned any one scheme, also comprise cross control rod, described sub-component is arranged with the matrix form of 2*2, form the cross zone between described sub-component, cross control rod is arranged in the cross zone.Obtain holding the zone of control rod by the arrangement of sub-component, and this cross zone also has guide effect, need not guide pipe and also can accurately insert control rod, has simplified structure of the present invention.
Further optimization as the 6th kind of prioritization scheme of the present invention also comprises top board, and top board is arranged in described upper base, offers cross bore and upper moderator hole on top board, and described upper moderator pipe passes the moderator hole.This top board is used for base in shutoff, and cross bore is used for by cross control rod.
Further optimization as the 6th kind of prioritization scheme of the present invention, also comprise spreader plate, spreader plate is the cross shell type structure, be used for by the cross control rod, spreader plate is arranged in base, to be divided into four independently spaces in upper base, each independently is communicated with a sub-component respectively in the space, offer on upper base four with the steam window of space corresponding independently.Said structure can make the chilled water shunting of flowing out in each sub-component.
In sum, advantage of the present invention and beneficial effect are:
1. be provided with separate moderator passage and cooling-water duct, realized effective shunting of chilled water and moderator;
2. a moderator passage is all arranged in each sub-component, guaranteed the homogeneity of slowing down; Each sub-component has the cooling-water duct of a correspondence, more easily realizes the control to cooling water temperature;
3. the base web member is arranged so that each sub-component is connected to be connected with bottom nozzle with upper base and is more prone to;
Screen work realized between sub-component radially, axial location and support, guaranteed lateral stiffness of the present invention, and can keep the spacing between sub-component, improved greatly structural stability of the present invention;
5. the compression when hold-down mechanism has realized that the present invention works prevents that the present invention from play occurring when work, improved the stability of reactor core, and, adopt the mode of spring compression, can also obtain certain deflection yoke, also can not cause reactor core to damage when making expanded by heating of the present invention;
6. be provided with positioning key in the bottom nozzle periphery, circumferential location can be provided in reactor for the present invention;
7. arrange by sub-component the cross zone that obtains and also have guide effect, need not guide pipe and also can accurately insert control rod, simplified structure of the present invention.
Description of drawings
In order to be illustrated more clearly in embodiments of the invention, the below will make simple explanation to the required accompanying drawing of using in the description embodiment of the present invention.Apparent, the accompanying drawing in the following describes is only some embodiment that put down in writing in the present invention, to those skilled in the art, in the situation that do not pay creative work, can also according to following accompanying drawing, obtain other accompanying drawing.
Fig. 1 is the structural representation of overcritical light water reactor;
Fig. 2 is the structural representation of high performance light water-water reactor;
Fig. 3 is cross-sectional view of the present invention;
Fig. 4 is that structure of the present invention is always schemed;
Fig. 5 is upper base structural representation;
Fig. 6 is the top board structure schematic diagram;
Fig. 7 is sub-component structural representation A;
Fig. 8 is sub-component structural representation B;
Fig. 9 is the bottom nozzle structural representation;
Figure 10 is the frame structure schematic diagram;
Figure 11 is base connecting-piece structure schematic diagram;
Wherein, the parts title that Reference numeral is corresponding is as follows:
the 1-sub-component, the upper base of 2-, the 3-bottom nozzle, the 4-screen work, the cross control rod of 5-, 6-base web member, the 7-register pin, 101-fuel rod A, 102-square water rod, 103-rectangle water rod, the 104-gauge pipe, 105-control rod guide pipe, the 106-assembly housing, 107-fuel rod B, the 108-wrapping wire, 109-water gap, 110-moderator container, 111-box wall, 121-sub-component box, 122-moderator box, the 123-fuel rod, 124-cross zone, the 125-upper junction plate, the 126-lower connecting plate, 127-locates gusset, the upper moderator pipe of 201-, the 202-pressure strip, the 203-holddown spring, the 204-pin, the 205-top board, the 206-cross bore, the upper moderator of 207-hole, the 208-spreader plate, 209-steam window, the 210-upper substrate, moderator pipe under 301-, the 302-infrabasal plate, 401-is tongue fixedly.
Embodiment
In order to make those skilled in the art understand better the present invention, below in conjunction with the accompanying drawing in the embodiment of the present invention, the technical scheme in the embodiment of the present invention is carried out clear, complete description.Apparent, embodiment described below is only the part in the embodiment of the present invention, rather than all.Based on the embodiment of the present invention record, those skilled in the art are not in the situation that pay other all embodiment that creative work obtains, all in the scope of protection of the invention.
Embodiment 1:
As shown in Figure 4, a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor, mainly consisted of by the upper base 2 and the bottom nozzle 3 that are arranged in square a plurality of sub-components 1, be connected with a plurality of sub-components 1 two ends simultaneously, be provided with separate moderator passage and cooling-water duct in described fuel assembly.In the present embodiment, for chilled water and moderator respectively provide a passage, chilled water and moderator are thoroughly shunted, fuel rod in sub-component 1 can mainly be heated chilled water, improve the efficiency of heating surface, made the outlet temperature of fuel assembly can reach predetermined temperature through less flow process.
The present embodiment namely is to disclose a kind of separate moderator passage and fuel assembly of cooling-water duct of having, and the remainder of fuel assembly can adopt existing techniques in realizing.
Embodiment 2:
the present embodiment limits the composition of moderator passage and coolant channel on the basis of embodiment 1, as Fig. 4, Fig. 5, Fig. 7, Fig. 8 and shown in Figure 9, also comprise and be arranged at a plurality of upper moderator pipe 201 in described upper base 2 and be arranged at the interior a plurality of lower moderator pipe 301 of described bottom nozzle 3, described sub-component 1 comprises the sub-component box 121 of square, moderator box 122 and fuel rod 123, moderator box 122 is arranged at sub-component box 121 middle parts, fuel rod 123 is arranged between moderator box 122 and sub-component box 121, upper moderator pipe 201 and lower moderator pipe 301 are communicated with moderator box 122 and form the moderator passage, upper base 2 and bottom nozzle 3 are communicated with sub-component box 121 and form cooling-water duct.
The moderator passage is communicated with a plurality of moderator boxes 122 by a plurality of upper and lower moderator pipes and forms, and namely a moderator passage is all arranged each sub-component 1 is interior, has guaranteed the homogeneity of slowing down.Cooling-water duct is communicated with sub-component 1 spatial composing that obtains by upper base 2, bottom nozzle 3, and namely each sub-component 1 has the cooling-water duct of a correspondence, to separately heating of chilled water, so more easily loses efficacy to the control of coolant water temperature.
Embodiment 3:
as shown in Figure 7 and Figure 8, the present embodiment is on the basis of embodiment 2, also comprise the upper junction plate 125 and the lower connecting plate 126 that are arranged at respectively described sub-component box two ends Shang Xia 121, the two ends of described fuel rod 123 are fixed on upper junction plate 125 and lower connecting plate 126, offer on upper junction plate 125 and be communicated with sub-component and 121 and the cooling water hole of upper base 2, offer on lower connecting plate 126 and be communicated with sub-component and 121 and the cooling water hole of bottom nozzle 3, upper moderator pipe 201 passes upper junction plate 125 and is connected with moderator box 122, lower moderator pipe 301 passes lower connecting plate 126 and is connected with moderator box 122.Offer porosely on upper junction plate 125 and lower connecting plate 126, be used for the two ends of top fuel rod 123.Also offer the muscle groove on upper junction plate 125, be used for placement positioning gusset 127, hole shown in the upper end plug of fuel rod 123 is passed is connected with location gusset 127, realizes the location, top of fuel rod 123.
Embodiment 4:
As Fig. 4 and shown in Figure 11, the present embodiment is set up base web member 6 on the basis of embodiment 1, and described each sub-component 1 is communicated with upper base 2 and bottom nozzle 3 by base web member 6.Also be provided with upper substrate 210 and infrabasal plate 302, upper substrate 210 is arranged at the bottom of base 2, and infrabasal plate 302 is arranged at the top of bottom nozzle 3, all offers the circular hole that Cooling Water and moderator pipe pass through on upper substrate 210 and infrabasal plate 302.
In order to coordinate sub-component 1 and being connected that upper base 2 is connected with bottom nozzle, base web member 6 is designed to the shape of circular upper part and square lower part, square end is connected with sub-component 1, and nose circle is connected with circular hole on upper substrate 210 or infrabasal plate 302.
Embodiment 5:
As shown in Figure 4, the present embodiment is set up pressure strip 202, holddown spring 203 and pin 204 on the basis of embodiment 1, offer vertical stopper slot on described upper base 2, be provided with limited step on upper base 2, pressure strip 202 is placed in base 2 tops, pin 204 runs through pressure strip 202 and is arranged in vertical stopper slot, and holddown spring 203 is between pressure strip 202 and limited step.
Said structure is hold-down mechanism, and when installation was of the present invention, the reactor core upper junction plate can compress holddown spring 203 by pressure strip 202, realizes compression of the present invention, prevents that the present invention from play occurring when work, improved the stability of reactor core.And the mode of employing spring compression can also obtain certain deflection yoke, also can not cause reactor core to damage when making expanded by heating of the present invention.
Embodiment 6:
This is as Fig. 4 and shown in Figure 10, and in order to improve stability of the present invention, the present embodiment is on the basis of embodiment 1, set up screen work 4, comprise a plurality of grids on screen work 4, screen work 4 peripheries are provided with fixedly tongue 401, and described sub-component 1 is arranged in grid and is connected and fixed with fixing tongue 401.
Embodiment 7:
As shown in Figure 9, the present embodiment is set up register pin 7 in bottom nozzle 3 peripheries on the basis of embodiment 1, circumferential location is provided in reactor for the present invention.
Embodiment 8:
As shown in Figure 3, the present embodiment also comprises cross control rod 5 on the basis of above-mentioned each embodiment, and described sub-component 1 is arranged with the matrix form of 2*2, forms cross zone 124 between described sub-component 1, and cross control rod 5 is arranged in cross zone 124.
Obtain holding the zone of cross control rod 5 by the arrangement of sub-component 1, and this cross zone 124 also has guide effect, need not guide pipe and also can accurately insert control rod, has simplified structure of the present invention.
Embodiment 9:
As shown in Figure 6, the present embodiment also comprises top board 205 on the basis of embodiment 8, and top board 205 is arranged in described upper base 2, offers cross bore 206 and upper moderator hole 207 on top board 205, and described upper moderator pipe 201 passes moderator hole 207.Cross bore 206 is passed through for cross control rod 5.
Embodiment 10:
As shown in Figure 4 and Figure 5, the present embodiment is on the basis of embodiment 8, also comprise spreader plate 208, spreader plate 208 is the cross shell type structure, be used for by cross control rod 5, spreader plate 208 is arranged in base 2, will be divided into four independently spaces in upper base 2, each independently is communicated with a sub-component 1 respectively in the space, offer on upper base 2 four with the steam window 209 of space corresponding independently.
Significantly, those skilled in the art can combine to realize purpose of the present invention with any scheme in embodiment 1 ~ embodiment 10 according to the description in embodiment 1 ~ embodiment 10.
In order originally to be convenient to understand, the below has also announced embodiment 11, and embodiment 11 is the combination of all technical schemes in embodiment 1 ~ embodiment 10.
Embodiment 11:
As Fig. 3 ~ shown in Figure 11, a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor, sub-component 1 is arranged with the matrix form of 2*2, forms cross zone 124 between described sub-component 1, and cross control rod 5 is arranged in cross zone 124.Comprise a plurality of grids on screen work 4, screen work 4 peripheries are provided with fixedly tongue 401, and described sub-component 1 is arranged in grid and is connected and fixed with fixing tongue 401.Be provided with cross-hole in screen work 4, pass for cross control rod 5.Be provided with upper substrate 210 and infrabasal plate 302, upper substrate 210 is arranged at the bottom of base 2, infrabasal plate 302 is arranged at the top of bottom nozzle 3, all offer the circular hole that Cooling Water and moderator pipe pass through on upper substrate 210 and infrabasal plate 302, described each sub-component 1 is communicated with upper base 2 and bottom nozzle 3 by base web member 6, and wherein, base web member 6 is the shape of circular upper part and square lower part, square end is connected with sub-component 1, and nose circle is connected with circular hole on upper substrate 210 or infrabasal plate 302.Be provided with separate moderator passage and cooling-water duct in described fuel assembly.Bottom nozzle 3 peripheries are provided with register pin 7.
Also comprise and be arranged at a plurality of upper moderator pipe 201 in described upper base 2 and be arranged at the interior a plurality of lower moderator pipe 301 of described bottom nozzle 3, described sub-component 1 comprises sub-component box 121, moderator box 122 and the fuel rod 123 of square, moderator box 122 is arranged at sub-component box 121 middle parts, fuel rod 123 is arranged between moderator box 122 and sub-component box 121, upper moderator pipe 201 and lower moderator pipe 301 are communicated with moderator box 122 and form the moderator passage, and upper base 2 and bottom nozzle 3 are communicated with sub-component box 121 and form cooling-water duct.Top board 205 is arranged in described upper base 2, offers cross bore 206 and upper moderator hole 207 on top board 205, and described upper moderator pipe 201 passes moderator hole 207.Cross bore 206 is passed through for cross control rod 5.Spreader plate 208 is the cross shell type structure, be used for by cross control rod 5, spreader plate 208 is arranged in base 2, four independently spaces will be divided in upper base 2, each independently is communicated with a sub-component 1 respectively in the space, offer on upper base 2 four with the steam window 209 of space corresponding independently.
Also comprise the upper junction plate 125 and the lower connecting plate 126 that are arranged at respectively described sub-component box two ends Shang Xia 121, the two ends of described fuel rod 123 are fixed on upper junction plate 125 and lower connecting plate 126, offer the cooling water hole that is communicated with sub-component 121 and upper base 2 on upper junction plate 125, offer the cooling water hole that is communicated with sub-component 121 and bottom nozzle 3 on lower connecting plate 126, upper moderator pipe 201 passes upper junction plate 125 and is connected with moderator box 122, and lower moderator pipe 301 passes lower connecting plate 126 and is connected with moderator box 122.Offer porosely on upper junction plate 125 and lower connecting plate 126, be used for the two ends of top fuel rod 123.Also offer the muscle groove on upper junction plate 125, be used for placement positioning gusset 127, hole shown in the upper end plug of fuel rod 123 is passed is connected with location gusset 127, realizes the location, top of fuel rod 123.
Also comprise pressure strip 202, holddown spring 203 and pin 204, offer vertical stopper slot on described upper base 2, be provided with limited step on upper base 2, pressure strip 202 is placed in base 2 tops, pin 204 runs through pressure strip 202 and is arranged in vertical stopper slot, and holddown spring 203 is between pressure strip 202 and limited step.
As mentioned above, just can realize preferably the present invention.
Claims (10)
1. square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor, mainly by the upper base (2) and bottom nozzle (3) formation that are arranged in square a plurality of sub-components (1), are connected with a plurality of sub-components (1) two ends simultaneously, it is characterized in that: be provided with separate moderator passage and cooling-water duct in described fuel assembly.
2. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 1, it is characterized in that: also comprise being arranged at a plurality of upper moderator pipe (201) in described upper base (2) and being arranged at the interior a plurality of lower moderator pipe (301) of described bottom nozzle (3), described sub-component (1) comprises sub-component box (121), moderator box (122) and fuel rod (123), moderator box (122) is arranged in the middle part of sub-component box (121), fuel rod (123) is arranged between moderator box (122) and sub-component box (121), upper moderator pipe (201) and lower moderator pipe (301) are communicated with moderator box (122) and form the moderator passage, upper base (2) and bottom nozzle (3) are communicated with sub-component box (121) and form cooling-water duct.
3. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 2, it is characterized in that: also comprise the upper junction plate (125) and the lower connecting plate (126) that are arranged at respectively two ends, described sub-component box (121) up and down, the two ends of described fuel rod (123) are fixed on upper junction plate (125) and lower connecting plate (126), offer the cooling water hole that is communicated with sub-component and (121) and upper base (2) on upper junction plate (125), offer the cooling water hole that is communicated with sub-component and (121) and bottom nozzle (3) on lower connecting plate (126), upper moderator pipe (201) passes upper junction plate (125) and is connected with moderator box (122), lower moderator pipe (301) passes lower connecting plate (126) and is connected with moderator box (122).
4. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 1, it is characterized in that: also comprise base web member (6), described each sub-component (1) is communicated with upper base (2) and bottom nozzle (3) by base web member (6).
5. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 1, it is characterized in that: also comprise pressure strip (202), holddown spring (203) and pin (204), offer vertical stopper slot on described upper base (2), upper base is provided with limited step on (2), pressure strip (202) is placed in base (2) top, pin (204) runs through pressure strip (202) and is arranged in vertical stopper slot, and holddown spring (203) is positioned between pressure strip (202) and limited step.
6. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 1, it is characterized in that: also comprise screen work (4), screen work comprises a plurality of grids on (4), screen work (4) periphery is provided with fixedly tongue (401), and described sub-component (1) is arranged in grid and is connected and fixed with fixing tongue (401).
7. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 1, is characterized in that: also comprise being arranged at the peripheral register pin (7) of bottom nozzle (3).
8. the described a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor of any one according to claim 2 ~ 7, it is characterized in that: also comprise cross control rod (5), described sub-component (1) is arranged with the matrix form of 2*2, form cross zone (124) between described sub-component (1), cross control rod (5) is arranged in cross zone (124).
9. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 8, it is characterized in that: also comprise top board (205), top board (205) is arranged in described upper base (2), offer cross bore (206) and upper moderator hole (207) on top board (205), described upper moderator pipe (201) passes moderator hole (207).
10. a kind of square fuel assembly structure that is applicable to Supercritical-Pressure Light Water Cooled Reactor according to claim 8, it is characterized in that: also comprise spreader plate (208), spreader plate (208) is the cross shell type structure, spreader plate (208) is arranged in base (2), four independently spaces will be divided in upper base (2), each independently is communicated with a sub-component (1) respectively in the space, offer on upper base (2) four with the steam window (209) of space corresponding independently.
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| CN2013100429347A CN103117098A (en) | 2013-02-04 | 2013-02-04 | Square fuel assembly structure suitable for supercritical water-cooled reactor |
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Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN104329067A (en) * | 2014-08-20 | 2015-02-04 | 中国石油化工股份有限公司 | Heavy oil thermal recovery process and special device thereof |
| CN106531232A (en) * | 2016-12-29 | 2017-03-22 | 中科瑞华原子能源技术有限公司 | Fuel assembly available for integral replacement |
| CN109935348A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of two-sided cooling annular fuel assembly being provided with periphery protection structure |
| CN110827999A (en) * | 2019-11-18 | 2020-02-21 | 中国核动力研究设计院 | Sleeve type fuel assembly and supercritical water-cooled reactor |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB870891A (en) * | 1959-04-16 | 1961-06-21 | Hawker Siddeley Nuclear Power | Improvements in or relating to nuclear reactors |
| CN85105433A (en) * | 1984-07-02 | 1987-01-14 | 西屋电气公司 | Fuel assembly |
| TW314632B (en) * | 1994-09-30 | 1997-09-01 | Siemens Power Corp | |
| JP2004069362A (en) * | 2002-08-02 | 2004-03-04 | Global Nuclear Fuel-Japan Co Ltd | Fuel assembly for boiling water reactor, and nuclear reactor |
| JP2005091292A (en) * | 2003-09-19 | 2005-04-07 | Toshiba Corp | Reactor and its operation method |
| JP2008045980A (en) * | 2006-08-15 | 2008-02-28 | Toshihisa Shirakawa | Square-shaped nuclear fuel assembly for bwr type using pwr nuclear fuel rod |
| KR20080060805A (en) * | 2006-12-27 | 2008-07-02 | 한전원자력연료 주식회사 | Nuclear fuel assembly comprising fuel rod end plug to increase fuel rod internal volume and to support fuel rod spring |
| CN102592688A (en) * | 2012-03-02 | 2012-07-18 | 华北电力大学 | Double-layer water rod assembly structure for supercritical water cooled reactor |
| CN102737735A (en) * | 2012-07-04 | 2012-10-17 | 中国核动力研究设计院 | Combined square fuel assembly, reactor core and two-pass flowing method of super-critical water reactor |
| WO2012150699A1 (en) * | 2011-05-02 | 2012-11-08 | 学校法人早稲田大学 | Fuel assembly, reactor core and water-cooled nuclear reactor |
-
2013
- 2013-02-04 CN CN2013100429347A patent/CN103117098A/en active Pending
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| GB870891A (en) * | 1959-04-16 | 1961-06-21 | Hawker Siddeley Nuclear Power | Improvements in or relating to nuclear reactors |
| CN85105433A (en) * | 1984-07-02 | 1987-01-14 | 西屋电气公司 | Fuel assembly |
| TW314632B (en) * | 1994-09-30 | 1997-09-01 | Siemens Power Corp | |
| JP2004069362A (en) * | 2002-08-02 | 2004-03-04 | Global Nuclear Fuel-Japan Co Ltd | Fuel assembly for boiling water reactor, and nuclear reactor |
| JP2005091292A (en) * | 2003-09-19 | 2005-04-07 | Toshiba Corp | Reactor and its operation method |
| JP2008045980A (en) * | 2006-08-15 | 2008-02-28 | Toshihisa Shirakawa | Square-shaped nuclear fuel assembly for bwr type using pwr nuclear fuel rod |
| KR20080060805A (en) * | 2006-12-27 | 2008-07-02 | 한전원자력연료 주식회사 | Nuclear fuel assembly comprising fuel rod end plug to increase fuel rod internal volume and to support fuel rod spring |
| WO2012150699A1 (en) * | 2011-05-02 | 2012-11-08 | 学校法人早稲田大学 | Fuel assembly, reactor core and water-cooled nuclear reactor |
| CN102592688A (en) * | 2012-03-02 | 2012-07-18 | 华北电力大学 | Double-layer water rod assembly structure for supercritical water cooled reactor |
| CN102737735A (en) * | 2012-07-04 | 2012-10-17 | 中国核动力研究设计院 | Combined square fuel assembly, reactor core and two-pass flowing method of super-critical water reactor |
Non-Patent Citations (1)
| Title |
|---|
| 邢硕,等: "超临界水冷堆燃料棒性能分析程序SCWRFPA的初步研究一包壳与冷却剂间的换热", 《中国核动力研究设计院科学技术年报（2011）》 * |
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|---|---|---|---|---|
| CN104329067A (en) * | 2014-08-20 | 2015-02-04 | 中国石油化工股份有限公司 | Heavy oil thermal recovery process and special device thereof |
| CN104329067B (en) * | 2014-08-20 | 2018-06-01 | 中国石油化工股份有限公司 | A kind of heavy crude heat extraction technique and its dedicated unit |
| CN106531232A (en) * | 2016-12-29 | 2017-03-22 | 中科瑞华原子能源技术有限公司 | Fuel assembly available for integral replacement |
| CN109935348A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of two-sided cooling annular fuel assembly being provided with periphery protection structure |
| CN109935348B (en) * | 2017-12-19 | 2024-07-19 | 中国原子能科学研究院 | Double-sided cooling annular fuel assembly with peripheral protection structure |
| CN110827999A (en) * | 2019-11-18 | 2020-02-21 | 中国核动力研究设计院 | Sleeve type fuel assembly and supercritical water-cooled reactor |
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