CN106448756A - Dual-zone fuel coolant counterflow fuel assembly and supercritical water cooled reactor - Google Patents
Dual-zone fuel coolant counterflow fuel assembly and supercritical water cooled reactor Download PDFInfo
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- CN106448756A CN106448756A CN201611059693.7A CN201611059693A CN106448756A CN 106448756 A CN106448756 A CN 106448756A CN 201611059693 A CN201611059693 A CN 201611059693A CN 106448756 A CN106448756 A CN 106448756A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Production Of Liquid Hydrocarbon Mixture For Refining Petroleum (AREA)
Abstract
The invention discloses a dual-zone fuel coolant counterflow fuel assembly and a supercritical water cooled reactor. The fuel assembly comprises a fuel assembly body. The fuel assembly body comprises a heat insulating shroud and an assembly box which are both in a barrel shape. The heat insulating shroud is sleeved with the assembly box, inner zone fuel rods and guide pipes are arranged in the heat insulating shroud, and outer zone fuel rods are arranged between the outer wall of the heat insulating shroud and the inner wall of the assembly box. The supercritical water cooled reactor comprises the fuel assembly. Compared with the prior art, according to the structure of the fuel assembly and the supercritical water cooled reactor, water rods occupying multiple lattice cells or a solid moderator is omitted, no guide pipe is arranged in an outer zone, the technical difficulty of the structural design of the assembly, components in the reactor and the like and the physical design of a reactor core is greatly lowered, structural materials are reduced, and neutron economical efficiency and engineering realizability are remarkably improved. The structural design of a pressure container, especially an upper steam chamber structure can be greatly simplified, and engineering realizability is remarkably improved.
Description
Technical field
The invention belongs to nuclear reactor technology field, a kind of more particularly to two-region fuel cooling agent reverse flow fuel stack
Part and Supercritical-Pressure Light Water Cooled Reactor.
Background technology
Supercritical-Pressure Light Water Cooled Reactor (SCWR) is most with prospects six kind that iv filters out for nuclear energy international symposium (GIF)
One of nuclear power system.SCWR nuclear power generating sets have the outstanding advantages such as the thermal efficiency is high, system simplifies.But it is slow in order to solve SCWR neutron
Change not enough and flowing instability sex chromosome mosaicism, assembly design introduces " water rod " design, Core Design employs " multithread
So that assembly and core structure design are extremely complex, engineering realizability is greatly lowered journey " mobility program.
Existing Supercritical-Pressure Light Water Cooled Reactor assembly and Core Design scheme, all have " water rod " or solid moderator, and cooling agent is
Double-flow or three flow processs.Under ideal conditions, substantially meet design requirement, if considering manufacture deviation and running the complicated work facing
Huge challenge will be faced in condition, assembly and Core Design concept feasible face.Additionally, in order to ensure cryogenic coolant and high temperature coolant
Between shunting, heat-insulated, the stronger structural material of a large amount of neutron absorption capability can be introduced to reactor core, lead to economy significantly under
Fall.Therefore, be highly desirable to rethink Supercritical-Pressure Light Water Cooled Reactor assembly and core structure design, realize economy, security with
The coordinating and unifying of engineering realizability.
Content of the invention
The present invention is directed to and overcomes existing supercritical water reactor fuel assembly and Core Design shortcoming, cancels " water rod " in assembly
Or " solid moderator ", reduce structural material and introduce, improve fuel economy.Secondly, cancel multipaths cooling agent flow design
Method, simplifies reactor core superstructure design, significantly improves engineering realizability, based on above goal of the invention, the invention provides
A kind of two-region fuel cooling agent reverse flow fuel assembly and Supercritical-Pressure Light Water Cooled Reactor.
For solving the above problems, a kind of two-region fuel cooling agent reverse flow fuel assembly and overcritical that the present invention provides
Water cooled reator is by following technical essential come solve problem：A kind of two-region fuel cooling agent reverse flow fuel assembly, including fuel
Component body, described fuel assembly body includes all tubular heat-insulated shroud and assembly housing, and described assembly housing is sheathed on heat-insulated
Outside shroud, in described heat-insulated shroud, it is provided with inner region fuel rod and guide pipe, the outer wall of described heat-insulated shroud and assembly housing
It is provided with outskirt fuel rod between inwall, and inner region fuel rod, guide pipe, the equal more than one of outskirt fuel rod, inner region fuel rod
All spaced apart with outskirt fuel rod adjacent thereto with guide pipe adjacent thereto or inner region fuel rod, outskirt fuel rod.
Specifically, in above fuel rod body construction, multiple fuel assemblies are segmented in outward by inner region using heat-insulated shroud
Area, the guide pipe simultaneously arranging is used for inserting control rod or measuring instrument, using assembly housing, multiple fuel assemblies is packaged,
Facilitate implementation mobility program in pressure vessel for the cool below agent：Cooling agent from cold end pressure vessel enter, first flow through every
The reactor core that hot shroud surrounds, after being flowed out by the reactor core that heat-insulated shroud surrounds between assembly housing inwall and heat-insulated shroud outer wall
Outflow pressure container after reactor core.Above design feature makes the fuel assembly of present invention offer compared to existing fuel assembly, takes
" the water rod " of the multiple lattice cell of the occupancy that disappeared or " solid moderator ", outskirt no guide pipe.Eliminate water rod, solid moderator and many
Flow process cooling agent flow design, significantly reduces the structure designs such as assembly, in-pile component and the technical difficulty of core physics design,
Decrease structural material, significantly improve neutron economy and engineering realizability.Meanwhile, the form of above fuel assembly replaces mesh
" double-flow or multipaths " coolant flow scheme of front employing, can significantly simplify construction of pressure vessel design, especially
Upper steam chamber structure, significantly improves engineering realizability.
As the further technical scheme to above two-region fuel cooling agent reverse flow fuel assembly：
In order to improve fuel availability, control power distribution, be easy to fuel assembly design, the inner region fuel in heat-insulated shroud
Rod and guide pipe press square or hexagonal lattice arrangement, the outskirt between heat-insulated shroud outer wall and assembly housing inwall each other
Fuel rod presses square or hexagonal lattice arrangement each other.Further, the inner region of fuel assembly, outskirt employ difference
Fuel rod, inner region fuel rod is identical with the physical dimension of guide pipe,.
In order to control the power distribution of inner region, outskirt, improve the utilization rate of outskirt fuel, described inner region fuel rod is simultaneously
Low enrichment UO2Fuel, described outskirt fuel rod is high enrichment UO2Fuel or mox fuel, described low enrichment UO2Fuel
For235The UO that U enrichment is less than 5%2Fuel, described high enrichment UO2Fuel is235U enrichment is more than or equal to 5% UO2Combustion
Material.
In order to control the cooling agent circulation area between the fuel rod of inner region, outskirt, the excellent footpath of described inner region fuel rod is little
In or be equal to the excellent footpath of outskirt fuel rod, inner region fuel rod is smaller than or equal to outskirt fuel interrod spacing.
In order to ensure that the control rod in guide pipe is in the relatively low cooling agent of temperature all the time, described inner region fuel
Rod, guide pipe, outskirt fuel rod, heat-insulated shroud, the diameter parallel of assembly housing, and guide cylinder is distributed in heat-insulated shroud.
It is provided with 200 inner region fuel rods and 25 guide pipes, heat-insulated shroud outer wall and assembly housing in described heat-insulated shroud
Be provided with 304 outskirt fuel rods between inwall, described outskirt fuel rod each other, interior drive fuel rod and guide pipe mutual it
Between all arrange by square grid, heat-insulated shroud and assembly housing are square perpendicular to the section of length direction.This programme is joined
Examine the nuclear power station Core Design scheme of conventionally employed square fuel assembly, this is conveniently easy to control zones of different in fuel assembly
Cooling agent circulation area.
It is provided with 210 inner region fuel rods and 61 guide pipes, heat-insulated shroud outer wall and assembly housing in described heat-insulated shroud
Be provided with 360 outskirt fuel rods between inwall, described outskirt fuel rod each other, interior drive fuel rod and guide pipe mutual it
Between all arrange by hexagonal lattice, heat-insulated shroud and assembly housing are hexagon perpendicular to the section of length direction.This programme is joined
Examine the nuclear power station Core Design scheme of conventionally employed hexagonal fuel assembly, this is conveniently easy to control zones of different in fuel assembly
Cooling agent circulation area.
Meanwhile, the invention discloses a kind of supercritical water using above two-region fuel cooling agent reverse flow fuel assembly
Cold dome, including pressure vessel, is provided with two pieces of layering dividing plates, pressure is held by two pieces of above layering dividing plates in described pressure vessel
Space within device is divided into upper chamber along pressure vessel axial directional distribution, steam chambers and lower chambers, steam chambers
Between upper chamber and lower chambers, in described steam chambers, it is additionally provided with two-region fuel cooling agent reverse flow described above
In fuel assembly, and described two-region fuel cooling agent reverse flow fuel assembly, the length of heat-insulated shroud is longer than assembly housing
Length, the entrance point of heat-insulated shroud is communicated with upper chamber and lower chambers respectively with the port of export, the arrival end of assembly housing and lower chambers
It is connected, the port of export of assembly housing is located in steam chambers, and described pressure vessel is additionally provided with the cooling agent being communicated with upper chamber
Entrance, pressure vessel is additionally provided with the coolant outlet being communicated with steam chambers.
Specifically, in Supercritical-Pressure Light Water Cooled Reactor provided above, the type of flow in pressure vessel for the cooling agent is：Cooling agent
Introduce upper chamber to coolant entrance, then flow through the region that heat-insulated shroud surrounds, complete the cooling to inner region fuel rod, then
Lower chambers are flow to by the port of export of heat-insulated shroud, then is entered between heat-insulated shroud outer wall and assembly housing inwall by the entrance of assembly housing
Region, complete the cooling to outskirt fuel rod, finally by coolant outlet outflow pressure container.In above structure, preferably will
Lower chambers are arranged on the seal head end of pressure vessel, and so, the cooling agent with certain kinetic energy is in seal head end inwall and respective diaphragms
In the lower chambers with given shape constituting, outskirt fuel rod cooled region of can entering again after fully stirring evenly mixing.
Pressure above container, compared to the pressure vessel in existing core field, eliminates water rod, solid moderator and multipaths
Cooling agent flow design, significantly reduces the structure designs such as assembly, in-pile component and the technical difficulty of core physics design, reduces
Structural material, significantly improves neutron economy and engineering realizability.Meanwhile, the form of above fuel assembly replaces adopting at present
" double-flow or multipaths " coolant flow scheme, can significantly simplify construction of pressure vessel design, especially top
Steam chambers structure, significantly improves engineering realizability.
Further technical scheme as above Supercritical-Pressure Light Water Cooled Reactor：
As the technical scheme of a kind of adjustable reactor core assembly inner region and outskirt Local cooling agent flux, right in order to obtain
The inner region fuel rod of zones of different or the different cooling capacity of outskirt fuel rod, are provided with use in described upper chamber and lower chambers
In to cooling agent flowing guided or current limliting throttling element.
The invention has the advantages that：
The invention provides a kind of two-region fuel cooling agent reverse flow fuel assembly and being faced using the super of this fuel assembly
Boundary's water cooled reator, fuel assembly structure or Supercritical-Pressure Light Water Cooled Reactor construction of pressure vessel that the present invention provides, compared to existing fuel stack
Part or pressure vessel, eliminate water rod, solid moderator and multipaths cooling agent flow design, significantly reduce assembly, in heap
The structure designs such as component and the technical difficulty of core physics design, decrease structural material, significantly improve neutron economy and work
Journey realizability.Meanwhile, the form of above fuel assembly replaces " double-flow or multipaths " the cooling agent flowing side adopting at present
Case, can significantly simplify construction of pressure vessel design, especially upper steam chamber structure, significantly improve engineering and can achieve
Property.
Brief description
Fig. 1 is in a kind of fuel cooling agent reverse flow fuel assembly of two-region of the present invention, concrete inner region combustion
Charge bar, outskirt fuel rod and guide pipe are each other using the assembly schematic top plan view of square two-region distribution；
Fig. 2 is in a kind of fuel cooling agent reverse flow fuel assembly of two-region of the present invention, concrete inner region combustion
Charge bar, outskirt fuel rod and guide pipe adopt the assembly schematic top plan view of hexagon two-region distribution each other；
Fig. 3 is a kind of Supercritical-Pressure Light Water Cooled Reactor of employing two-region of the present invention fuel cooling agent reverse flow fuel assembly
Flow graph in this water cooled reator for the structural representation and cooling agent of a concrete embodiment；
Fig. 4 is a kind of Supercritical-Pressure Light Water Cooled Reactor of employing two-region of the present invention fuel cooling agent reverse flow fuel assembly
In, a concrete fuel stringer assembly adopts the fuel stringer assembly schematic diagram of square arrangement；
Fig. 5 is a kind of Supercritical-Pressure Light Water Cooled Reactor of employing two-region of the present invention fuel cooling agent reverse flow fuel assembly
In, a concrete fuel stringer assembly adopts the fuel stringer assembly schematic diagram of rounded projections arranged.
The title of mark and corresponding parts in accompanying drawing：1st, outskirt fuel rod, 2, inner region fuel rod, 3, guide pipe, 4, group
Part box, 5, heat-insulated shroud, 6, pressure vessel, 7, upper chamber, 8, steam chambers, 9, lower chambers, 10, square two-region fuel stack
Part, 11, hexagon two-region fuel assembly.
Specific embodiment
The invention provides a kind of two-region fuel cooling agent reverse flow fuel assembly and Supercritical-Pressure Light Water Cooled Reactor, for being directed to
Overcome existing supercritical water reactor fuel assembly and Core Design shortcoming, cancel " water rod " or " solid moderator " in assembly, subtract
Few structural material introduces, and improves the problem of fuel economy.With reference to embodiment, the present invention is described in further detail,
But the present invention is not limited only to following examples：
Embodiment 1：
As shown in Figure 1 to Figure 3, a kind of two-region fuel cooling agent reverse flow fuel assembly, including fuel assembly body, institute
State fuel assembly body and include all tubular heat-insulated shroud 5 and assembly housing 4, described assembly housing 4 is sheathed on outside heat-insulated shroud 5
Portion, is provided with inner region fuel rod 2 and guide pipe 3 in described heat-insulated shroud 5, the outer wall of described heat-insulated shroud 5 is interior with assembly housing 4
It is provided with outskirt fuel rod 1 between wall, and inner region fuel rod 2, guide pipe 3, the equal more than one of outskirt fuel rod 1, inner region fuel
Rod 2 is all spaced with outskirt fuel rod 1 adjacent thereto with guide pipe 3 adjacent thereto or inner region fuel rod 2, outskirt fuel rod 1
Distribution.
In the present embodiment, in above fuel rod body construction, multiple fuel assemblies are segmented in by inner region using heat-insulated shroud 5
With outskirt, the guide pipe 3 simultaneously arranging is used for inserting control rod or measuring instrument, using assembly housing 4, multiple fuel assemblies entered
Row encapsulation, facilitates implementation mobility program in pressure vessel 6 for the cool below agent：Cooling agent enters from pressure vessel 6 cold end, first
First flow through the reactor core that heat-insulated shroud 5 surrounds, enclose with heat-insulated through assembly housing 4 inwall after being flowed out by the reactor core that heat-insulated shroud 5 surrounds
Outflow pressure container 6 after reactor core between cylinder 5 outer walls.Above design feature makes the fuel assembly of present invention offer compared to existing
There is fuel assembly, eliminate water rod, solid moderator and multipaths cooling agent flow design, significantly reduce assembly, structure in heap
The structure designs such as part and the technical difficulty of core physics design, decrease structural material, significantly improve neutron economy and engineering
Realizability.Meanwhile, the form of above fuel assembly replaces " the double-flow or multipaths " coolant flow scheme adopting at present,
Pressure vessel 6 structure design, especially upper steam chamber 8 structure can significantly be simplified, significantly improve engineering and can achieve
Property.
Meanwhile, the invention discloses a kind of supercritical water using above two-region fuel cooling agent reverse flow fuel assembly
Cold dome, including pressure vessel 6, is provided with two pieces of layering dividing plates in described pressure vessel 6, above two pieces of layering dividing plates are by pressure
Space within container 6 is divided into upper chamber 7 along pressure vessel 6 axial directional distribution, steam chambers 8 and lower chambers 9, steams
Vapour chamber 8 is located between upper chamber 7 and lower chambers 9, is additionally provided with two-region fuel cooling described above in described steam chambers 8
In agent reverse flow fuel assembly, and described two-region fuel cooling agent reverse flow fuel assembly, the length of heat-insulated shroud 5 is long
In the length of assembly housing 4, the entrance point of heat-insulated shroud 5 is communicated with upper chamber 7 and lower chambers 9 respectively with the port of export, assembly housing 4
Arrival end is connected with lower chambers 9, and the port of export of assembly housing 4 is located in steam chambers 8, described pressure vessel 6 is additionally provided with
The coolant entrance that upper chamber 7 communicates, pressure vessel 6 is additionally provided with the coolant outlet being communicated with steam chambers 8.
Specifically, in Supercritical-Pressure Light Water Cooled Reactor provided above, the type of flow in pressure vessel 6 for the cooling agent is：Cooling
Agent introduces upper chamber 7 to coolant entrance, then flows through the region that heat-insulated shroud 5 surrounds, completes cold to inner region fuel rod 2
But, then lower chambers 9 are flow to by the port of export of heat-insulated shroud 5, more heat-insulated shroud 5 outer wall and group are entered by the entrance of assembly housing 4
Region between part box 4 inwall, completes the cooling to outskirt fuel rod 1, finally by coolant outlet outflow pressure container 6.With
In upper structure, preferably lower chambers 9 are arranged on the seal head end of pressure vessel 6, so, the cooling agent with certain kinetic energy is in end socket
In the lower chambers 9 with given shape that end inwall is constituted with respective diaphragms, outskirt combustion of can entering again after fully stirring evenly mixing
Charge bar 1 cooled region.
Pressure above container 6, compared to the pressure vessel 6 in existing core field, eliminates water rod, solid moderator and multithread
Journey cooling agent flow design, significantly reduces the structure designs such as assembly, in-pile component and the technical difficulty of core physics design, subtracts
Lack structural material, significantly improve neutron economy and engineering realizability.Meanwhile, the form of above fuel assembly replaces at present
Using " double-flow or multipaths " coolant flow scheme, can significantly simplify pressure vessel 6 structure design, especially go up
Portion's steam chambers 8 structure, significantly improves engineering realizability.
Embodiment 2：
The present embodiment is further qualified on the basis of the fuel assembly that embodiment 1 provides or provides concrete implementation side
Formula, as described in Fig. 1 to Fig. 3, the inner region fuel rod 2 in heat-insulated shroud 5 and guide pipe 3 press square or hexagon grid each other
Grillages arranges, and the outskirt fuel rod 1 between heat-insulated shroud 5 outer wall and assembly housing 4 inwall presses square or hexagon grid each other
Grillages arranges.
Described inner region fuel rod 2 is low enrichment UO2Fuel, described outskirt fuel rod 1 is high enrichment UO2Fuel or
Mox fuel, described low enrichment UO2Fuel is235The UO that U enrichment is less than 5%2Fuel, described high enrichment UO2Fuel is235U enrichment is more than or equal to 5% UO2Fuel.
The excellent footpath of described inner region fuel rod 2 is less than or equal to the excellent footpath of outskirt fuel rod 1, and inner region fuel rod 2 is smaller than
Or it is equal to outskirt fuel rod 1 spacing.
Described inner region fuel rod 2, guide pipe 3, outskirt fuel rod 1, heat-insulated shroud 5, the diameter parallel of assembly housing 4 five,
And guide cylinder is distributed in heat-insulated shroud 5.
It is provided with 200 inner region fuel rods 2 and 25 guide pipes 3, heat-insulated shroud 5 outer wall and group in described heat-insulated shroud 5
Be provided with 304 outskirt fuel rods 1 between part box 4 inwall, described outskirt fuel rod 1 each other, interior drive fuel rod and guiding
Pipe 3 is all arranged by square grid each other, and heat-insulated shroud 5 and assembly housing 4 are pros perpendicular to the section of length direction
Shape.This adopts the concrete implementation that square grid arranges as follows：The interrod spacing of inner region and outskirt fuel rod 1 is
1.0mm, the excellent footpath of assembly outskirt fuel rod 1 is 9.5mm, and the excellent footpath of assembly inner region fuel rod 2 is 9.1mm, and guide pipe 3 external diameter is
9.1mm, the wall thickness of square heat-insulated shroud 5 is 3.0mm, and square shaped module box 4 thickness is 0.5mm.Assembly inner region fuel rod 2 is
200,25 guide pipes 3, assembly outskirt fuel rod 1 is 304, and square heat-insulated shroud 5 length of side is 157.5mm, assembly housing 4
The length of side is 242.5mm.Inner region fuel is low enrichment UO2,235U enrichment is less than 5%, and outskirt fuel is high enrichment UO2Or
MOX, to balance interior outskirt power fraction, as preferred plan：Outskirt is mox fuel, and inner region is low enrichment UO2Fuel.Interior
Area's cooling agent enters from assembly upper end, and inlet temperature is 280 DEG C, flows out from lower end；Outskirt cooling agent enters from assembly lower end, enters
Mouth temperature is about 380 DEG C, flows out from assembly upper end, outlet temperature is more than 500 DEG C.
It is provided with 210 inner region fuel rods 2 and 61 guide pipes 3, heat-insulated shroud 5 outer wall and group in described heat-insulated shroud 5
Be provided with 360 outskirt fuel rods 1 between part box 4 inwall, described outskirt fuel rod 1 each other, interior drive fuel rod and guiding
Pipe 3 is all arranged by hexagonal lattice each other, and heat-insulated shroud 5 and assembly housing 4 are hexagonal perpendicular to the section of length direction
Shape.This adopts specifically a kind of implementation that hexagonal lattice arranges as follows：The excellent footpath of assembly outskirt fuel rod 1 is 9.5mm, rod
Spacing is 1.1mm, and the excellent footpath of assembly inner region fuel rod 2 is 9.1mm, and guide pipe 3 external diameter is 9.1mm, and interrod spacing is 1.0mm, six
Angular heat-insulated shroud 5 wall thickness is 2.7mm, and assembly housing 4 thickness is 0.5mm.Assembly inner region fuel rod 2 is 210,61 guide pipes
3, assembly outskirt fuel rod 1 is 360, and the heat-insulated shroud of hexagon 5 opposite side distance is 181.7mm, and hexagonal assembly box 4 opposite side distance is
266.1mm.Inner region fuel is low enrichment UO2,235U enrichment is less than 5%, and outskirt fuel is high enrichment UO2Or MOX, with flat
Outskirt power fraction in weighing apparatus, as preferred plan：Outskirt is mox fuel, and inner region is low enrichment UO2Fuel.Inner region cooling agent
Enter from assembly upper end, inlet temperature is 280 DEG C, flow out from lower end；Outskirt cooling agent enters from assembly lower end, and inlet temperature is about
For 380 DEG C, flow out from assembly upper end, outlet temperature is more than 500 DEG C.Wherein, mox fuel is plutonium uranium oxide fuel combination.
Embodiment 3：
Embodiment is further qualified on the basis of the Supercritical-Pressure Light Water Cooled Reactor that embodiment 1 provides or provides concrete implementation
Mode, as the technical scheme of a kind of adjustable reactor core assembly inner region and outskirt Local cooling agent flux, in order to obtain to not
With the different cooling capacity of the inner region fuel rod 2 in region or outskirt fuel rod 1, it is provided with described upper chamber 7 and lower chambers 9
For to cooling agent flowing guided or current limliting throttling element.
Embodiment 4：
Embodiment is providing a kind of specific implementation of Supercritical-Pressure Light Water Cooled Reactor, and which includes two concrete schemes, such as
Fig. 4 and Fig. 5, Fig. 4 are that wherein, in fuel assembly, the spacing of each assembly is 1.5mm using 121 box square two-region fuel assemblies
(spacing between adjacent outskirt fuel rod 1, adjacent inner region fuel rod 2), reactor core circumscribed circle diameter is 3256mm, wherein,
Label 10 points to square two-region fuel assembly；Fig. 5 is using 121 box hexagon two-region fuel assemblies, wherein, fuel assembly
In, the spacing of each assembly is 1.9mm (spacing between adjacent outskirt fuel rod 1, adjacent inner region fuel rod 2), outside reactor core
Connecing circular diameter is 3275mm, and wherein, label 11 points to hexagon two-region fuel assembly.The other technologies index of two schemes is such as
Shown in following table：
Above content is the further description present invention made with reference to specific preferred embodiment it is impossible to assert this
The specific embodiment of invention is confined to these explanations.For general technical staff of the technical field of the invention,
The other embodiment drawing under without departing from technical scheme, should be included in protection scope of the present invention.
Claims (9)
1. a kind of two-region fuel cooling agent reverse flow fuel assembly, including fuel assembly body it is characterised in that described fuel
Component body includes all tubular heat-insulated shroud (5) and assembly housing (4), and described assembly housing (4) is sheathed on heat-insulated shroud (5) outward
Portion, is provided with inner region fuel rod (2) and guide pipe (3), the outer wall of described heat-insulated shroud (5) and group in described heat-insulated shroud (5)
It is provided with outskirt fuel rod (1) between the inwall of part box (4), and inner region fuel rod (2), guide pipe (3), outskirt fuel rod (1)
All more than one, inner region fuel rod (2) and guide pipe (3) adjacent thereto or inner region fuel rod (2), outskirt fuel rod (1) with
Outskirt fuel rod (1) adjacent thereto is all spaced apart.
2. a kind of two-region according to claim 1 fuel cooling agent reverse flow fuel assembly is it is characterised in that heat-insulated enclose
Inner region fuel rod (2) in cylinder (5) and guide pipe (3) press square or hexagonal lattice arrangement, heat-insulated shroud (5) each other
Outskirt fuel rod (1) between outer wall and assembly housing (4) inwall presses square or hexagonal lattice arrangement each other.
3. a kind of two-region fuel cooling agent reverse flow fuel assembly according to claim 1 is it is characterised in that described interior
Area's fuel rod (2) is low enrichment UO2Fuel, described outskirt fuel rod (1) is high enrichment UO2Fuel or mox fuel, institute
State low enrichment UO2Fuel is235The UO that U enrichment is less than 5%2Fuel, described high enrichment UO2Fuel is235U enrichment is big
In or be equal to 5% UO2Fuel.
4. a kind of two-region fuel cooling agent reverse flow fuel assembly according to claim 1 is it is characterised in that described interior
The excellent footpath of area's fuel rod (2) is less than or equal to the excellent footpath of outskirt fuel rod (1), and inner region fuel rod (2) is smaller than or is equal to outer
Area's fuel rod (1) spacing.
5. a kind of two-region fuel cooling agent reverse flow fuel assembly according to claim 1 is it is characterised in that described interior
Area's fuel rod (2), guide pipe (3), outskirt fuel rod (1), heat-insulated shroud (5), the diameter parallel of assembly housing (4) five, and lead
It is distributed in heat-insulated shroud (5) to cylinder (3).
6. a kind of two-region fuel cooling agent reverse flow fuel assembly according to claim 1 it is characterised in that described every
It is provided with 200 inner region fuel rods (2) and 25 guide pipes (3), heat-insulated shroud (5) outer wall and assembly housing (4) in hot shroud (5)
Be provided with 304 outskirt fuel rods (1) between inwall, described outskirt fuel rod (1) each other, interior drive fuel rod (2) and lead
All arrange by square grid each other to pipe (3), heat-insulated shroud (5) and assembly housing (4) are perpendicular to the section of length direction
It is square.
7. a kind of two-region fuel cooling agent reverse flow fuel assembly according to claim 1 it is characterised in that described every
It is provided with 210 inner region fuel rods (2) and 61 guide pipes (3), heat-insulated shroud (5) outer wall and assembly housing (4) in hot shroud (5)
Be provided with 360 outskirt fuel rods (1) between inwall, described outskirt fuel rod (1) each other, interior drive fuel rod (2) and lead
All arrange by hexagonal lattice each other to pipe (3), heat-insulated shroud (5) and assembly housing (4) are perpendicular to the section of length direction
It is hexagon.
8. a kind of Supercritical-Pressure Light Water Cooled Reactor, including pressure vessel (6) it is characterised in that being provided with two pieces in described pressure vessel (6)
Layering dividing plate, the internal space of pressure vessel (6) is divided into along pressure vessel (6) axial direction side two pieces of above layering dividing plates
To the upper chamber (7) being distributed, steam chambers (8) and lower chambers (9), steam chambers (8) are located at upper chamber (7) and lower chambers (9)
Between, it is additionally provided with two-region as claimed in claim 1 fuel cooling agent reverse flow fuel stack in described steam chambers (8)
In part, and described two-region fuel cooling agent reverse flow fuel assembly, the length of heat-insulated shroud (5) is longer than assembly housing (4)
Length, the entrance point of heat-insulated shroud (5) is communicated with upper chamber (7) and lower chambers (9) respectively with the port of export, the entering of assembly housing (4)
Mouth end is connected with lower chambers (9), and the port of export of assembly housing (4) is located in steam chambers (8), and described pressure vessel (6) also sets
It is equipped with the coolant entrance communicating with upper chamber (7), pressure vessel (6) is additionally provided with the cooling being communicated with steam chambers (8)
Agent exports.
9. a kind of Supercritical-Pressure Light Water Cooled Reactor according to claim 8 is it is characterised in that described upper chamber (7) and lower chambers (9)
In be provided with for cooling agent flowing guided or current limliting throttling element.
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109273105A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of supercritical carbon dioxide reactor fuel assemblies |
| CN110828006A (en) * | 2019-11-18 | 2020-02-21 | 中国核动力研究设计院 | Coolant staggered flowing type fuel assembly and supercritical water cooled reactor |
| 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 |
| CN110853771A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Supercritical water-cooled reactor based on stacked fuel assembly |
| CN110867260A (en) * | 2019-11-21 | 2020-03-06 | 中国核动力研究设计院 | Supercritical water-cooled reactor based on combined type fuel element |
| CN111916232A (en) * | 2020-08-13 | 2020-11-10 | 中国核动力研究设计院 | Light water nuclear reactor structure |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001004774A (en) * | 1999-06-22 | 2001-01-12 | Yoshiaki Oka | Supercritical pressure light water cooled fast reactor |
| JP2003139881A (en) * | 2001-10-30 | 2003-05-14 | Toshiba Corp | Reactor cooled with supercritical pressure water, channel box, water rod and fuel assembly |
| 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 |
| CN103093838A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same |
-
2016
- 2016-11-25 CN CN201611059693.7A patent/CN106448756B/en active Active
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2001004774A (en) * | 1999-06-22 | 2001-01-12 | Yoshiaki Oka | Supercritical pressure light water cooled fast reactor |
| JP2003139881A (en) * | 2001-10-30 | 2003-05-14 | Toshiba Corp | Reactor cooled with supercritical pressure water, channel box, water rod and fuel assembly |
| 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 |
| CN103093838A (en) * | 2013-01-15 | 2013-05-08 | 西安交通大学 | Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109273105A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of supercritical carbon dioxide reactor fuel assemblies |
| CN109273105B (en) * | 2018-09-13 | 2022-03-25 | 中国核动力研究设计院 | Supercritical carbon dioxide reactor fuel assembly |
| CN110828006A (en) * | 2019-11-18 | 2020-02-21 | 中国核动力研究设计院 | Coolant staggered flowing type fuel assembly and supercritical water cooled reactor |
| 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 |
| CN110828006B (en) * | 2019-11-18 | 2021-08-24 | 中国核动力研究设计院 | Coolant staggered flowing type fuel assembly and supercritical water cooled reactor |
| CN110853771A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Supercritical water-cooled reactor based on stacked fuel assembly |
| CN110867260A (en) * | 2019-11-21 | 2020-03-06 | 中国核动力研究设计院 | Supercritical water-cooled reactor based on combined type fuel element |
| CN111916232A (en) * | 2020-08-13 | 2020-11-10 | 中国核动力研究设计院 | Light water nuclear reactor structure |
| CN111916232B (en) * | 2020-08-13 | 2022-03-01 | 中国核动力研究设计院 | Light water nuclear reactor structure |
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