CN110853773A - Axial reverse-charging metal cooling reactor and management method - Google Patents
Axial reverse-charging metal cooling reactor and management method Download PDFInfo
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- CN110853773A CN110853773A CN201911149861.5A CN201911149861A CN110853773A CN 110853773 A CN110853773 A CN 110853773A CN 201911149861 A CN201911149861 A CN 201911149861A CN 110853773 A CN110853773 A CN 110853773A
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- fuel
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- 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
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/328—Relative disposition of the elements in the bundle lattice
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- 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
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/3262—Enrichment distribution in zones
- G21C3/3267—Axial distribution
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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
Abstract
The invention discloses an axial reverse refueling metal cooling reactor and a management method thereof. The fuel assembly channel is provided with 3 standard fuel assemblies in the axial direction, the bottom layer is an old fuel assembly which passes through a plurality of burnup cycles, and the top layer is a new fuel assembly which is loaded into a reactor core. After the old fuel assemblies are unloaded from the channels of each fuel assembly, the axial residual fuel assemblies in the channels move downwards in sequence, and the new fuel assemblies are loaded from the tops of the channels. The invention effectively flattens the axial and radial power distribution of the reactor core, makes the burnup of the fuel assembly more uniform, greatly prolongs the service life of the fuel assembly, and increases the service life of the fuel assembly and the average unloading burnup depth of the reactor core.
Description
Technical Field
The invention relates to the technical field of nuclear reactors, in particular to an axial refueling metal cooling reactor and a management method.
Background
Based on a closed uranium plutonium fuel circulation system, the liquid metal cooling reactor has strong capacity in nuclear fuel transmutation and nuclear fuel proliferation, and has an important effect on nuclear energy sustainable development. For this reason, various countries in the world develop various liquid metal cooled reactors with different power scales, such as the American modular sodium cooled fast reactor SMFR, Japanese sodium cooled fast reactor JSFR, Russian sodium cooled fast reactor BN600/800, Chinese sodium cooled fast reactor CFR600, Russian small-sized lead bismuth cooled SVBR-75/100, pure lead cooled BREST-OD-300 fast reactor, European lead cooled ELSY fast reactor, and so on, and at present, part of the liquid metal cooled reactors enter the prototype reactor verification stage. The pressure of the liquid metal cooling reactor system is slightly higher than the normal pressure, the inlet temperature of the reactor core is above 330 ℃, the outlet temperature is above 500 ℃, and the fuel is high-enrichment UO2Or MOX fuel, the neutron spectrum is fast. Compared with a light water reactor, the liquid metal cooling reactor has the remarkable characteristics of large average power density, large neutron leakage and the like. Since liquid metal cooled reactors typically employ control rods to control core backup reactivity, i.e., insertion from the top of the core, the upper core power contribution is lower and the lower core power contribution is higher. Therefore, at the end of the cycle, the burnup distribution of the reactor core is very uneven, the upper burnup of the fuel assembly is shallow, and the lower burnup of the fuel assembly is deep, so that the average unloading burnup depth of the fuel assembly is reduced, and the nuclear fuel transmutation and proliferation capacity and the economy of the metal-cooled reactor are seriously influenced. Therefore, it is very necessary to search for a better method for managing the core fuel of the liquid metal cooling reactor, so as to improve the average core discharge depth, reduce the non-uniformity of the axial burnup distribution of the fuel assemblies, and improve the service life of the fuel assemblies and the average core discharge burnup depth without breaking through the design limit of the fuel assemblies.
Disclosure of Invention
The invention aims to provide an axial reverse-refueling metal-cooled reactor and a management method, which solve the problem of non-uniformity of axial burnup distribution of the conventional liquid metal-cooled reactor, prolong the service life of a fuel assembly, improve the average unloading burnup depth of a reactor core and enhance the transmutation and proliferation capacity of nuclear fuel under the condition of not changing the burnup limit value of the conventional fuel assembly.
The invention is realized by the following technical scheme:
the axial refueling metal cooling reactor has a reactor core structure of an integral regular hexagon channel, wherein the regular hexagon channel comprises a control rod assembly channel and a fuel assembly channel, and the control rod assembly channel and the fuel assembly channel are uniformly and alternately arranged to improve the backup reactivity control capability of the reactor core; 3 fuel assemblies are arranged in the fuel assembly channel in an axial superposition mode; a guide tube is arranged in the control rod assembly channel, and a control rod assembly consisting of 7 control rod neutron absorbers is inserted into the guide tube; the outer side of the reactor core is provided with an integral metal reflecting layer, the inner side of the integral metal reflecting layer is matched with the integral regular hexagonal channel, control rods are inserted into the reactor core from the top of the reactor, the periphery and the top of the reactor core are low-power areas, and the middle lower part of the reactor core is a high-power area.
The reactor core is discharged from the reactor core through a plurality of burnup cycles, fuel assemblies which are positioned at the bottommost part of each assembly channel and reach or approach to a burnup limit value, residual fuel assemblies in the channels move downwards in sequence, and new fuel assemblies are loaded into corresponding fuel assembly channels from the top of the reactor core; then, radial reversal is carried out on fuel assemblies at the bottommost layer and the middle layer of the reactor core, and on the premise of flattening radial power distribution, the deep-burning fuel assemblies are transferred to the periphery of the reactor core, and the shallow-burning fuel assemblies are transferred to the inside of the reactor core. Therefore, the reactor core power peak factor is greatly reduced, the three-dimensional power distribution and the burnup distribution of the reactor core are flatter, the average unloading burnup depth of the reactor core is increased within the range of the burnup design limit value of the fuel assembly, the service life of the fuel assembly and the utilization rate of nuclear fuel are obviously improved, and the fuel economy and the market competitiveness are enhanced.
Furthermore, the fuel assembly is composed of a plurality of fuel rods, positioning tubes and instrument tubes, wherein the fuel rods and the positioning tubes are arranged according to regular triangle grids to form a regular hexagon fuel assembly; the positioning pipes are arranged at the 6 corner points of the fuel assemblies, the thickness of the pipe wall is 1.0-3.0 mm, and the positioning pipes are used for maintaining the geometric shapes of the fuel assemblies and the accurate alignment of each fuel assembly in the axial direction of the assembly channel; the instrument tube is arranged at the center of the fuel assembly, occupies 7 bar grid positions, has the tube wall thickness of 1.0-3.0 mm, and is used for being inserted into various measuring instruments and bearing the weight of the fuel assembly.
According to the invention, the control rod assembly guide tube with the outer square and the inner circle is inserted into the control rod assembly channel, and 1 bundle of control rods consisting of 7 rod-shaped neutron absorbers are arranged in the guide tube, so that the outer surface area of the control rod absorbers can be effectively increased, the neutron absorption capacity is improved, the reactor core reactivity control capacity is enhanced, and the weight of the control rod assembly can be reduced.
Further, the core of the reactor consists of 163 regular hexagonal channels, including 18 control rod assembly channels, 145 fuel assembly channels. The center distance between adjacent hexagonal channels is 139mm, the wall thickness of the fuel assembly channel is 2.0mm, and the wall thickness of the control rod assembly channel is 3.0 mm-6.0 mm.
A management method for an axial reverse-charging metal cooling reactor is characterized by comprising the following steps:
1) the bottommost layer of the fuel assembly channel is a fuel assembly with deeper fuel consumption after a plurality of fuel consumption cycles, and the topmost layer is a fuel assembly with shallower fuel consumption; after the bottommost layer deep-burned fuel assemblies reaching the design limit value or the service life are discharged out of the reactor core from the fuel assembly channels, the axial residual fuel assemblies in the channels move downwards in sequence, and new fuel assemblies are loaded from the tops of the channels;
2) the lowest layer and the middle layer fuel assemblies of all the fuel assembly channels of the reactor core are subjected to radial material reversing, namely the fuel assembly channels where the lowest layer fuel assemblies are mutually exchanged are arranged, the fuel assembly channels where the middle layer fuel assemblies are mutually exchanged are arranged, the fuel assemblies with deeper burnup are transferred into the fuel assembly channels at the periphery of the reactor core, and the fuel assemblies with shallower burnup are transferred into the fuel assembly channels in the reactor core.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the invention fully considers the high power density metal cooling reactor, because of the non-uniformity of axial power distribution and burnup distribution of the reactor core caused by the insertion of the control rod into the reactor core, 3 layers of fuel assemblies are arranged along the axial direction of the reactor core, the bottommost layer is an old fuel assembly which passes through a plurality of burnup cycles, and the topmost layer is a new fuel assembly which is loaded into the reactor core. After the old fuel assemblies are unloaded from the channels of each fuel assembly, the axial residual fuel assemblies in the channels move downwards in sequence, and the new fuel assemblies are loaded from the tops of the channels. The new fuel assemblies have larger residual reactivity and can increase the power share of the upper part of the reactor core, the residual reactivity of the old fuel assemblies is smaller, and the power share of the lower part of the reactor core can be reduced, so that the axial power distribution and the burnup distribution of the reactor core can be effectively flattened. And secondly, performing radial material reversing on each layer of fuel assemblies of the reactor core, transferring deep fuel-consuming fuel assemblies to the periphery of the reactor core, transferring shallow fuel-consuming fuel assemblies to the inside of the reactor core, and further flattening the fuel-consuming depth of the fuel assemblies. Therefore, the reactor core axial and radial power distribution is effectively flattened, the fuel consumption of the fuel assembly is more uniform, the service life of the fuel assembly is greatly prolonged under the condition of not breaking through the fuel consumption design limit value of the fuel assembly, the service life of the fuel assembly and the average unloading fuel consumption depth of the reactor core are increased, and the nuclear fuel transmutation and proliferation capacity and the fuel economy of the metal-cooled reactor are obviously improved.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic illustration of a core passageway and loading arrangement;
FIG. 2 is a schematic view of a control rod assembly passage;
FIG. 3 is a schematic view of a hexagonal fuel assembly;
FIG. 4 is a schematic view of the axial arrangement of fuel assembly passages.
Reference numbers and corresponding part names in the drawings:
1-integral metal reflecting layer, 2-fuel assembly channel, 3-control rod assembly channel, 4-guide tube, 5-control rod neutron absorber, 6-control rod assembly, 7-positioning tube, 8-fuel rod, 9-instrument tube and 10-fuel assembly.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Example 1:
as shown in fig. 1-4, the core structure of the axial refueling metal-cooled reactor is an integral honeycomb-shaped regular hexagonal assembly channel which comprises 163 regular hexagonal channels including 145 fuel assembly channels 2 and 18 control rod assembly channels 3, and an integral metal reflecting layer 1 is arranged outside the core. The control rod assembly channel 3 is internally provided with a guide tube 4 of the control rod assembly with the shape of 'square outside and round inside', and the inner diameter is 125 mm. The center distance between adjacent hexagonal channels is 139mm, and the wall thickness of the fuel assembly channel 2 and the wall thickness of the control rod assembly channel 3 are both 2.0 mm. The fuel assembly channel 2 is provided with 3 fuel assemblies 10 in the axial direction; the outer side of the integral honeycomb-shaped regular hexagonal assembly channel is provided with an integral metal reflecting layer 1, the average thickness of the integral metal reflecting layer 1 is 150mm, and the main structure of the reactor core and the material of the reflecting layer are both stainless steel; the height of the active area of the fuel assembly 10 is 300.0mm, and the heights of the tube seats at the upper end and the lower end are both 30.0 mm; the fuel assembly 10 is composed of a plurality of fuel rods 8, positioning tubes 7 and instrument tubes 9, wherein the fuel rods 8 and the positioning tubes 7 are arranged according to regular triangle grids to form a hexagonal fuel assembly; the positioning pipe 7 is arranged at 6 corner points of the fuel assembly, and the thickness of the pipe wall is 1.0-3.0 mm; the instrument tube 9 is positioned at the center of the fuel assembly 10, occupies the grid positions of a plurality of fuel rods 8, has the tube wall thickness of 2.0-3.0 mm, and can be inserted into various measuring instruments, burnable poison rods and the like; the materials of the guide tube 4, the fuel rod cladding 8, the positioning tube 7 and the instrument tube 9 are all stainless steel.
The outer diameter of the fuel rod 8 is 8.0mm, the cladding thickness is 0.60mm, the core diameter is 7.6mm, and the core material is enriched uranium dioxide or uranium plutonium mixed oxide fuel; the diameter of the control rod neutron absorber 5 is 30.0mm, and the outer diameter of the control rod assembly 6 is 120 mm. The thermal power of the axial refueling liquid metal cooling reactor is 300MW, the diameter of the circumscribed circle is 1310mm, the total height of the fuel active region is 900mm, and the bulk power density is 135.5MW/m3Cycle length 1500 is equivalent to full power days. The main design parameters of the reactor core are shown in the table 1.
An axial refueling method for an axial refueling metal cooled reactor as described in example 1, comprising the steps of:
1) 3 layers of fuel assemblies are respectively X-1, X-2 and X-3 which are arranged along the axial direction of the reactor core, the bottommost layer is the fuel assembly X-3 which has deeper fuel consumption and passes through a plurality of fuel consumption cycles, and the topmost layer is the fuel assembly X-1 which has shallower fuel consumption. After the fuel assemblies X-3 are discharged from all the fuel assembly channels, the axial residual fuel assemblies X-1 and X-2 in the channels move downwards in sequence, namely the serial numbers of the fuel assemblies X-1 and X-2 are converted into the fuel assemblies X-2 and X-3, and new fuel assemblies are loaded from the tops of all the channels, wherein the serial number is X-1. The new fuel assemblies have higher residual reactivity and can increase the power share of the upper part of the reactor core, the old fuel assemblies have lower residual reactivity and can reduce the power share of the lower part of the reactor core, and therefore the axial power distribution and the fuel consumption distribution of the reactor core are effectively flattened;
2) and (2) performing radial material reversing aiming at each layer of fuel assemblies of the reactor core, performing mutual exchange among the X-2 fuel assemblies and the X-3 fuel assemblies of each channel, transferring the fuel assemblies with deeper burn-up to the periphery of the reactor core, transferring the fuel assemblies with shallower burn-up to the inside of the reactor core, and further flattening the burn-up depth of the fuel assemblies.
TABLE 1 core Primary design parameters
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (3)
1. The axial refueling metal cooled reactor is characterized in that the core structure of the reactor is an integral regular hexagon channel, the regular hexagon channel comprises a control rod assembly channel (3) and a fuel assembly channel (2), and the control rod assembly channel (3) and the fuel assembly channel (2) are uniformly and alternately arranged; 3 fuel assemblies (10) are arranged in the fuel assembly channel (2) in an axially overlapped mode; a guide tube (4) is arranged in the control rod assembly channel (3), and a control rod assembly (6) consisting of 7 control rod neutron absorbers (5) is inserted into the guide tube (4); the outer side of the reactor core is provided with an integral metal reflecting layer (1), and the inner side of the integral metal reflecting layer (1) is matched with the integral regular hexagonal channel.
2. An axial refueling metal cooled reactor as claimed in claim 1, wherein the fuel assembly (10) is composed of a plurality of fuel rods (8), spacer tubes (7) and instrumentation tubes (9), the fuel rods (8) and spacer tubes (7) being arranged uniformly in a regular triangular grid; the positioning tubes (7) are arranged at 6 angular points of the fuel assemblies (10), maintaining the geometry of the fuel assemblies (10) and the precise alignment of axially adjacent fuel assemblies (10); the instrument tube (9) is arranged in the center of the fuel assembly (10), and the instrument tube (9) is used for inserting a measuring instrument and bears the whole weight of the fuel assembly (10).
3. A method of managing an axially reversed fuel metal cooled reactor according to claim 1 or 2, characterized in that it comprises the following steps:
1) the bottommost layer of the fuel assembly channel (2) is a fuel assembly (10) with deep burning through a plurality of burning cycles, and the topmost layer is a fuel assembly (10) with shallow burning; after the bottommost layer deep-burned fuel assemblies (10) reaching the design limit value or the service life are discharged out of the reactor core from the fuel assembly channel (2), the axial residual fuel assemblies (10) in the channel move downwards in sequence, and new fuel assemblies (10) are loaded from the top of each channel;
2) the lowest layer of each fuel assembly channel (2) of the reactor core and the middle layer fuel assemblies (10) are subjected to radial reverse refueling, namely the fuel assembly channels (2) of the lowest layer fuel assemblies (10) are mutually exchanged, the fuel assembly channels (2) of the middle layer fuel assemblies (10) are mutually exchanged, the fuel assemblies (10) with higher fuel consumption are transferred into the fuel assembly channels (2) at the periphery of the reactor core, and the fuel assemblies (10) with lower fuel consumption are transferred into the fuel assembly channels (2) in the reactor core.
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| CN201911149861.5A CN110853773A (en) | 2019-11-21 | 2019-11-21 | Axial reverse-charging metal cooling reactor and management method |
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2019
- 2019-11-21 CN CN201911149861.5A patent/CN110853773A/en active Pending
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| US20140064433A1 (en) * | 2012-08-31 | 2014-03-06 | Hitachi-Ge Nuclear Energy, Ltd. | Fuel Assembly and Core of Nuclear Reactor |
| CN106297907A (en) * | 2016-09-06 | 2017-01-04 | 中国核动力研究设计院 | A kind of pencil control rod structure |
| CN208400501U (en) * | 2018-07-19 | 2019-01-18 | 中国核电工程有限公司 | A kind of modular fuel assembly |
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