CN114446496A - Ultra-high flux reactor core based on annular fuel element - Google Patents
Ultra-high flux reactor core based on annular fuel element Download PDFInfo
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- CN114446496A CN114446496A CN202210147490.2A CN202210147490A CN114446496A CN 114446496 A CN114446496 A CN 114446496A CN 202210147490 A CN202210147490 A CN 202210147490A CN 114446496 A CN114446496 A CN 114446496A
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- 239000000446 fuel Substances 0.000 title claims abstract description 103
- 230000004907 flux Effects 0.000 title claims abstract description 39
- 230000000712 assembly Effects 0.000 claims abstract description 43
- 238000000429 assembly Methods 0.000 claims abstract description 43
- 238000005253 cladding Methods 0.000 claims description 16
- 239000002826 coolant Substances 0.000 claims description 11
- 239000006096 absorbing agent Substances 0.000 claims description 9
- 238000001816 cooling Methods 0.000 claims description 8
- 239000000463 material Substances 0.000 claims description 7
- 229910052580 B4C Inorganic materials 0.000 claims description 3
- 229910008894 U—Mo Inorganic materials 0.000 claims description 3
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 3
- 229910052726 zirconium Inorganic materials 0.000 claims description 3
- 229910052751 metal Inorganic materials 0.000 claims description 2
- 239000002184 metal Substances 0.000 claims description 2
- 238000010276 construction Methods 0.000 abstract description 3
- 238000012360 testing method Methods 0.000 description 13
- 230000009286 beneficial effect Effects 0.000 description 9
- 238000013461 design Methods 0.000 description 4
- 239000007788 liquid Substances 0.000 description 4
- 229910001220 stainless steel Inorganic materials 0.000 description 4
- 239000010935 stainless steel Substances 0.000 description 4
- 229910052797 bismuth Inorganic materials 0.000 description 3
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 description 3
- 238000011161 development Methods 0.000 description 3
- 238000011160 research Methods 0.000 description 3
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 3
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 229910052770 Uranium Inorganic materials 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 241000723353 Chrysanthemum Species 0.000 description 1
- 235000005633 Chrysanthemum balsamita Nutrition 0.000 description 1
- 230000002745 absorbent Effects 0.000 description 1
- 239000002250 absorbent Substances 0.000 description 1
- 230000007812 deficiency Effects 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- -1 i.e. Substances 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 239000011148 porous material Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
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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
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
- G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
-
- 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
- G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
-
- 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
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses an ultrahigh flux reactor core based on an annular fuel element, which relates to the technical field of nuclear reactors and has the technical scheme key points that: the reactor core comprises a reflecting layer and a reactor core active area arranged in the reflecting layer, and is characterized in that the reactor core active area is provided with a plurality of fuel assemblies and a plurality of control rod assemblies; the sections of the fuel assembly and the control rod assembly are both hexagonal; a plurality of said fuel assemblies are arranged in a compact arrangement with a plurality of control rod assemblies arranged in the periphery of the core active area. The reactor core has a thermal power of no more than 200MW, a refueling period of no less than 100 full power days, and an average power density of no more than 1200MW/m3In the case of (1) to (10) the maximum neutron flux of the core16n/cm2And/s, the maximum neutron flux of the reactor core is far higher than that of the reactor under construction or planning at present, and the reactor has high advancement and competitiveness.
Description
Technical Field
The present invention relates to the field of nuclear reactor technology, and more particularly, it relates to an ultra-high flux reactor core based on annular fuel elements.
Background
Nuclear power engineering has evolved without departing from nuclear reactors, while nuclear reactors have evolved without departing from test reactors. The test reactor plays an important role in the development of various reactor types. The high neutron flux engineering test reactor is one of the important marks of national science and technology strength, and is essential infrastructure and an important tool for national independent and independent nuclear energy development. These depend on the neutron flux level of the test reactor, and the higher the neutron flux, the better the irradiation and isotope production, etc.
At present, the neutron flux of the internationally established advanced test reactor is 1.0 multiplied by 1015n/cm2In the order of/s, the flux exceeds 2.0 x 1015n/cm2The test piles per s are few. Typical advanced test stacks are the chinese advanced research stack (CARR stack) and the french JHR stack. CARR reactor using U3Si2Al dispersed plate fuel, square box fuel assembly forming square grid, U-235 enrichment of 20%, core uranium density of 4.0gU/cm3. Be is filled between the reactor core container and the fuel assemblies, and a heavy water reflecting layer annular water tank is arranged outside the reactor core container. JHR stack adopts U3Si2-Al cylindrical fuel and daisy type grid arrangement with a U-235 enrichment of 27% and a core uranium density of 4.8gU/cm3. Be is selected as a reflecting layer at the periphery of the reactor core.
The new generation advanced test reactor design gradually adopts the fourth generation reactor type, for example, the high flux reactor MBIR which is expected to be constructed in Russia belongs to the concept of sodium-cooled fast reactor, the thermal power is 150MW, and the maximum fast neutron flux level is 5.3 multiplied by 1015n/cm2And s. Currently, the atton national laboratory is working on developing a conceptual design of a radiation test stack called a multifunctional test stack (VTR). VTR belongs to the concept of sodium-cooled fast reactor, the thermal power of the reactor is 300MW, and the maximum fast neutron flux level is 4.0 multiplied by 1015n/cm2S; the reflecting layer design of the existing novel test reactor usually adopts a depleted uranium or stainless steel material, and the overall neutron flux level is limited.
However, the higher the flux and the greater the core power density, the higher the temperature of the fuel core and the cladding temperature will increase, which requires that the coolant have sufficient capacity to carry away heat while ensuring that the maximum fuel core temperature and the cladding temperature are a sufficient safety distance from the respective melting limits. It is therefore of great interest to develop an ultra high flux reactor core based on annular fuel elements that overcomes the above-mentioned drawbacks.
Disclosure of Invention
To overcome the deficiencies of the prior art, it is an object of the present invention to provide an ultra high flux reactor core based on annular fuel elements having an average module power density of no more than 1200MW/m with a thermal power of no more than 200MW, a refueling cycle of no less than 100 full power days3Under the condition that the maximum neutron flux in the reactor core exceeds 1 x 1016n/cm2And/s, greatly improves the development of material irradiation examination and solves the domestic important and scarce isotope production problem.
The technical purpose of the invention is realized by the following technical scheme: the ultrahigh-flux reactor core based on the annular fuel elements comprises a reflecting layer and a core active area arranged in the reflecting layer, wherein the core active area is provided with a plurality of fuel assemblies and a plurality of control rod assemblies;
the sections of the fuel assembly and the control rod assembly are both hexagonal;
a plurality of said fuel assemblies are arranged in a compact arrangement with a plurality of control rod assemblies arranged in the periphery of the core active area.
Further, the core active area is provided with fifty-two fuel assemblies and nine control rod assemblies;
fifty-two fuel assemblies and nine control rod assemblies form a hexagon with a five-circle structure, and are rotationally symmetrical at 120 degrees;
the nine control rod assemblies are divided into three groups, the three control rod assemblies are respectively arranged on three sides of the hexagon at intervals, and the three control rod assemblies on each side are arranged at intervals of one fuel assembly.
Further, the fuel assembly includes a plurality of fuel elements and a first assembly cartridge enclosing the fuel elements;
cooling flow channels for flowing of cooling agents are formed among the fuel elements, the fuel elements are arranged in a triangular structure, and the cross sections of the fuel elements are annular;
the fuel element comprises an inner cladding, a fuel core and an outer cladding which are sequentially arranged from inside to outside, wherein a cooling flow channel for flowing of a coolant is formed inside the inner cladding.
Furthermore, the distance between the opposite sides of the fuel assembly is 90mm-95mm, and 61 fuel elements are arranged in the fuel assembly.
Further, the outer diameter of the fuel core is 8.0mm-10.0mm, and the thickness of the fuel core is 1.0mm-3.0 mm.
Furthermore, the fuel assembly is prepared from any one metal fuel of U-Zr, U-Mo and U-Pu-Zr.
Further, the control rod assembly includes a plurality of control rods and a second assembly cassette enclosing the control rods;
each control rod comprises an absorber and a guide pipe sleeved on the outer wall of the absorber;
the absorber is cylindrical and is prepared from a boron carbide material.
Further, the radial outer shape of the reflecting layer is circular, and the outer diameter of the reflecting layer is not less than 2000 mm.
Further, the height of the core active area is 400mm-500mm, and the thickness of the reflecting layer at the two ends of the core active area is 500mm-1000 mm.
Further, the reactor core of the ultra-high flux reactor has an average module power density of not more than 1200MW/m when the thermal power is not more than 200MW, the refueling period is not less than 100 full power days3Under the condition that the maximum neutron flux in the reactor core exceeds 1 x 1016n/cm2/s。
Compared with the prior art, the invention has the following beneficial effects:
1. the reactor core of the ultrahigh-flux reactor based on the annular fuel element provided by the invention has the advantages that the average power density of the reactor core does not exceed 1200MW/m when the thermal power of the reactor core does not exceed 200MW, the refueling period is not less than 100 full-power days3In the case of (1) to (10) the maximum neutron flux of the core16n/cm2The maximum neutron flux of the reactor core is far higher than that of the reactor under construction or planning at present, and the reactor core has high advancement and competitiveness;
2. the center of the annular fuel element is provided with the cooling flow channel, so that the heat of the reactor core can be effectively taken away, the temperature of the fuel core body, the inner cladding and the outer cladding can be reduced, and the safety of the reactor core is improved;
3. the invention designs the size of the reflecting layer area, which is beneficial to developing various researches, such as arrangement of pore channels and loops with various purposes, and simultaneously, because the reflecting layer is made of the same material as the coolant, a large amount of coolant in the reflecting layer is also beneficial to ensuring the safety of the reactor core.
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 the distribution of core loading in an embodiment of the present invention;
FIG. 2 is an axial schematic view of the core in an embodiment of the invention.
FIG. 3 is a schematic structural view of a fuel assembly in an embodiment of the present invention;
FIG. 4 is a schematic structural view of a fuel element in an embodiment of the invention;
FIG. 5 is a schematic structural view of a control rod assembly in an embodiment of the present invention;
reference numbers and corresponding part names in the drawings:
1. a first component cartridge; 2. a fuel element; 3. a cooling flow channel; 4. an outer envelope; 5. a fuel core; 6. an inner envelope; 7. a guide tube; 8. an absorbent body; 9. a control rod assembly; 10. a fuel assembly; 11. a core active area; 12. a reflective layer; 13. a second component cartridge.
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.
It will be understood that when an element is referred to as being "secured to" or "disposed on" another element, it can be directly on the other element or be indirectly on the other element. When an element is referred to as being "connected to" another element, it can be directly or indirectly connected to the other element.
It will be understood that the terms "length," "width," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," and the like, as used herein, refer to an orientation or positional relationship indicated in the drawings that is solely for the purpose of facilitating the description and simplifying the description, and do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed and operated in a particular orientation, and is therefore not to be construed as limiting the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically defined otherwise.
Example (b): as shown in fig. 1 and 2, the ultrahigh-flux reactor core based on annular fuel elements includes a reflective layer 12 and a core active region 11 disposed in the reflective layer 12, wherein the core active region 11 is provided with a plurality of fuel assemblies 10 and a plurality of control rod assemblies 9, and is cooled by liquid lead or liquid lead bismuth. The fuel assembly 10 and the control rod assembly 9 are hexagonal in cross section. A plurality of fuel assemblies 10 are arranged in a compact manner to reduce core leakage. The plurality of control rod assemblies 9 are arranged at the periphery of the core active area 11 to control the power distribution of the peripheral assemblies and improve the power density of the fuel assemblies 10 in the central area, which is beneficial to improving the maximum neutron flux density of the core.
As shown in fig. 1, the core active area 11 is provided with fifty-two fuel assemblies 10 and nine control rod assemblies 9; fifty-two fuel assemblies 10 and nine control rod assemblies 9 form a five-turn hexagonal shape and are rotationally symmetric at 120 degrees; the nine control rod assemblies 9 are divided into three groups, the three groups of control rod assemblies 9 are respectively arranged on three sides which are arranged in the hexagon at intervals, and the three control rod assemblies 9 on each side are arranged at intervals of one fuel assembly 10.
As shown in fig. 3, the fuel assembly 10 includes a plurality of fuel elements 2 and a first assembly case 1 surrounding the fuel elements 2, the first assembly case 1 being prepared from stainless steel, and the fuel core 5 having stainless steel cladding on both sides. The fuel elements 2 form cooling flow channels 3 for flowing coolant, the fuel elements 2 are arranged in a triangular structure, and the cross section of each fuel element 2 is annular. As shown in fig. 4, the fuel element 2 includes an inner cladding 6, a fuel core 5 and an outer cladding 4 which are arranged in sequence from inside to outside, and a cooling flow channel 3 for flowing a coolant is formed inside the inner cladding 6, which is beneficial to reducing the temperature of the fuel.
As shown in fig. 3, in the present embodiment, the distance between opposite sides of the fuel assembly 10 is 90mm to 95mm, 61 fuel elements 2 are arranged in the fuel assembly 10, and the 61 fuel elements 2 are distributed in a five-ring structure.
In the present embodiment, the outer diameter of the fuel core 5 is 8.0mm to 10.0mm, preferably 9.0mm, and the thickness of the fuel core 5 is 1.0mm to 3.0 mm.
The fuel assembly 10 is prepared from any one of U-Zr, U-Mo and U-Pu-Zr, the adoption of the fuel containing Pu is favorable for improving the maximum neutron flux density, and the cladding is made of stainless steel and has good compatibility with a lead bismuth (or lead-based) coolant.
As shown in fig. 5, the control rod assembly 9 includes a plurality of control rods and a second assembly cassette 13 enclosing the control rods; each control rod comprises an absorber 8 and a guide pipe 7 sleeved on the outer wall of the absorber 8; the absorber 8 is cylindrical and is made of boron carbide material.
The radial outer shape of the reflective layer 12 is circular, and the outer diameter of the reflective layer 12 is not less than 2000mm, in this embodiment, the outer diameter of the reflective layer 12 is 2000 mm. The components of the reflector layer 12 are made of the same material as the coolant, i.e., liquid lead or liquid lead bismuth, and are arranged in the axial direction and the radial direction to occupy a large area, which is beneficial to reducing the core leakage and simultaneously beneficial to arranging ducts and loops for various purposes in the reflector layer 12.
The height of the core active area 11 is 400mm-500 mm. In the present embodiment, the height of the core active region 11 is 450mm, and the lower height of the active region is beneficial to reducing the maximum cladding temperature and is more beneficial to the core safety.
The thickness of the reflecting layer 12 at both ends of the core active region 11 is 500mm to 1000 mm. In the present embodiment, the thickness of the reflective layer 12 at both ends of the core active region 11 is 500 mm.
For a core formed by 52 boxes of fuel assemblies 10, the thermal power is 200MW, the refueling period is 100 full-power days, and the maximum neutron flux in the refueling period is 1.05 multiplied by 1016n/cm2S, average module power density 1100MW/m3. The indexes of the invention are far beyond the level of the current international test piles and the level of the international advanced test concept piles under research.
The working principle is as follows: the reactor core has a thermal power of no more than 200MW, a refueling period of no less than 100 full power days, and an average power density of no more than 1200MW/m3In the case of (1) to (10) the maximum neutron flux of the core16n/cm2And/s, the maximum neutron flux of the reactor core is far higher than that of the reactor under construction or planning at present, and the reactor has high advancement and competitiveness.
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 (10)
1. The ultrahigh-flux reactor core based on the annular fuel elements comprises a reflecting layer (12) and a reactor core active area (11) arranged in the reflecting layer (12), and is characterized in that the reactor core active area (11) is provided with a plurality of fuel assemblies (10) and a plurality of control rod assemblies (9);
the sections of the fuel assembly (10) and the control rod assembly (9) are both hexagonal;
a plurality of said fuel assemblies (10) are arranged compactly, and a plurality of control rod assemblies (9) are arranged in the periphery of the core active area (11).
2. The annular fuel element-based ultrahigh flux reactor core according to claim 1 wherein the core active area (11) is provided with fifty-two fuel assemblies (10) and nine control rod assemblies (9);
fifty-two fuel assemblies (10) and nine control rod assemblies (9) form a hexagon with a five-circle structure, and are in 120-degree rotational symmetry;
the nine control rod assemblies (9) are divided into three groups, the three groups of control rod assemblies (9) are respectively arranged on three sides of the hexagon at intervals, and the three control rod assemblies (9) on each side are arranged at intervals of one fuel assembly (10).
3. The annular fuel element-based ultrahigh flux reactor core according to claim 1, wherein the fuel assembly (10) comprises a plurality of fuel elements (2) and a first assembly box (1) surrounding the fuel elements (2);
cooling flow channels (3) for flowing of coolant are formed among the fuel elements (2), the fuel elements (2) are arranged in a triangular structure, and the cross sections of the fuel elements (2) are annular;
the fuel element (2) comprises an inner cladding (6), a fuel core body (5) and an outer cladding (4) which are sequentially arranged from inside to outside, and a cooling flow channel (3) for flowing of a coolant is formed in the inner cladding (6).
4. The annular fuel element-based ultrahigh flux reactor core according to claim 3, wherein the fuel assemblies (10) are spaced 90mm to 95mm apart on opposite sides, and 61 fuel elements (2) are provided in the fuel assemblies (10).
5. The ultra high flux reactor core based on annular fuel elements according to claim 3, wherein the outer diameter of the fuel core (5) is 8.0mm-10.0mm and the thickness of the fuel core (5) is 1.0mm-3.0 mm.
6. The ultra high flux reactor core based on annular fuel elements of claim 3, wherein the fuel assembly (10) is made of any one of metal fuels of U-Zr, U-Mo and U-Pu-Zr.
7. The ultra high flux annular fuel element-based reactor core according to claim 1, wherein the control rod assembly (9) comprises a plurality of control rods and a second assembly box (13) surrounding the control rods;
each control rod comprises an absorber (8) and a guide pipe (7) sleeved on the outer wall of the absorber (8);
the absorber (8) is cylindrical and is prepared from a boron carbide material.
8. The ultra high flux reactor core based on annular fuel elements according to any of claims 1 to 7, wherein the outer shape of the reflecting layer (12) in the radial direction is circular and the outer diameter of the reflecting layer (12) is not less than 2000 mm.
9. The ultra high flux reactor core based on annular fuel elements according to any one of claims 1 to 7, wherein the height of the core active region (11) is 400mm to 500mm, and the thickness of the reflective layer (12) at both ends of the core active region (11) is 500mm to 1000 mm.
10. The ultra-high flux reactor core based on annular fuel elements of any of claims 1 to 7, wherein the ultra-high flux reactor core has an average module power density of not more than 1200MW/m at a thermal power of not more than 200MW, a refueling cycle of not less than 100 full power days3Under the condition that the maximum neutron flux in the reactor core exceeds 1 x 1016n/cm2/s。
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115394458A (en) * | 2022-08-26 | 2022-11-25 | 中国核动力研究设计院 | Ultra-high flux reactor core based on rod bundle type fuel assembly |
| CN115394459A (en) * | 2022-08-26 | 2022-11-25 | 中国核动力研究设计院 | Ultrahigh flux reactor core based on plate-shaped fuel assembly |
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