CN114121308A - Reactor core structure of lead bismuth cooling fast neutron research reactor with ultra-high flux - Google Patents
Reactor core structure of lead bismuth cooling fast neutron research reactor with ultra-high flux Download PDFInfo
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- 238000011160 research Methods 0.000 title claims abstract description 29
- 230000004907 flux Effects 0.000 title claims abstract description 24
- 229910052797 bismuth Inorganic materials 0.000 title claims abstract description 14
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 title claims abstract description 12
- 238000001816 cooling Methods 0.000 title claims abstract description 12
- 239000000446 fuel Substances 0.000 claims abstract description 105
- 238000000429 assembly Methods 0.000 claims abstract description 50
- 230000000712 assembly Effects 0.000 claims abstract description 50
- 239000000463 material Substances 0.000 claims abstract description 32
- 239000002826 coolant Substances 0.000 claims abstract description 26
- 239000011148 porous material Substances 0.000 claims abstract description 9
- 229910001093 Zr alloy Inorganic materials 0.000 claims abstract description 6
- NBWXXYPQEPQUSB-UHFFFAOYSA-N uranium zirconium Chemical compound [Zr].[Zr].[U] NBWXXYPQEPQUSB-UHFFFAOYSA-N 0.000 claims abstract description 6
- 238000004519 manufacturing process Methods 0.000 claims description 10
- 239000010935 stainless steel Substances 0.000 claims description 10
- 229910001220 stainless steel Inorganic materials 0.000 claims description 10
- 238000002474 experimental method Methods 0.000 claims description 9
- 239000008188 pellet Substances 0.000 claims description 7
- 229910052580 B4C Inorganic materials 0.000 claims description 6
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 claims description 6
- 229910000909 Lead-bismuth eutectic Inorganic materials 0.000 claims description 5
- 238000005253 cladding Methods 0.000 claims description 4
- 239000006023 eutectic alloy Substances 0.000 claims description 4
- QNRATNLHPGXHMA-XZHTYLCXSA-N (r)-(6-ethoxyquinolin-4-yl)-[(2s,4s,5r)-5-ethyl-1-azabicyclo[2.2.2]octan-2-yl]methanol;hydrochloride Chemical group Cl.C([C@H]([C@H](C1)CC)C2)CN1[C@@H]2[C@H](O)C1=CC=NC2=CC=C(OCC)C=C21 QNRATNLHPGXHMA-XZHTYLCXSA-N 0.000 claims description 3
- 239000006096 absorbing agent Substances 0.000 claims description 2
- 238000013461 design Methods 0.000 description 5
- 229910003460 diamond Inorganic materials 0.000 description 4
- 239000010432 diamond Substances 0.000 description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 3
- 229910052708 sodium Inorganic materials 0.000 description 3
- 239000011734 sodium Substances 0.000 description 3
- 230000004913 activation Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000001678 irradiating effect Effects 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000001956 neutron scattering Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
- 210000003934 vacuole Anatomy 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
- 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
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
- G21C3/332—Supports for spacer grids
-
- 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
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- 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
- G21C3/336—Spacer elements for fuel rods in the bundle
-
- 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
- G21C3/34—Spacer grids
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
- G21C3/60—Metallic fuel; Intermetallic dispersions
-
- 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)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The reactor core structure of the super-high-flux lead bismuth cooling fast neutron research reactor has the reactor core power of 200 MW; the reactor core radially consists of a fuel area, a radial reflecting layer and a radial shielding layer; the axial direction of the cooling device is composed of a coolant channel, a reflecting layer assembly and an upper end socket and a lower end socket of a shielding layer assembly; the fuel area comprises a fuel assembly, an irradiation pore channel, a control rod assembly and a safety rod assembly, and the four assemblies are densely paved by 6 circles of regular hexagons; the fuel assembly has Y-shaped 1/3 rotation symmetry and burns at each 1/3In the material assembly, the plate-shaped fuel and the coolant flux are alternately arranged; the fuel plate uses uranium zirconium alloy fuel with 10% of Zr mass content, and the U235 enrichment degree is 90%. The structure adopts the arrangement of specially designed plate-shaped fuel elements and the reactor core, can effectively improve the power density and the heat exchange capacity of the reactor core, can effectively improve the flux level and the material irradiation capacity of the reactor core, and can ensure that the peak value of the neutron fluence rate can reach 1.01 multiplied by 1016n/cm2s。
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to a reactor core structure of a super-high-flux lead bismuth cooling fast neutron research reactor.
Background
High-throughput research stacks are commonly used in the fields of radioisotope production and material irradiation experiments. Compared with a conventional research reactor and a conventional power reactor, the neutron flux level in the high-flux reactor is higher, and the reactor is provided with a specially designed irradiation space with a larger volume, so that the isotope production or material irradiation experiment with higher efficiency is facilitated.
Based on the advantages of the high-flux reactor, the method has wide application prospect in the fields of radioisotope production, material irradiation experiments, neutron activation, neutron scattering and the like. At present, the domestic high-flux research reactor mainly takes a thermopile and is mainly applied to the production of some radioactive isotopes; because the neutron energy spectrum in the reactor is soft, the material irradiation experiment capability is relatively poor. With the rapid development of the fourth-generation advanced nuclear energy system, the existing material irradiation experimental capability is revealed to be insufficient, and the research and development design of a new-generation high-throughput fast neutron research reactor is necessary. On the other hand, in view of the multifunctional requirements for material irradiation and isotope production, the fast neutron fluence rate of the reactor core still needs to be greatly improved. Therefore, the fast neutron research reactor with ultra-high flux has important application value.
Disclosure of Invention
In order to solve the problems, the invention provides a reactor core structure of a super-high-flux lead bismuth cooling fast neutron research reactor, and the neutron flux level in the reactor core is effectively improved through optimized material selection, fuel assembly structural design and reactor core structural design.
In order to achieve the purpose, the invention adopts the following technical scheme:
a core structure of a super-high-flux lead bismuth cooling fast neutron research reactor is disclosed, wherein the core is composed of a fuel area 1, a radial reflecting layer 2 and a radial shielding layer 3 in the radial direction; the reactor core is symmetrical along a horizontal mid-plane in the axial direction, the upper part and the lower part of the fuel region 1 are coolant channels 15, the upper part and the lower part of the radial reflecting layer 2 are reflecting layer upper and lower end sockets 16, and the upper part and the lower part of the radial shielding layer 3 are shielding layer upper and lower end sockets 17;
the fuel zone 1
Comprises a fuel assembly 4, an irradiation duct 5, a control rod assembly 6 and a safety rod assembly 7; the four types of assemblies are densely paved by 6 circles of regular hexagons, and 6 irradiation pore canals 5 or 6 internal reflection layer assemblies 8 are arranged at six corners of the outermost circle, belonging to the area of the radial reflection layer 2, so that the fuel area 1 has 85 assemblies in total; fuel assemblies 4 are uniformly distributed in 6 circles in the fuel area 1; the irradiation duct 5 replaces the fuel assemblies 4 at six corners of the third circle and three corners of the fifth circle which are spaced two by two, so that 9 or 15 irradiation ducts 5 are provided; the control rod assemblies 6 replace the fuel assemblies 4 at the middle position of the fifth turn, so that there are 6 control rod assemblies; the safety rod assemblies 7 replace the fuel assemblies 4 in the remaining three corners of the fifth turn, so there are 3 safety rod assemblies;
according to the reactor core structure of the ultra-high-flux lead-bismuth cooling fast neutron research reactor, the fuel assemblies 4 form a Y shape by taking the connecting line of the central point and three alternate angles in the assemblies as a boundary, and the fuel assemblies 4 can be trisected into three identical rhombic structures; inside each rhomboid there is a rhomboid assembly wall 11, a plurality of fuel assembly coolant channels 12 and fuel plates, which are parallel to each other and alternate at regular intervals, and which are composed of an outer fuel cladding 13 and an inner plate-like fuel pellet 14; the three diamond-shaped structures differ only in angle, and by rotating one of the diamond-shaped structures 120 ° clockwise or counterclockwise about the fuel assembly inner center point, the other two diamond-shaped structures are obtained, so that the fuel assembly 4 is "Y" shaped and rotationally symmetric about the assembly inner center point 1/3; the fuel used by the fuel pellet 14 is uranium zirconium alloy fuel with 10% of Zr mass content, and the enrichment degree of U235 is 90%;
the reactor core structure power is 200MW, the in-reactor neutron flux level can be effectively improved under the power level, and the in-reactor peak total neutron flux can reach 1.00 multiplied by 1016n/cm2Therefore, the efficiency of material irradiation experiment and isotope production is greatly improved.
Inside each diamond structure, 10 coolant channels 12 and 9 fuel plates are arranged parallel to each other and alternately at fixed intervals.
The material of the assembly walls 11 and the fuel clad 13 within the fuel assembly 4 are both stainless steel.
The coolant material in the coolant channels 12 in the fuel assembly 4 is a lead bismuth eutectic alloy.
The absorber material of the control rod assembly 6 and the safety rod assembly 7 is boron carbide.
The radial reflecting layer 2 consists of inner reflecting layer assemblies 8 on six angles of the sixth circle of the reactor core and outer reflecting layer assemblies 9 from the seventh circle to the ninth circle; the internal reflection layer assembly 8 can be replaced by an irradiation pore channel, so that the irradiation space of the reactor core is expanded, and the material irradiation experiment or isotope production capacity of the reactor core is enhanced.
According to the reactor core structure of the super-high-flux lead bismuth cooling fast neutron research reactor, the radial shielding layer 3 is composed of the shielding layer assembly 10 from the tenth circle to the eleventh circle of the reactor core.
The fuel assembly external coolant passages 15 of the upper and lower portions of the fuel zone 1 use a lead bismuth coolant material.
The radial reflecting layer 2 and the upper and lower end sockets 16 of the reflecting layer are made of stainless steel materials; the radial shielding layer 3 is made of boron carbide materials, and the upper end socket 17 and the lower end socket 17 are made of stainless steel materials.
Compared with the prior art, the invention has the following advantages:
1. in the reactor core scheme adopted by the invention, a special fuel assembly is designed, and through the optimized geometric shape and geometric parameters, the fuel loading is reduced, and the heat exchange capacity is improved, so that the local power density can be further improved; the fuel assembly uses a high-concentration uranium zirconium alloy to reduce the capture of neutrons by uranium 238 in the fuel to increase neutron flux levels.
2. In the reactor core scheme adopted by the invention, the lead bismuth eutectic is used as the coolant, so that the reactor core slowing down can be effectively reduced, and the heat exchange capacity of the coolant is improved; meanwhile, compared with sodium coolant, the coolant has higher safety, and does not have sodium vacuole effect and sodium water reaction.
3. In the reactor core scheme adopted by the invention, nine irradiation channels with large irradiation volume are reserved in the reactor, the neutron flux level at the corresponding positions is high, and the related material irradiation experiment and isotope production work can be efficiently carried out.
4. In the reactor core scheme adopted by the invention, the equivalent diameter of the reactor core active area is small, the reactor core leakage is strong, and the radial reflecting layer area still has higher flux level; a certain number of irradiation channels are allowed to be arranged on the reflecting layer region to carry out material irradiation experiments and isotope production work, space in the reactor is reasonably utilized, and experimental capacity is improved.
Drawings
FIG. 1 is a schematic cross-sectional view of the core structure of a super high flux lead bismuth cooled fast neutron research reactor of the present invention.
FIG. 2 is a schematic view of the arrangement of the core assembly.
Fig. 3 is a schematic cross-sectional view of the structure of the fuel assembly of fig. 2.
Fig. 4 is an axial view of fig. 2 taken along a-a.
In the above drawings: 1: a fuel zone; 2: a radially reflective layer; 3: a radial shield layer; 4: a fuel assembly; 5: irradiating the pore channel; 6: a control rod assembly; 7: a safety bar assembly; 8: an internal reflective layer assembly; 9: an outer reflective layer assembly; 10: a shielding layer assembly; 11: a diamond-shaped component wall; 12: coolant passages within the fuel assembly; 13: a fuel clad; 14: a plate-shaped fuel pellet; 15: a fuel assembly external coolant passage; 16: an upper end socket and a lower end socket of the reflecting layer; 17: and the shielding layer comprises an upper end enclosure and a lower end enclosure.
Detailed Description
The invention provides a reactor core structure of a super-high-flux lead bismuth cooling fast neutron research reactor, which is combined with the attached drawing, and uses high enrichment with the reactor core power of 200MWThe maximum flux of the reactor core reaches 1.01 multiplied by 1016n/cm2The present invention will be described in further detail by taking the ultra-high flux reactor core of s as an example.
As shown in FIG. 1, a core structure of a super-high-flux lead bismuth-cooled fast neutron research reactor is composed of a fuel area 1, a radial reflecting layer 2 and a radial shielding layer 3 in the radial direction.
As shown in fig. 2, the core structure of the ultra-high-flux lead-bismuth-cooled fast neutron research reactor comprises a fuel area 1, a fuel assembly 4, an irradiation duct 5, a control rod assembly 6 and a safety rod assembly 7; the four types of assemblies are densely paved by 6 circles of regular hexagons, and 6 internal reflection layer assemblies 8 are arranged at six corners of the outermost circle, and belong to the area of the radial reflection layer 2, so that the fuel area 1 has 85 assemblies in total; fuel assemblies 4 are uniformly distributed in 6 circles in the fuel area 1; the irradiation pore channels 5 replace the fuel assemblies 4 at six corners of the third circle and three corners of the fifth circle which are spaced two by two, so that 9 irradiation pore channels 5 are formed; the control rod assemblies 6 replace the fuel assemblies 4 at the middle position of the fifth turn, so that there are 6 control rod assemblies 6; the safety rod assemblies 7 replace the fuel assemblies 4 in the remaining three corners of the fifth turn, so there are 3 safety rod assemblies; the radial reflecting layer 2 consists of inner reflecting layer assemblies 8 on six corners of the sixth circle of the reactor core and outer reflecting layer assemblies 9 from the seventh circle to the ninth circle; the radial shielding layer 3 consists of a shielding layer assembly 10 from the tenth circle to the eleventh circle of the reactor core; the control rod assembly 6 and the safety rod assembly 7 are made of boron carbide materials; the inner reflecting layer assembly 8 and the outer reflecting layer assembly 9 are made of stainless steel materials; the shield layer assembly 10 uses a boron carbide material.
As shown in fig. 3, in the core structure of the ultra-high-flux lead-bismuth cooling fast neutron research reactor, the fuel assemblies 4 form a Y shape by using the connection line of the center point and the three alternate angles in the assemblies as a boundary, and the fuel assemblies 4 are trisected into three identical rhombic structures; inside each diamond-shaped structure, there are diamond- shaped assembly walls 11, 10 fuel assembly coolant channels 12 and 9 fuel plates, which are parallel to each other and alternate at regular intervals, and which are composed of outer fuel cladding 13 and inner plate-shaped fuel pellets 14; the three diamond-shaped structures differ only in angle, with one diamond-shaped structure rotated 120 ° clockwise or counterclockwise about the fuel assembly inner center point, resulting in the other two diamond-shaped structures, so that fuel assembly 4 is "Y" shaped and rotationally symmetric about assembly inner center point 1/3; the fuel used by the fuel pellet 14 is uranium zirconium alloy fuel with 10% of Zr mass content, and the enrichment degree of U235 is 90%; the diamond shaped assembly walls 11 and the fuel clad 13 are made of stainless steel.
As shown in fig. 4, in the core structure of the ultra-high-flux lead-bismuth-cooled fast neutron research reactor, the core is axially symmetrical along a horizontal mid-plane, the upper and lower parts of the fuel region 1 are lead-bismuth eutectic alloy fuel assembly outer coolant channels 15, and the upper and lower end sockets 16 of the reflecting layer of the radial reflecting layer 2 are made of stainless steel; the upper and lower seal heads 17 of the shield layer of the radial shield layer 3 are made of stainless steel.
Take an ultra-high flux stack as an example: the thermal power of a reactor core is 200MW, the coolant is lead-bismuth eutectic alloy, and uranium-zirconium alloy fuel with the enrichment degree of 90% is used; the edge distance of all the components in the reactor core is 7.8cm, and the distance between the components is 0.1 cm; the fuel assembly comprises 67 fuel assemblies, each fuel assembly is in a Y-shaped 1/3 rotational symmetry shape and can be trisected into three identical diamond structures, and each diamond structure is provided with 10 coolant channels and 9 fuel plates which are alternately arranged; a total of 9 irradiation channels, wherein each irradiation channel is provided with a maximum irradiation space of about 1.10L; the number of the reflecting layer assemblies is 116, wherein the reflecting layer assemblies positioned at six angular positions of the fuel area can be replaced by irradiation channels so as to expand the irradiation volume of the reactor core; there are 112 shield layer assemblies. Through the physical transport calculation of the three-dimensional reactor, the equivalent diameter of the reactor core calculated by the scheme of the invention is 79cm, the height of the active region is 50cm, and the peak value of the internal flux of the reactor core reaches 1.01 multiplied by 1016n/cm2s, the flux of the irradiation channel in the third circle reaches 7.55X 1015n/cm2s, the flux of the irradiation channel in the fifth circle reaches 5.25X 1015n/cm2And s. Compared with the same type of research reactor, the invention doubles the flux level, and effectively improves the neutron flux level in the reactor core through optimized material selection, fuel assembly structure design and reactor core structure design.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (9)
1. The utility model provides a lead bismuth cooling fast neutron research reactor core structure with super high flux which characterized in that: the reactor core is composed of a fuel area (1), a radial reflecting layer (2) and a radial shielding layer (3) in the radial direction; the reactor core is symmetrical along a horizontal mid-plane in the axial direction, the upper part and the lower part of the fuel region (1) are coolant channels (15), the upper part and the lower part of the radial reflecting layer (2) are reflecting layer upper and lower end sockets (16), and the upper part and the lower part of the radial shielding layer (3) are shielding layer upper and lower end sockets (17);
the fuel area (1) comprises a fuel assembly (4), an irradiation duct (5), a control rod assembly (6) and a safety rod assembly (7); the four types of assemblies are densely paved by 6 circles of regular hexagons, and 6 irradiation pore canals (5) or 6 internal reflection layer assemblies (8) are arranged at six corners of the outermost circle, belonging to the area of the radial reflection layer (2), so that the fuel area (1) has 85 assemblies; 6 circles of fuel assemblies (4) are uniformly distributed in the fuel area (1); the irradiation pore channels (5) replace the fuel assemblies (4) at six corners of the third circle and three corners of the fifth circle which are spaced by two, so that 9 or 15 irradiation pore channels (5) are formed; the control rod assemblies (6) replace the fuel assemblies (4) at the middle edge position of the fifth circle, so that the number of the control rod assemblies (6) is 6; the safety rod assemblies (7) replace the fuel assemblies (4) in the remaining three corners of the fifth circle, so that the number of the safety rod assemblies is 3;
the fuel assembly (4) forms a Y shape by taking a connecting line of a central point and three alternate angles in the assembly as a boundary, and the fuel assembly (4) is trisected into three identical rhombic structures; inside each rhomboid structure, there are rhomboid module walls (11), a plurality of fuel module coolant passages (12) and fuel plates are parallel to each other and arranged alternately according to the fixed interval, the fuel plate is made up of outer fuel cladding (13) and inner plate-like fuel pellet (14); the three diamond-shaped structures differ only in angle, one of the diamond-shaped structures being rotated 120 ° clockwise or counterclockwise about the fuel assembly inner center point, resulting in the other two diamond-shaped structures, so that the fuel assembly (4) is "Y" shaped and rotationally symmetric about the assembly inner center point 1/3; the fuel used by the fuel pellet (14) is uranium zirconium alloy fuel with 10% of Zr mass content, and the enrichment degree of U235 is 90%;
the reactor core structure power is 200MW, the in-reactor neutron flux level can be effectively improved under the power level, and the in-reactor peak total neutron flux reaches 1.00 multiplied by 1016n/cm2Therefore, the efficiency of material irradiation experiment and isotope production is greatly improved.
2. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: inside each diamond-shaped structure, 10 coolant channels (12) and 9 fuel plates are arranged parallel to each other and alternately at fixed intervals.
3. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the material of the component wall (11) and the fuel cladding (13) in the fuel component (4) is stainless steel.
4. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the coolant material in the coolant channels (12) in the fuel assembly is a lead bismuth eutectic alloy.
5. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the absorber material of the control rod assembly (6) and the safety rod assembly (7) is boron carbide.
6. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the radial reflecting layer (2) consists of inner reflecting layer assemblies (8) on six corners of the sixth circle of the reactor core and outer reflecting layer assemblies (9) of the seventh circle to the ninth circle.
7. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the radial shielding layer (3) is composed of a shielding layer assembly (10) from the tenth circle to the eleventh circle of the reactor core.
8. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the fuel assembly external coolant channels (15) of the upper and lower parts of the fuel area (1) use a lead bismuth coolant material.
9. The reactor core structure of the ultra-high-flux lead bismuth-cooled fast neutron research reactor of claim 1, wherein: the radial reflecting layer (2) and the upper and lower seal heads (16) of the reflecting layer are made of stainless steel materials; the radial shielding layer (3) is made of boron carbide materials, and the upper and lower end sockets (17) of the shielding layer are made of stainless steel materials.
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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 |
Citations (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1208777A (en) * | 1957-11-25 | 1960-02-25 | Atomic Energy Authority Uk | Atomic batteries |
| FR1255816A (en) * | 1960-04-30 | 1961-03-10 | Babcock & Wilcox Co | Improvements to fuel element assemblies for nuclear reactors |
| ES293446A1 (en) * | 1962-12-26 | 1964-01-16 | Atomic Energy Commission | Nuclear reactor |
| US4764339A (en) * | 1986-12-16 | 1988-08-16 | The United States Of America As Represented By The United States Department Of Energy | High flux reactor |
| JP2008281501A (en) * | 2007-05-14 | 2008-11-20 | Toshihisa Shirakawa | Core of light-water type nuclear reactor |
| CN103474097A (en) * | 2012-06-06 | 2013-12-25 | 中国核动力研究设计院 | Reactor core with high fast neutron fluence |
| CN103578578A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy source reactor core fuel assembly |
| CN104681105A (en) * | 2015-03-04 | 2015-06-03 | 东南大学 | Regularly-hexagonal nuclear fuel assembly provided with double-end spirally-arranged rhombic supporting plates |
| CN105976879A (en) * | 2016-05-09 | 2016-09-28 | 中国科学院上海应用物理研究所 | Assembly type molten salt reactor |
| CN106463184A (en) * | 2014-04-29 | 2017-02-22 | 伊恩·理查德·斯科特 | Movement of fuel tubes within array |
| CN107066745A (en) * | 2017-04-20 | 2017-08-18 | 西安交通大学 | The method for obtaining the three-dimensional netron-flux density distribution of fast neutron reactor reactor core transient process |
| CN107723625A (en) * | 2017-11-10 | 2018-02-23 | 中国工程物理研究院材料研究所 | A kind of preparation method of U Mo Zr alloys |
| CN108648834A (en) * | 2018-04-19 | 2018-10-12 | 西安交通大学 | Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core |
| CN110289109A (en) * | 2019-07-08 | 2019-09-27 | 西安交通大学 | The cooling similar honeycomb briquet type fuel assembly of liquid chlorate and the reactor core using the component |
| CN110853772A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Single-flow supercritical water-cooled reactor based on square fuel assembly |
| CN111477355A (en) * | 2020-04-16 | 2020-07-31 | 中国原子能科学研究院 | Reactor core fuel assembly and arrangement method thereof, micro neutron source reactor and reactor core thereof |
| CN113140331A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Compact structure fuel assembly, reactor and mobile carrier |
| CN113436756A (en) * | 2021-06-04 | 2021-09-24 | 西安交通大学 | Compact type space reactor core structure suitable for passive start |
-
2021
- 2021-11-24 CN CN202111407574.7A patent/CN114121308A/en active Pending
Patent Citations (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1208777A (en) * | 1957-11-25 | 1960-02-25 | Atomic Energy Authority Uk | Atomic batteries |
| FR1255816A (en) * | 1960-04-30 | 1961-03-10 | Babcock & Wilcox Co | Improvements to fuel element assemblies for nuclear reactors |
| ES293446A1 (en) * | 1962-12-26 | 1964-01-16 | Atomic Energy Commission | Nuclear reactor |
| US4764339A (en) * | 1986-12-16 | 1988-08-16 | The United States Of America As Represented By The United States Department Of Energy | High flux reactor |
| JP2008281501A (en) * | 2007-05-14 | 2008-11-20 | Toshihisa Shirakawa | Core of light-water type nuclear reactor |
| CN103474097A (en) * | 2012-06-06 | 2013-12-25 | 中国核动力研究设计院 | Reactor core with high fast neutron fluence |
| CN103578578A (en) * | 2013-10-16 | 2014-02-12 | 中国核电工程有限公司 | Advanced fusion-fission subcritical energy source reactor core fuel assembly |
| CN106463184A (en) * | 2014-04-29 | 2017-02-22 | 伊恩·理查德·斯科特 | Movement of fuel tubes within array |
| CN104681105A (en) * | 2015-03-04 | 2015-06-03 | 东南大学 | Regularly-hexagonal nuclear fuel assembly provided with double-end spirally-arranged rhombic supporting plates |
| CN105976879A (en) * | 2016-05-09 | 2016-09-28 | 中国科学院上海应用物理研究所 | Assembly type molten salt reactor |
| CN107066745A (en) * | 2017-04-20 | 2017-08-18 | 西安交通大学 | The method for obtaining the three-dimensional netron-flux density distribution of fast neutron reactor reactor core transient process |
| CN107723625A (en) * | 2017-11-10 | 2018-02-23 | 中国工程物理研究院材料研究所 | A kind of preparation method of U Mo Zr alloys |
| CN108648834A (en) * | 2018-04-19 | 2018-10-12 | 西安交通大学 | Honeycomb briquet type fuel assembly and small size long-life lead bismuth cool down fast reactor reactor core |
| CN110289109A (en) * | 2019-07-08 | 2019-09-27 | 西安交通大学 | The cooling similar honeycomb briquet type fuel assembly of liquid chlorate and the reactor core using the component |
| CN110853772A (en) * | 2019-11-21 | 2020-02-28 | 中国核动力研究设计院 | Single-flow supercritical water-cooled reactor based on square fuel assembly |
| CN111477355A (en) * | 2020-04-16 | 2020-07-31 | 中国原子能科学研究院 | Reactor core fuel assembly and arrangement method thereof, micro neutron source reactor and reactor core thereof |
| CN113140331A (en) * | 2021-03-05 | 2021-07-20 | 国科中子能(青岛)研究院有限公司 | Compact structure fuel assembly, reactor and mobile carrier |
| CN113436756A (en) * | 2021-06-04 | 2021-09-24 | 西安交通大学 | Compact type space reactor core structure suitable for passive start |
Non-Patent Citations (4)
| Title |
|---|
| WASIM RAZA 等: "《Effects of wire-spacer shape in LMR on thermal–hydraulic performance》", 《NUCLEAR ENGINEERING AND DESIGN》 * |
| 吴宏春 等: "《复杂几何燃料组件的参数计算》", 《原子能科学技术》 * |
| 朱宇翔: "IP200的堆芯物理特性分析", 《中国优秀博硕士学位论文全文数据库(硕士) 工程科技II辑》 * |
| 阎昌琪 等, 哈尔滨工业大学出版社 * |
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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