CN116612908A - Lead bismuth cooling reactor core structure with inherent safety - Google Patents
Lead bismuth cooling reactor core structure with inherent safety Download PDFInfo
- Publication number
- CN116612908A CN116612908A CN202310591945.4A CN202310591945A CN116612908A CN 116612908 A CN116612908 A CN 116612908A CN 202310591945 A CN202310591945 A CN 202310591945A CN 116612908 A CN116612908 A CN 116612908A
- Authority
- CN
- China
- Prior art keywords
- fuel
- reactor core
- bismuth
- lead
- core structure
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 229910052797 bismuth Inorganic materials 0.000 title claims abstract description 21
- JCXGWMGPZLAOME-UHFFFAOYSA-N bismuth atom Chemical compound [Bi] JCXGWMGPZLAOME-UHFFFAOYSA-N 0.000 title claims abstract description 12
- 238000001816 cooling Methods 0.000 title abstract description 5
- 239000000446 fuel Substances 0.000 claims abstract description 71
- 239000002826 coolant Substances 0.000 claims abstract description 34
- 239000011159 matrix material Substances 0.000 claims abstract description 19
- 239000011148 porous material Substances 0.000 claims abstract description 13
- 238000005253 cladding Methods 0.000 claims abstract description 11
- 230000009471 action Effects 0.000 claims abstract description 6
- 239000007788 liquid Substances 0.000 claims abstract description 5
- 229910045601 alloy Inorganic materials 0.000 claims abstract description 4
- 239000000956 alloy Substances 0.000 claims abstract description 4
- 229910052790 beryllium Inorganic materials 0.000 claims abstract description 4
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 claims abstract description 4
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 claims abstract description 4
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims abstract description 4
- 229910010271 silicon carbide Inorganic materials 0.000 claims abstract description 4
- 239000000758 substrate Substances 0.000 claims abstract description 4
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 claims abstract description 4
- 239000008188 pellet Substances 0.000 claims description 8
- 229910001152 Bi alloy Inorganic materials 0.000 claims description 5
- 230000008878 coupling Effects 0.000 claims description 5
- 238000010168 coupling process Methods 0.000 claims description 5
- 238000005859 coupling reaction Methods 0.000 claims description 5
- 230000009257 reactivity Effects 0.000 claims description 5
- 239000006096 absorbing agent Substances 0.000 claims description 3
- 230000004992 fission Effects 0.000 claims description 3
- 239000006023 eutectic alloy Substances 0.000 claims description 2
- 229910052751 metal Inorganic materials 0.000 claims description 2
- 239000002184 metal Substances 0.000 claims description 2
- 238000005260 corrosion Methods 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 229910000909 Lead-bismuth eutectic Inorganic materials 0.000 description 1
- 238000005299 abrasion Methods 0.000 description 1
- 230000000903 blocking effect Effects 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 230000001105 regulatory effect Effects 0.000 description 1
Classifications
-
- 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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/045—Pellets
- G21C3/047—Pellet-clad interaction
-
- 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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/045—Pellets
- G21C3/048—Shape of pellets
-
- 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
- G21C3/3206—Means associated with the fuel bundle for filtering the coolant, e.g. nozzles, 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
- G21C3/30—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
-
- 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
-
- 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
- G21C3/334—Assembling, maintenance or repair of 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a lead-bismuth cooling reactor core structure with inherent safety, which consists of a fuel area, a control assembly and a reactor container; the fuel area is formed by discretely arranging fuel units according to a regular hexagonal grid array; each fuel cell is comprised of an outer beryllium reflector and an inner silicon carbide substrate; the reflector is nested outside the matrix and combined with the matrix under the action of the electromagnetic device; the matrix is internally provided with fuel pore channels and coolant channels which are arranged in a staggered way; the fuel rod adopts uranium dioxide fuel and MoNbZr alloy cladding, and is arranged in the fuel pore canal; the liquid lead bismuth leads out core heat through independent parallel coolant channels on the matrix; the control assembly is arranged outside the fuel unit and in the cavity in the stack container; the present invention proposes a discretely arranged core solution with significant inherent safety.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to a lead-bismuth cooling reactor core structure with inherent safety.
Background
The small-sized reactor is mainly used for one-stop energy supply or micro-grid power supply, and provides alternative energy sources with larger energy density and longer duration stability than that of a diesel generator in islands, remote areas and the like. Compared with the traditional commercial nuclear power system, the system has the characteristics of miniaturization, compact structure, high economy, short construction period and the like.
With the development of small-sized reactors, the distance between nuclear power and users becomes closer, the connection is tighter, and the requirements on operation safety are higher. At present, the acceptance of nuclear energy by the public is not high, and the sustainable development of nuclear power needs a safer and more reliable reactor design. The present invention is therefore directed to a compact reactor core design with inherent safety that addresses the above-described problems.
Disclosure of Invention
In order to solve the technical problems, the invention aims to provide a lead-bismuth cooling reactor core structure with inherent safety, and the running safety of a small-sized reactor is improved through reasonable structure and arrangement.
In order to achieve the above purpose, the present invention adopts the following technical scheme:
an intrinsically safe lead bismuth cooled reactor core structure consisting of a fuel zone, a control assembly 2 and a reactor vessel 3; the fuel area is arranged at the center of the reactor core and is formed by arranging a plurality of fuel units 1 in a regular hexagonal grid array; the control assembly 2 is arranged in a cavity at any position outside the fuel area and inside the stack container 3, and the position of the cavity is determined according to actual needs; the pile container 3 is a cylinder with a spherical lower end socket, contains all the internal pile components and is filled with liquid lead bismuth coolant; the fuel unit 1 is cylindrical, is discretely arranged in the reactor container 3, is independent, and enables the reactor to enter a critical state through neutron leakage coupling, and the fuel unit 1 comprises a reflector 4 and a matrix 5; the reflector 4 is annular, is nested outside the base body 5 and is combined with the base body 5 under the action of an electromagnetic device, and the reflector 4 can be naturally separated from the base body 5 by means of the buoyancy of the high-density lead-bismuth alloy under the over-temperature or power-losing emergency working condition, so that the reactor core automatically enters a subcritical shutdown state.
The fuel units 1 are cylindrical and are discretely arranged in a stack 3, and comprise a reflector 4 and a matrix 5; the reflector 4 is annular, is nested outside the base body 5 and is combined with the base body 5 under the action of an electromagnetic device; the matrix 5 is circular, 3 circles are divided according to a regular hexagonal grid array, a fuel pore canal 6 and a coolant channel 7 are respectively arranged in the grid, and 1 central coolant channel, 6 middle fuel pore canals, 6 corner fuel pore canals and 6 side core coolant channels which are alternately arranged are sequentially arranged from inside to outside.
The reflector 4 adopts metallic beryllium with excellent neutron moderating performance and reflecting performance, and the matrix 5 adopts silicon carbide with high temperature resistance and corrosion resistance.
The fuel pore canal 6 of the matrix 5 is internally provided with a fuel rod; the fuel rod consists of fuel pellets 8 and cladding 9.
The fuel pellet 8 of the fuel rod adopts uranium dioxide fuel with an enrichment degree of 19.75%, and the cladding 9 adopts a MoNbZr alloy cladding.
The coolant channels 7 are separate parallel channels arranged on the base body 5, the coolant being driven by a coolant pump, flowing through the coolant channels 7 to carry away fission heat release conducted through the base body 5 and forming a circulation within the stack container 3.
The lead-bismuth alloy coolant adopts lead-bismuth eutectic alloy with the mass percentage of 44.5:55.5.
The control assembly 2 is made of neutron strong absorber material.
Compared with the prior art, the invention has the following advantages:
1. compared with the traditional reactor core arrangement, the discrete fuel unit structure is adopted, the coupling among units is realized through neutron leakage, when the temperature of the reactor is obviously increased, the coupling is weakened, and natural negative feedback is introduced to the reactor;
2. each fuel unit is relatively independent, any unit fails, the reactor automatically enters a subcritical state, reliable accident shutdown is realized, and meanwhile, the failed unit can be isolated and replaced from other units, so that the subsequent operation of the reactor is not influenced;
3. in contrast to conventional reactor fuel assemblies, the fuel rods are placed on a high temperature resistant substrate and transfer heat to the coolant by conduction. Under the condition of insufficient coolant, the matrix can contain a large amount of fuel heat release, so that the risk of fuel melting caused by overheating of the reactor core is greatly reduced. The coolant exchanges heat in the independent large-diameter channel, so that corrosion and abrasion of the coolant to the cladding under the bar grating structure can be effectively avoided, the influence of coolant blocking flow is greatly reduced, and the safety of reactor operation is improved.
4. In contrast to conventional reactor fuel assemblies, each fuel cell has an independent reflector that effectively maintains the independence of each fuel cell while the reflector is combined with the substrate by electromagnetic means. Under the working conditions of overtemperature or power failure, the reflector can be separated from the matrix by virtue of the buoyancy action of the lead-bismuth alloy, and negative reactivity is introduced, so that automatic stack stopping is realized.
Drawings
FIG. 1 is a schematic diagram of a reactor core arrangement.
FIG. 2 is a second schematic view of a reactor core arrangement.
Fig. 3 is a schematic cross-sectional view of a fuel unit.
FIG. 4 is a schematic cross-sectional view of a fuel rod.
In the above figures: 1: a fuel unit; 2: a control assembly; 3: a stack container; 4: a reflector; 5: a base; 6: a fuel port; 7: a coolant channel; 8: a fuel pellet; 9: and (5) cladding.
Detailed Description
The structure of the present invention will be described in detail with reference to the accompanying drawings and the detailed description.
As shown in fig. 1, a lead bismuth cooled reactor core structure with inherent safety is comprised of a fuel zone, a control assembly 2 and a reactor vessel 3. The center of the reactor core is provided with a fuel area, and the fuel area is formed by arranging a plurality of fuel units 1 in a regular hexagonal grid array. The control assembly 2 is arranged in a cavity outside the fuel unit inside the stack container 3. The stack container 3 is a cylinder with a spherical lower end socket, contains all the internal components of the stack and is filled with liquid lead bismuth coolant.
As shown in fig. 1, individual fuel units 1 are arranged discretely, bringing the reactor into a critical state by neutron leak coupling.
As shown in fig. 1 and 2, the control assembly 2 may be disposed in a cavity at any location outside the fuel zone and inside the stack container 3, and the specific arrangement may be determined as desired.
As shown in fig. 3, the fuel unit 1 has a cylindrical shape with a radius of 11.28cm, and includes a reflector 4 and a base 5. The reflector 4 is made of a metal beryllium material with excellent neutron moderating performance and reflection performance, and the matrix 5 is made of a high-temperature-resistant and corrosion-resistant silicon carbide material. The reflector 4 is annular, is nested outside the base 5 and is combined with the base under the action of an electromagnetic device. The matrix 5 is round, the radius is 5.75cm, the inside is divided into 3 circles according to a regular hexagonal grid array, and the grid distance is 2.30cm. The grids are respectively provided with a fuel pore canal 6 with the radius of 0.95cm and a coolant channel 7 with the radius of 1.15cm, and the grids are sequentially provided with 1 central coolant channel, 6 middle fuel pore canals, 6 corner fuel pore canals and 6 side core coolant channels which are alternately arranged from inside to outside.
As shown in fig. 3, the coolant channels 7 are independent parallel channels arranged on the base body 5. The coolant is driven by a coolant pump through coolant channels 7 to carry away fission heat released by conduction through matrix 5 and to circulate within stack container 3.
As shown in fig. 1, 2 and 3, to effectively control the reactivity of the reactor core and meet the safety requirements during the operation of the reactor, the reactor core is provided with two sets of control systems, namely a regulating system and a shutdown system, which have different driving modes and are independent of each other. The adjusting system consists of a control component 2, and the control component 2 is driven by a motor when in operation, and the area of an absorber which is opposite to the reactor core is changed by moving in the cavity, so that the purposes of power adjustment and reactivity compensation are achieved. The shutdown system combines the reflector 4 of the fuel unit 1 with the matrix 5 by means of an electromagnetic device under normal operation working conditions, and the reflector 4 can be separated from the matrix 5 by means of buoyancy of the lead-bismuth alloy under accident working conditions such as overtemperature or power failure, so that negative reactivity is introduced, and automatic shutdown is realized.
As shown in fig. 4, the fuel rod is circular and is loaded in the fuel channel 6 of the base body 5, and is composed of a fuel pellet 8 and a cladding 9. The radius of the fuel pellet 8 is 0.85cm, and uranium dioxide fuel with the enrichment degree of 19.75% is adopted, so that the fuel pellet has good heat conduction performance and higher technical maturity. The MoNbZr alloy cladding with the thickness of 0.1cm has excellent high-temperature resistance.
Claims (8)
1. An intrinsically safe lead bismuth cooled reactor core structure, characterized by: the reactor core structure consists of a fuel area, a control assembly (2) and a reactor vessel (3); the fuel area is arranged at the center of the reactor core and is formed by arranging a plurality of fuel units (1) in a regular hexagonal grid array; the control assembly (2) is arranged in a cavity at any position outside the fuel area and inside the stack container (3); the pile container (3) is a cylinder with a spherical lower end socket, contains all the internal pile components and is filled with liquid lead bismuth coolant; the fuel unit (1) is cylindrical, is discretely arranged in the reactor container (3), is independent, and enables the reactor to enter a critical state through neutron leakage coupling, and the fuel unit (1) comprises a reflector (4) and a matrix (5); the reflector (4) is annular, is nested outside the base body (5) and is combined with the base body (5) under the action of the electromagnetic device, and the reflector (4) can be naturally separated from the base body (5) by means of the buoyancy of the high-density lead bismuth alloy under the overtemperature or power-losing emergency working condition, so that the reactor core automatically enters a subcritical shutdown state.
2. The intrinsically safe lead-bismuth cooled reactor core structure of claim 1, wherein: the matrix (5) is circular, 3 circles of the matrix are divided according to a regular hexagonal grid array, a fuel pore canal (6) and a coolant channel (7) are respectively arranged in the grid, and 1 central coolant channel, 6 middle fuel pore canals, 6 corner fuel pore canals which are alternately arranged and 6 side core coolant channels are sequentially arranged from inside to outside.
3. The intrinsically safe lead-bismuth cooled reactor core structure of claim 1, wherein: the reflector (4) is made of metal beryllium, and the substrate (5) is made of silicon carbide.
4. A lead bismuth cooled reactor core structure with inherent safety as claimed in claim 2, wherein: the fuel rod is loaded in a fuel pore canal (6) of the base body (5); the fuel rod consists of fuel pellets (8) and cladding (9).
5. The intrinsically safe lead-bismuth cooled reactor core structure of claim 4, wherein: the fuel pellet (8) is uranium dioxide fuel, and the cladding (9) is MoNbZr alloy cladding.
6. A lead bismuth cooled reactor core structure with inherent safety as claimed in claim 2, wherein: the coolant channels (7) are independent parallel channels arranged on the base body (5), and the coolant is driven by a coolant pump, flows through the coolant channels (7) to take away fission heat release conducted through the base body (5) and forms a circulation in the stack container (3).
7. The intrinsically safe lead-bismuth cooled reactor core structure of claim 1, wherein: the liquid lead-bismuth coolant is made of lead and bismuth eutectic alloy with the mass percentage of 44.5:55.5.
8. The intrinsically safe lead-bismuth cooled reactor core structure of claim 1, wherein: the control assembly (2) is driven by a motor when in operation, and the area of an absorber which is opposite to the reactor core is changed by moving in the cavity, so that the purposes of power adjustment and reactivity compensation are achieved.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310591945.4A CN116612908A (en) | 2023-05-24 | 2023-05-24 | Lead bismuth cooling reactor core structure with inherent safety |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310591945.4A CN116612908A (en) | 2023-05-24 | 2023-05-24 | Lead bismuth cooling reactor core structure with inherent safety |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN116612908A true CN116612908A (en) | 2023-08-18 |
Family
ID=87676067
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310591945.4A Pending CN116612908A (en) | 2023-05-24 | 2023-05-24 | Lead bismuth cooling reactor core structure with inherent safety |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN116612908A (en) |
-
2023
- 2023-05-24 CN CN202310591945.4A patent/CN116612908A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN1319074C (en) | Supercritical water nuclear reactor utilizing sleeve fuel assembly | |
| CN101315815B (en) | Method and device for fast breeding and converting nuclear fuel | |
| CN102543224B (en) | Power reactor adopting uranium zirconium hydride fuel element | |
| CN101252025B (en) | Heavy water stack cobalt regulating rod component | |
| CN110534213B (en) | Heat pipe cooling mixed fuel reactor system | |
| CN111627572B (en) | Modularized molten salt reactor core and molten salt reactor | |
| CN108140433A (en) | Nuclear reactor | |
| CN110867261B (en) | Multi-type pellet mixed loading metal cooling reactor and management method | |
| WO2022206072A1 (en) | Gas-cooled micro-reactor core and gas-cooled micro-reactor | |
| CN110853774B (en) | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor | |
| Sefidvash | A fluidized-bed nuclear reactor concept | |
| CN113270206B (en) | Small prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels | |
| Wei et al. | Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor | |
| CN108806805A (en) | A kind of pool molten salt reactor and its operation method | |
| CN116612908A (en) | Lead bismuth cooling reactor core structure with inherent safety | |
| CN113205892B (en) | Reactor core system of prismatic gas-cooled micro-reactor | |
| CN112366010A (en) | First circulation loading method for applying FCM fuel to million kilowatt pressurized water reactor | |
| KR20190098611A (en) | Fuel block, nuclear reactor core having the fuel block, micro high temperature gas-cooled reactor having the nuclear reactor core | |
| CN113130099A (en) | Compact-structure high-flux small-sized multipurpose lead-cooled fast reactor | |
| CN114121309A (en) | Reactor based on all-ceramic dispersion micro-packaging fuel and silicon carbide cladding | |
| CN112216408A (en) | Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system | |
| CN115101221B (en) | Integrated movable air-cooled miniature power reactor core | |
| CN113270207B (en) | Short-life-period air-cooled micro-reactor performance optimization structure | |
| Ponomarev-Stepnoi et al. | Prospects for using microelements in VVÉR reactors | |
| CN117174349A (en) | Gallium metal cooled megawatt-level small modular nuclear reactor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |