CN111667939A - Reactor core assembly and system for producing carbon-14 isotopes - Google Patents
Reactor core assembly and system for producing carbon-14 isotopes Download PDFInfo
- Publication number
- CN111667939A CN111667939A CN202010425657.8A CN202010425657A CN111667939A CN 111667939 A CN111667939 A CN 111667939A CN 202010425657 A CN202010425657 A CN 202010425657A CN 111667939 A CN111667939 A CN 111667939A
- Authority
- CN
- China
- Prior art keywords
- carbon
- core assembly
- cladding
- targets
- isotopes
- 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
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G1/00—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes
- G21G1/02—Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
-
- 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
- G21C3/16—Details of the construction within the casing
-
- 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)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- General Chemical & Material Sciences (AREA)
- Particle Accelerators (AREA)
Abstract
The invention provides a reactor core assembly and a system for producing carbon-14 isotopes, the reactor core assembly comprises rods (2, 4) of a cladding structure, cladding tubes (6) are arranged in the rods (2, 4), the cladding tubes (6) cover sealing targets (8) or targets (17), two ends of the cladding tubes (6) are sealed through end plugs (5, 9), and compression springs (7, 15) are arranged between the cladding tubes (6) and the sealing targets (8) or targets (17) and are used for compressing the sealing targets (8) or targets (17). The reactor core assembly is compatible with reactor internals, fuel assemblies and related operation tool interfaces of the pressurized water reactor nuclear power station, can be used for large pressurized water reactor nuclear power stations, has the capacity of loading a large amount of targets, and can flexibly allocate the loading capacity according to actual needs.
Description
Technical Field
The invention relates to the field of in-core components, in particular to the field of carbon-14 isotope production by core operation.
Background
Carbon-14 is a radioactive isotope of carbon, and carbon-14 is used in many applications, such as plant drug research (molecular labeling) in environmental protection, animal drug research in drug development, and biological labeling in healthcare. Natural carbon-14 is very low in reserves and widely distributed in the atmosphere, animals and plants, and is therefore an indispensable way to utilize carbon-14 isotopes through artificial synthesis. Carbon-14 belongs to low-toxicity radioactive nuclide, and the technical feasibility of production and separation by utilizing nuclear power station irradiation is higher. The thermal neutron flux of the nuclear power station is high but not effectively used, and the in-reactor free neutrons are used for carbon-14 industrial production, so that the carbon-14 market gap can be relieved, and the social benefit of the nuclear power station can be greatly increased.
At present, the carbon-14 isotope is produced internationally by adopting modes such as an accelerator or reactor irradiation and the like. For the reactor irradiation mode, as shown in fig. 1, the target material is usually wrapped in a target cylinder, and the target cylinder is placed in the reactor for irradiation. This approach is typically applied to small reactors or pilot stacks with irradiation channels.
The invention discloses a target and a system for a large pressurized water reactor, wherein the assembly is in a rod bundle structure, and the head part is a connecting part and can be matched with an in-reactor component to position the assembly in the reactor. The lower part of the connecting part is connected with a plurality of rods, a target material for producing the carbon-14 isotope is placed in the rods, and the rod bundle of the rod bundle can be inserted into a guide pipe of a reactor fuel assembly and is irradiated when the reactor runs. The assembly comprises a plurality of rods in a single assembly, can be loaded with a large amount of target materials, is used for a large pressurized water reactor, and has the capability of producing the carbon-14 isotope in a large amount. Meanwhile, the number of the rods which are arranged in the nuclear power station can be flexibly adjusted according to the operation requirement of the nuclear power station, and the overlarge influence on the economy of the nuclear power station is avoided.
Disclosure of Invention
The invention aims to provide a core assembly and a system for producing carbon-14 isotopes, and the carbon-14 isotopes can be produced in a pressurized water reactor by using the core assembly.
The reactor core assembly comprises rods (2, 4) of a cladding structure, a cladding tube (6) is arranged in the rods (2, 4), the cladding tube (6) covers a sealing target (8), two ends of the cladding tube (6) are sealed through end plugs (5, 9), and compression springs (7, 15) are arranged between the cladding tube (6) and the sealing target (8) and used for compressing the sealing target (8).
Preferably, the cladding tube (6) is a cylindrical hollow tube, and the material of the cladding tube (6) is stainless steel, zirconium alloy or aluminum alloy.
Preferably, the end plug (5) is connected to the connecting member (1, 3) by a screw.
Preferably, the end plugs (9) are tapered to facilitate insertion of the neutron absorbing rods (2, 4) into the fuel assembly guide tubes.
Preferably, an inner cladding (11) is arranged in the cladding tube (6), the inner cladding (11) is a cylindrical hollow tube, and end plugs (10, 13) seal the inner cladding (11).
Preferably, the inner cladding (11) is made of stainless steel, zirconium alloy or aluminum alloy.
Preferably, the target (12) may Be a pellet, powder or flocculent AlN, Be3N2And Si3N4,Ca(NO3)2And one or more of metallic and non-metallic materials.
Preferably, the compression springs (7, 15) are C-shaped springs or spiral springs.
A core assembly system for producing carbon-14 isotopes, wherein a plurality of core assemblies as claimed in claims 1-8 form a rod bundle structure through interfaces of fuel assemblies and reactor internals inserted by connecting parts (1, 3), and the connecting parts (1, 3) are used for realizing the operation of the core assemblies inside and outside a reactor and in spent fuel pools through handles or barrels.
Preferably, the shape of the connecting member (1, 3) is determined according to the interface between the fuel assembly to be inserted and the internals.
The reactor core assembly for producing the carbon-14 isotope is compatible with reactor internals, fuel assemblies and related operation tool interfaces of a pressurized water reactor nuclear power station, can be used for large pressurized water reactor nuclear power stations, has the capacity of loading a large amount of targets, and can flexibly allocate the loading capacity according to actual needs. The assembly is loaded in a pressurized water reactor nuclear power station, so that the preparation of the carbon-14 isotope in the pressurized water reactor can be realized, the yield of the carbon-14 isotope is improved, the supply problem of the carbon-14 isotope is favorably relieved, and the production cost of the carbon-14 isotope is reduced.
Drawings
FIG. 1 is a schematic view of a target construction;
FIG. 2 is a schematic view of a rod with a carbon-14 target material attached thereto 1;
FIG. 3 is a schematic view 2 of a rod loaded with a carbon-14 target material;
FIG. 4 is a schematic illustration of the containment structure;
FIG. 5 is a schematic view of a double-shelled structure;
FIG. 6 is a schematic view of a hold down spring;
wherein, 2 and 4 are rods, 1 and 3 are connecting parts, 8 is a sealing target material, 5 and 9 are end plugs, 6 is a cladding tube, 11 is an inner cladding, 14 and 18 are end plugs, 17 is a target material, and 7 and 15 are compression springs.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention comprehensible, embodiments accompanied with figures are described in further detail below.
The specific implementation mode of the reactor core assembly for producing the carbon-14 isotope is as follows:
as shown in fig. 2 and 3, a plurality of rods 2, 4 containing carbon 14 target material are connected into a rod bundle structure through connecting parts 1, 3, and the rods 2, 4 containing target material pass through small holes on the connecting parts. A handle or a cylinder for operation is arranged above the connecting part and is used for realizing the operation of the assembly inside and outside the stack and in the spent fuel pool.
The rods 2, 4 are of double-clad or single-clad construction. The double-cladding structure is shown in figure 4, and is formed by cladding a sealed target material 8 by a cladding tube 6, two ends of the double-cladding structure are sealed by end plugs 5 and 9, and a compression spring 7 is arranged on the double-cladding structure in order to prevent the sealed target material 8 from moving. The shape of the connecting members 1, 3 is determined according to the interface of the fuel assembly and the internals to be inserted.
The cladding tube 6 is a cylindrical hollow tube and is made of metals such as stainless steel, zirconium alloy, aluminum alloy and the like. The outside diameter of the cladding tube 6 is selected according to the outside diameter of the fuel assembly guide tube into which it is inserted. The end plugs 5 connected to the connecting members 1, 3 are provided with threads for fixing the rods 2, 4 to the connecting members 1, 3, but the rods 2, 4 may be connected to the connecting members 1, 3 in other ways. The lower end plug 9 is designed with a conical shape to facilitate insertion of the rods 2, 4 into the fuel assembly guide tubes.
The inner jacket 11 is also a cylindrical hollow tube made of metal such as stainless steel, zirconium alloy, aluminum alloy, and the like. The end plugs 10, 13 seal the inner envelope 11.
The target 12 may be in the form of pellets, powder, flakes, or the like. The material is AlN or Be3N2And Si3N4, Ca(NO3)2And a variety of metallic and non-metallic materials.
The purpose of the compression springs 7, 15 is to compress the target material and prevent the target material from moving during transportation, handling, etc. The compression springs 7, 15 may be C-shaped springs as shown in fig. 4 and 6, or helical springs may be used.
The foregoing embodiments are merely illustrative of the principles and utilities of the present invention and are not intended to limit the invention. Any person skilled in the art can modify or change the above-mentioned embodiments without departing from the spirit and scope of the present invention. Accordingly, it is intended that all equivalent modifications or changes which can be made by those skilled in the art without departing from the spirit and technical spirit of the present invention be covered by the claims of the present invention.
Claims (10)
1. The reactor core assembly for producing the carbon-14 isotope is characterized by comprising rods (2 and 4) of a cladding structure, wherein cladding tubes (6) are arranged in the rods (2 and 4), the cladding tubes (6) are coated with sealing targets (8) or directly coated with the targets (17), two ends of each cladding tube (6) are sealed through end plugs (5 and 9), and compression springs (7 and 15) are arranged between each cladding tube (6) and each target (17) or each sealing target (8) and used for compressing the targets (17) or each sealing target (8).
2. The core assembly for producing a carbon-14 isotope according to claim 1, wherein the cladding tube (6) is a cylindrical hollow tube, and the material of the cladding tube (6) is stainless steel, zirconium alloy, aluminum alloy.
3. The core assembly for producing a carbon-14 isotope according to claim 1, wherein the end plugs (5) are connected by screwing the connection members (1, 3).
4. The core assembly for the production of carbon-14 isotopes as claimed in claim 1, characterised in that said end plugs (9) are provided with a conical shape.
5. The core assembly for producing carbon-14 isotopes as claimed in claim 1, wherein a target (17) or an inner cladding (11) is arranged inside the cladding tube (6), the inner cladding (11) is a cylindrical hollow tube, and end plugs (10, 13) seal the inner cladding (11).
6. The core assembly for the production of carbon-14 isotopes as claimed in claim 5, characterised in that said inner cladding (11) is made of stainless steel, zirconium alloy, aluminium alloy.
7. The core assembly for the production of carbon-14 isotopes as claimed in claim 1, characterised in that said targets (12, 17) can Be pellets, powder or flocculent AlN, Be3N2And Si3N4,Ca(NO3)2And one or more of metallic and non-metallic materials.
8. The core assembly for producing a carbon-14 isotope according to claim 1, wherein the hold-down springs (7, 15) are C-shaped springs or spiral springs.
9. A core assembly system for producing carbon-14 isotopes, characterized in that a plurality of core assemblies as claimed in claims 1-8 form a rod bundle structure through interfaces of fuel assemblies and internals inserted by connecting members (1, 3), and the connecting members (1, 3) are used for realizing the operation of the core assemblies inside and outside the reactor and in spent fuel pools through handles or barrels.
10. The core assembly system for producing a carbon-14 isotope according to claim 9, wherein the shape of the connection members (1, 3) is determined according to the interface of the fuel assembly to be inserted and the internals.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202010425657.8A CN111667939A (en) | 2020-05-19 | 2020-05-19 | Reactor core assembly and system for producing carbon-14 isotopes |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN202010425657.8A CN111667939A (en) | 2020-05-19 | 2020-05-19 | Reactor core assembly and system for producing carbon-14 isotopes |
Publications (1)
Publication Number | Publication Date |
---|---|
CN111667939A true CN111667939A (en) | 2020-09-15 |
Family
ID=72383975
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN202010425657.8A Pending CN111667939A (en) | 2020-05-19 | 2020-05-19 | Reactor core assembly and system for producing carbon-14 isotopes |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN111667939A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2022218436A1 (en) * | 2021-04-16 | 2022-10-20 | 上海核工程研究设计院有限公司 | Target and target group used for heavy water reactor production of c-14 isotopes |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104900288A (en) * | 2015-04-08 | 2015-09-09 | 中科华核电技术研究院有限公司 | Novel choke plug assembly for using pressurized water reactor to prepare radioactive source, and radioactive rod |
CN105244069A (en) * | 2015-08-31 | 2016-01-13 | 中科华核电技术研究院有限公司 | High-specific-activity radioactive source core target, radioactive rod and novel thimble plug assembly |
CN106531278A (en) * | 2017-01-11 | 2017-03-22 | 中国核动力研究设计院 | Irradiated target containing Np-237 used for producing Pu-238 by means of research reactor irradiation |
CN109473190A (en) * | 2018-11-29 | 2019-03-15 | 上海核工程研究设计院有限公司 | A kind of secondary neutron source rod reducing tritium discharge |
-
2020
- 2020-05-19 CN CN202010425657.8A patent/CN111667939A/en active Pending
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN104900288A (en) * | 2015-04-08 | 2015-09-09 | 中科华核电技术研究院有限公司 | Novel choke plug assembly for using pressurized water reactor to prepare radioactive source, and radioactive rod |
CN105244069A (en) * | 2015-08-31 | 2016-01-13 | 中科华核电技术研究院有限公司 | High-specific-activity radioactive source core target, radioactive rod and novel thimble plug assembly |
CN106531278A (en) * | 2017-01-11 | 2017-03-22 | 中国核动力研究设计院 | Irradiated target containing Np-237 used for producing Pu-238 by means of research reactor irradiation |
CN109473190A (en) * | 2018-11-29 | 2019-03-15 | 上海核工程研究设计院有限公司 | A kind of secondary neutron source rod reducing tritium discharge |
Non-Patent Citations (1)
Title |
---|
中国核动力研究设计院: "《学术交流论文集"》", 31 December 1990 * |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2022218436A1 (en) * | 2021-04-16 | 2022-10-20 | 上海核工程研究设计院有限公司 | Target and target group used for heavy water reactor production of c-14 isotopes |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US20150310948A1 (en) | Fully ceramic nuclear fuel and related methods | |
CN112951472B (en) | Irradiation target containing support rod for producing molybdenum-99 isotope in heavy water pile | |
KR20200101353A (en) | Cylindrical metal nuclear fuel and its manufacturing method | |
US8625733B2 (en) | Neutron source assembly | |
WO2018206234A1 (en) | A nuclear fuel pellet, a fuel rod, and a fuel assembly | |
CN112967829A (en) | Irradiation target for producing molybdenum-99 isotope in heavy water reactor | |
CN111667939A (en) | Reactor core assembly and system for producing carbon-14 isotopes | |
WO2015195115A1 (en) | Triso-isotropic (triso) based light water reactor fuel | |
EP0788117A1 (en) | Nuclear fuel pellet | |
US8774344B1 (en) | Tri-isotropic (TRISO) based light water reactor fuel | |
JP2022553924A (en) | Modular Radioisotope Generation Capsule and Related Methods | |
CN112117021A (en) | Carbon 14 target rod in square assembly placed in nuclear reactor | |
US9202601B2 (en) | Methods and apparatus for suppressing tritium permeation during tritium production | |
US3928130A (en) | Sheath for nuclear fuel elements | |
Shemon et al. | Specification of the Advanced Burner Test Reactor Multi-Physics Coupling Demonstration Problem | |
JPH11352272A (en) | Reactor core and fuel assembly and fuel element used for the core | |
JP3044186B2 (en) | Method for eliminating unnecessary nuclides using a nuclear reactor | |
KR20180061498A (en) | Method of Cobalt Bundle Design | |
GB2115212A (en) | Nuclear fuel element | |
Nitheanandan et al. | The results from the first high-pressure melt ejection test completed in the molten fuel moderator interaction facility at Chalk River Laboratories | |
RU2217819C2 (en) | Nuclear reactor fuel element | |
US20060176995A1 (en) | Control arrangement for use with nuclear fuel | |
Lindsey et al. | Production of plutonium-238 with minimum plutonium-236 contamination | |
JPS61256285A (en) | Nuclear fuel aggregate | |
Marek et al. | LVR-15 reactor application for material testing |
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 | ||
RJ01 | Rejection of invention patent application after publication |
Application publication date: 20200915 |
|
RJ01 | Rejection of invention patent application after publication |