CN111477354A - Co-extrusion annular fuel rod - Google Patents
Co-extrusion annular fuel rod Download PDFInfo
- Publication number
- CN111477354A CN111477354A CN202010449324.9A CN202010449324A CN111477354A CN 111477354 A CN111477354 A CN 111477354A CN 202010449324 A CN202010449324 A CN 202010449324A CN 111477354 A CN111477354 A CN 111477354A
- Authority
- CN
- China
- Prior art keywords
- annular fuel
- fuel rod
- reactors
- cladding
- extruded
- 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
- 239000000446 fuel Substances 0.000 title claims abstract description 95
- 238000001125 extrusion Methods 0.000 title claims abstract description 13
- 238000005253 cladding Methods 0.000 claims abstract description 38
- 239000001307 helium Substances 0.000 claims abstract description 4
- 229910052734 helium Inorganic materials 0.000 claims abstract description 4
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 claims abstract description 4
- 230000000694 effects Effects 0.000 claims description 9
- 238000012546 transfer Methods 0.000 claims description 7
- 238000004804 winding Methods 0.000 claims description 7
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 claims description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 6
- 230000001965 increasing effect Effects 0.000 claims description 5
- 230000017525 heat dissipation Effects 0.000 claims description 4
- 238000009835 boiling Methods 0.000 claims description 3
- 239000002184 metal Substances 0.000 claims description 3
- 239000006185 dispersion Substances 0.000 claims description 2
- 238000012856 packing Methods 0.000 claims 2
- 239000008188 pellet Substances 0.000 abstract description 9
- 239000003758 nuclear fuel Substances 0.000 abstract description 6
- 238000004519 manufacturing process Methods 0.000 abstract description 5
- 230000006835 compression Effects 0.000 abstract description 3
- 238000007906 compression Methods 0.000 abstract description 3
- 239000007789 gas Substances 0.000 abstract description 3
- 239000002901 radioactive waste Substances 0.000 abstract description 2
- 239000002826 coolant Substances 0.000 description 5
- 238000010618 wire wrap Methods 0.000 description 4
- 238000013461 design Methods 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 239000007787 solid Substances 0.000 description 2
- 238000005520 cutting process Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000002708 enhancing effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 230000001052 transient effect Effects 0.000 description 1
Images
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
- G21C3/06—Casings; Jackets
- G21C3/08—Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
-
- 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
- G21C3/06—Casings; Jackets
- G21C3/10—End closures ; Means for tight mounting therefor
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention relates to the technical field of nuclear fuel, and particularly discloses a co-extrusion annular fuel rod, wherein a gap is not formed between a fuel pellet and a cladding, the heat conduction is enhanced, the central temperature of the fuel pellet is reduced, a traditional compression spring structure is not needed, the operation stability is improved, and radioactive waste is reduced. The fuel rod structure simplifies the assembly and manufacturing process of the fuel rod, does not need to fill helium gas into the fuel rod during manufacturing, and reduces the cost.
Description
Technical Field
The invention belongs to the technical field of nuclear fuel, and particularly relates to a co-extrusion annular fuel rod.
Background
During the operation of a nuclear power plant reactor, the performance of nuclear fuel is an important factor affecting the safety and economy of the reactor. Therefore, the research on fuel elements is put on a very prominent position internationally, and various performances of the nuclear fuel elements are continuously improved by optimizing the design of the fuel elements, adopting advanced structural materials, improving element manufacturing processes and other methods, so that nuclear power is promoted to develop towards a safer and more economic direction.
The nuclear fuel is generally designed into a solid cylinder shape and consists of an upper end plug, a lower end plug, a pellet, a compression spring and a cladding, and a coolant flows through the cladding to cool a fuel rod.
The benefit of the annular fuel is that at high linear power densities, the temperature in the center of the fuel is still low, there is less stored energy in the fuel, and there is less fission gas release than with conventional solid cylindrical fuels. Better fuel performance can be expected under normal operating and transient conditions.
In the existing annular fuel rod, gaps exist between the outer surface of the inner cladding and the inner surface of the annular fuel pellet and between the inner surface of the outer cladding and the outer surface of the annular fuel pellet, so that the annular fuel pellet is not favorably radiated, the assembly process has high precision requirement, and the assembly and the processing are inconvenient.
In the existing sodium-cooled fast reactor fuel element, the outer surface of the fuel rod cladding tube generally adopts a wire winding positioning structure to transversely position the fuel rod in the assembly, and the coolant is enabled to generate transverse flow by the transverse acting force of the wire winding, so that the heat transmitted from the surface of the cladding tube is better transmitted to the central area of the coolant, the highest temperature of the surface of the fuel rod cladding tube is effectively reduced, and the safety of the assembly is ensured. However, since there is inevitably a gap between the wire wrap and the outer surface of the fuel rod cladding tube, vibration is easily generated between the wire wrap and the outer surface of the fuel rod cladding tube, which affects the stability of the structure, and the coolant flow area of the contact part of the wire wrap and the fuel rod is narrow and long, and there are vortex and flow stagnation areas on the back flow surface of the wire wrap to the coolant, which also brings obstruction to heat conduction.
Therefore, it is desirable to design a fuel rod that eliminates the above-mentioned drawbacks.
Disclosure of Invention
The invention aims to provide a co-extrusion annular fuel rod, which eliminates the clearance between fuel pellets and a cladding and optimizes the heat transfer effect of a contact part of a wire winding and the fuel rod.
The technical scheme of the invention is as follows:
a co-extrusion annular fuel rod comprises an upper end plug, a lower end plug, an inner cladding, an outer cladding and an annular fuel core;
the annular fuel core, the inner cladding and the outer cladding are processed in a co-extrusion mode, no gap exists between the annular fuel core and the inner cladding and between the annular fuel core and the outer cladding, heat conduction is enhanced, and central temperature is reduced;
and an upper end plug and a lower end plug are connected above the inner cladding and the outer cladding.
The outer surface of the outer casing is provided with N turbulence wings, wherein N is more than or equal to 1.
The turbulence wings are spirally distributed on the outer surface of the outer cladding.
The turbulence wings and the outer surface of the outer wrapping shell are integrally processed and formed, so that the heat exchange area can be obviously increased, the whole heat dissipation is facilitated, and the phenomenon that the heat transfer effect of local heat of the wrapping shell is poor due to the poor heat transfer effect of the contact part of the wire winding positioning structure and the surface of the fuel rod is eliminated.
When the number of the turbulence wings is multiple, the turbulence wings are distributed on the outer surface of the outer wrapping shell at equal angles along the axial direction.
The height of the turbulence wings is equal to the distance between two adjacent annular fuel rods in the fuel assembly, and the two adjacent annular fuel rods can be limited through the turbulence wings.
Helium does not need to be filled in the fuel rod.
The annular fuel core is a dispersion fuel.
The annular fuel core is metal fuel.
The reactor is suitable for pressurized water reactors, fast reactors, low-temperature heat supply reactors, space reactors, boiling water reactors, micro-reactors, zero-power reactors, heavy water reactors, power reactors and marine power reactor types.
The invention has the following remarkable effects:
(1) the fuel rod has no gap between the fuel pellet and the cladding, thus enhancing heat conduction, reducing the central temperature of the fuel pellet, avoiding the need of a traditional compression spring structure, increasing the operation stability and reducing radioactive wastes.
(2) The turbulence wing structure and the outer fuel rod casing are integrally processed and formed, no gap exists between the turbulence wing structure and the outer fuel rod casing, and compared with a wire winding positioning structure, the heat exchange area can be remarkably increased, and the integral heat dissipation is facilitated.
(3) The turbulence wing structure of the fuel rod can obviously enhance the transverse mixing effect.
(4) The fuel rod structure simplifies the assembly and manufacturing process of the fuel rod, does not need to fill helium gas into the fuel rod during manufacturing, and reduces the cost.
Drawings
FIG. 1 is a cross-sectional view of a co-extruded annular fuel rod without turbulators;
FIG. 2 is a schematic longitudinal cross-sectional view of a co-extruded annular fuel rod without turbulators;
FIG. 3 is a schematic cross-sectional view of a co-extruded annular fuel rod having turbulators;
FIG. 4 is a schematic longitudinal cross-sectional view of a co-extruded annular fuel rod having turbulators;
FIG. 5 is a schematic cross-sectional view of a co-extruded annular fuel rod with multiple flow vanes.
In the figure: 1. an upper end plug; 2. a lower end plug; 3. an inner envelope; 4. an outer envelope; 5. an annular fuel core; 6. and a spoiler.
Detailed Description
The invention is described in further detail below with reference to the figures and the embodiments.
A co-extruded annular fuel rod as shown in fig. 1 and 2 comprises an upper end plug 1, a lower end plug 2, an inner cladding 3, an outer cladding 4 and an annular fuel core 5.
The annular fuel core body 5, the inner wrapping shell 3 and the outer wrapping shell 4 are processed in a co-extrusion mode, no gap exists between the annular fuel core body and the inner wrapping shell, heat conduction is enhanced, and the central temperature of the fuel core blocks is reduced.
An upper end plug 1 is connected above the inner cladding 3 and the outer cladding 4, and a lower end plug 2 is connected below.
The annular fuel core 5 is a dispersoid or a metal fuel.
Traditional co-extrusion processing mode produces the inhomogeneous condition of core distribution easily at co-extrusion piece's both ends, consequently this application co-extrusion formula annular fuel rod is through cutting off behind the inhomogeneous part of both ends core, and end plug 1 and lower end plug 2 are welded respectively to the rethread.
As shown in figures 3 and 4, N spoiler wings 6 are processed on the outer surface of the outer cladding 4, wherein N is more than or equal to 0. The turbulence wings 6 are spirally distributed on the outer surface of the outer cladding 4 and are integrally processed and formed with the outer surface of the outer cladding 4, so that the heat exchange area can be obviously increased, the whole heat dissipation is facilitated, and the phenomenon of poor heat transfer effect of local heat of the cladding caused by poor heat transfer effect of the contact part of the wire winding positioning structure and the surface of the fuel rod is eliminated.
As shown in fig. 5, when there are a plurality of flow-disturbing wings 6, they are distributed on the outer surface of the outer envelope 4 at equal angles along the axial direction. The height of the turbulence wings 6 is equal to the distance between two adjacent annular fuel rods in the fuel assembly, and the two adjacent annular fuel rods can be limited by the turbulence wings 6.
The co-extrusion type annular fuel rod is suitable for pressurized water reactors, fast reactors, low-temperature heat supply reactors, space reactors, boiling water reactors, micro-reactors, zero-power reactors, heavy water reactors, power reactors and marine power reactor types.
Claims (10)
1. A co-extruded annular fuel rod characterized by: comprises an upper end plug (1), a lower end plug (2), an inner packing shell (3), an outer packing shell (4) and an annular fuel core body (5);
the annular fuel core (5), the inner cladding (3) and the outer cladding (4) are processed in a co-extrusion mode, no gap exists between the annular fuel core and the inner cladding, heat conduction is enhanced, and central temperature is reduced;
an upper end plug (1) is connected above the inner cladding (3) and the outer cladding (4), and a lower end plug (2) is connected below the inner cladding and the outer cladding.
2. A co-extruded annular fuel rod of claim 1 wherein: the outer surface of the outer casing (4) is provided with N turbulence wings (6), wherein N is more than or equal to 1.
3. A co-extruded annular fuel rod of claim 2 wherein: the turbulence wings (6) are spirally distributed on the outer surface of the outer cladding (4).
4. A co-extruded annular fuel rod of claim 3 wherein: the turbulence wings (6) and the outer surface of the outer wrapping shell (4) are integrally processed and formed, so that the heat exchange area can be obviously increased, the whole heat dissipation is facilitated, and the phenomenon of poor heat transfer effect of local heat of the cladding caused by poor heat transfer effect of the contact part of the wire winding positioning structure and the surface of the fuel rod is eliminated.
5. A co-extruded annular fuel rod of claim 4 wherein: when the number of the turbulence wings (6) is multiple, the turbulence wings are distributed on the outer surface of the outer casing (4) at equal angles along the axial direction.
6. A co-extruded annular fuel rod of claim 5 wherein: the height of the turbulence wing (6) is equal to the distance between two adjacent annular fuel rods in the fuel assembly, and the two adjacent annular fuel rods can be limited through the turbulence wing (6).
7. A co-extruded annular fuel rod of claim 6 wherein: helium does not need to be filled in the fuel rod.
8. A co-extruded annular fuel rod of claim 7 wherein: the annular fuel core (5) is a dispersion fuel.
9. A co-extruded annular fuel rod of claim 7 wherein: the annular fuel core (5) is metal fuel.
10. A co-extruded annular fuel rod as claimed in any one of claims 1 to 9, wherein: the reactor is suitable for pressurized water reactors, fast reactors, low-temperature heat supply reactors, space reactors, boiling water reactors, micro-reactors, zero-power reactors, heavy water reactors, power reactors and marine power reactor types.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010449324.9A CN111477354A (en) | 2020-05-25 | 2020-05-25 | Co-extrusion annular fuel rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202010449324.9A CN111477354A (en) | 2020-05-25 | 2020-05-25 | Co-extrusion annular fuel rod |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN111477354A true CN111477354A (en) | 2020-07-31 |
Family
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202010449324.9A Pending CN111477354A (en) | 2020-05-25 | 2020-05-25 | Co-extrusion annular fuel rod |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN111477354A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113130097A (en) * | 2021-03-05 | 2021-07-16 | 安徽中科超核科技有限公司 | High-efficiency heat-conducting heat pipe reactor fuel element |
| CN113470840A (en) * | 2021-06-21 | 2021-10-01 | 清华大学 | Method for manufacturing spiral multi-blade nuclear fuel element |
| CN114944234A (en) * | 2022-04-27 | 2022-08-26 | 中国原子能科学研究院 | End plug cladding integrated annular fuel rod and fuel assembly |
| CN115116629A (en) * | 2022-05-11 | 2022-09-27 | 中国原子能科学研究院 | Annular fuel end plug, annular fuel assembly and welding method |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11183674A (en) * | 1997-12-25 | 1999-07-09 | Japan Nuclear Cycle Development Inst State Of Projects(Jnc) | Liquid metal bond-type fuel rod for reactor |
| CN101727992A (en) * | 2009-11-23 | 2010-06-09 | 中国核动力研究设计院 | Sleeve pipe type low-enriched uranium nuclear fuel assembly |
| CN106782681A (en) * | 2016-12-23 | 2017-05-31 | 中广核研究院有限公司 | Three cold type fuel rod and fuel assembly |
| CN106925777A (en) * | 2015-12-29 | 2017-07-07 | 中核北方核燃料元件有限公司 | A kind of annular dispersion fuel core base mould and forming method |
| CN212135972U (en) * | 2020-05-25 | 2020-12-11 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
-
2020
- 2020-05-25 CN CN202010449324.9A patent/CN111477354A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH11183674A (en) * | 1997-12-25 | 1999-07-09 | Japan Nuclear Cycle Development Inst State Of Projects(Jnc) | Liquid metal bond-type fuel rod for reactor |
| CN101727992A (en) * | 2009-11-23 | 2010-06-09 | 中国核动力研究设计院 | Sleeve pipe type low-enriched uranium nuclear fuel assembly |
| CN106925777A (en) * | 2015-12-29 | 2017-07-07 | 中核北方核燃料元件有限公司 | A kind of annular dispersion fuel core base mould and forming method |
| CN106782681A (en) * | 2016-12-23 | 2017-05-31 | 中广核研究院有限公司 | Three cold type fuel rod and fuel assembly |
| CN212135972U (en) * | 2020-05-25 | 2020-12-11 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113130097A (en) * | 2021-03-05 | 2021-07-16 | 安徽中科超核科技有限公司 | High-efficiency heat-conducting heat pipe reactor fuel element |
| CN113470840A (en) * | 2021-06-21 | 2021-10-01 | 清华大学 | Method for manufacturing spiral multi-blade nuclear fuel element |
| CN114944234A (en) * | 2022-04-27 | 2022-08-26 | 中国原子能科学研究院 | End plug cladding integrated annular fuel rod and fuel assembly |
| CN115116629A (en) * | 2022-05-11 | 2022-09-27 | 中国原子能科学研究院 | Annular fuel end plug, annular fuel assembly and welding method |
| CN115116629B (en) * | 2022-05-11 | 2024-05-10 | 中国原子能科学研究院 | Annular fuel end plug, annular fuel assembly and welding method |
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