CN114121320A - Spontaneous thermal corrosion sample for fuel cladding of nuclear power plant, preparation method and test device - Google Patents
Spontaneous thermal corrosion sample for fuel cladding of nuclear power plant, preparation method and test device Download PDFInfo
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- CN114121320A CN114121320A CN202111397241.0A CN202111397241A CN114121320A CN 114121320 A CN114121320 A CN 114121320A CN 202111397241 A CN202111397241 A CN 202111397241A CN 114121320 A CN114121320 A CN 114121320A
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- cladding
- cladding tube
- corrosion
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- 238000005253 cladding Methods 0.000 title claims abstract description 139
- 238000005260 corrosion Methods 0.000 title claims abstract description 95
- 230000007797 corrosion Effects 0.000 title claims abstract description 91
- 238000012360 testing method Methods 0.000 title claims abstract description 58
- 239000000446 fuel Substances 0.000 title claims abstract description 25
- 230000002269 spontaneous effect Effects 0.000 title claims abstract description 17
- 238000002360 preparation method Methods 0.000 title abstract description 8
- 238000010438 heat treatment Methods 0.000 claims abstract description 46
- 239000000463 material Substances 0.000 claims abstract description 30
- 238000005485 electric heating Methods 0.000 claims abstract description 22
- 230000004907 flux Effects 0.000 claims abstract description 14
- 238000000034 method Methods 0.000 claims abstract description 14
- 238000006243 chemical reaction Methods 0.000 claims abstract description 7
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 7
- 238000003466 welding Methods 0.000 claims abstract description 7
- 238000007789 sealing Methods 0.000 claims description 36
- 239000011810 insulating material Substances 0.000 claims description 6
- 239000002184 metal Substances 0.000 claims description 6
- 238000005520 cutting process Methods 0.000 claims description 4
- 230000008569 process Effects 0.000 abstract description 10
- 238000011156 evaluation Methods 0.000 abstract description 7
- 238000011160 research Methods 0.000 abstract description 5
- 239000002826 coolant Substances 0.000 description 5
- 230000009286 beneficial effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 230000007246 mechanism Effects 0.000 description 2
- 238000012544 monitoring process Methods 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 238000012827 research and development Methods 0.000 description 1
- 238000009991 scouring Methods 0.000 description 1
- 238000006467 substitution reaction Methods 0.000 description 1
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
-
- 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)
- Physics & Mathematics (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Manufacturing & Machinery (AREA)
- Testing Resistance To Weather, Investigating Materials By Mechanical Methods (AREA)
Abstract
The invention discloses a spontaneous heating corrosion sample of a nuclear power plant fuel cladding, a preparation method and a test device, comprising a cladding tube and an electric heating element; one end of the cladding tube is closed, and one end of the cladding tube is opened, and the cladding tube is made of a cladding material to be subjected to a corrosion test; the heating element is arranged in the cladding tube and can simulate the heat flux density applied to the cladding tube by nuclear fuel reaction. According to the invention, the cladding material of the corrosion sample is designed into a tubular structure, and the resistance wire is added in the cladding material to achieve the purpose of simulating surface spontaneous heating and heat flux density of the cladding material, so that the research and engineering evaluation of the corrosion behavior of the cladding material under the condition of heat flux density can be realized; one end of the cladding tube is sealed by welding, so that the electric heating element is prevented from being damaged by corrosive media in the test process, and the other end of the cladding tube is opened, so that the heating element can be detached and replaced on line in the test process, and the engineering requirements of long-period corrosion tests on the cladding material are met.
Description
Technical Field
The invention relates to the technical field of material corrosion tests, in particular to a spontaneous heating corrosion sample for a fuel cladding of a nuclear power plant, a preparation method and a test device.
Background
The fuel clad is the first safety barrier for reactor operation. The cladding prevents fission products from escaping and isolates the nuclear fuel from the coolant, preventing chemical reaction from occurring in contact with the coolant. The corrosion resistance of the cladding material in the high-temperature coolant is a key factor influencing the service life of the cladding, and the development of corrosion test research on the cladding material in the coolant medium is beneficial to knowing the corrosion mechanism of the cladding material and provides a basis for evaluating the service performance and service life prediction of the cladding material.
At present, the corrosion behavior of a cladding material is generally researched by using an autoclave hanging piece test, although the corrosion mechanism research can be completed, the prototype working condition of the cladding in service cannot be simulated, and the engineering evaluation is limited. Under the actual operation condition of the reactor, the cladding is not only subjected to scouring of the coolant, but also bears the heat flux density generated by nuclear reaction of the nuclear fuel, and further influences the corrosion behavior. Therefore, the research and development of a corrosion sample capable of realizing the surface heat flux density of the cladding material are urgently needed for the corrosion research and engineering evaluation of the cladding material.
In view of this, the present application is specifically made.
Disclosure of Invention
The invention aims to solve the technical problems that the corrosion behavior of the cladding material is researched in the prior art, the prototype working condition of the cladding in service cannot be simulated, and the engineering evaluation is limited, and aims to provide a novel nuclear power plant fuel cladding spontaneous heating corrosion sample which can simulate spontaneous heating and surface heat flux density of the cladding in service and solve the engineering evaluation problem of the cladding material corrosion.
The invention is realized by the following technical scheme:
a nuclear power plant fuel cladding self-heating corrosion sample comprises a cladding tube and an electric heating element; one end of the cladding tube is closed, and one end of the cladding tube is opened, and the cladding tube is made of a cladding material to be subjected to a corrosion test; the heating element is arranged in the cladding tube and can simulate the heat flux density applied to the cladding tube by nuclear fuel reaction.
According to the invention, the cladding material of the corrosion sample is designed into a tubular structure, and the resistance wire is added in the cladding material to achieve the purpose of simulating surface spontaneous heating and heat flux density of the cladding material, so that the research and engineering evaluation of the corrosion behavior of the cladding material under the condition of heat flux density can be realized. One end of the cladding tube is sealed by welding, so that the electric heating element is prevented from being damaged by corrosive media in the test process, and the other end of the cladding tube is opened, so that the heating element can be detached and replaced on line in the test process, and the engineering requirements of long-period corrosion tests on the cladding material are met.
In another embodiment of the invention, the corrosion test sample further comprises a sealing element, the sealing element is sleeved on the outer wall of one open end of the cladding tube, and when the closed end of the cladding tube is inserted into the corrosion test section, the sealing element can realize the sealing between the open end of the cladding tube and the corrosion test section; through the arrangement of the sealing piece, the corrosion medium can be prevented from overflowing from the position between the corrosion test section and the cladding tube in the test sample process.
The sealing element is an ellipsoid-shaped metal block with a circular through hole in the middle, the cladding tube penetrates through the through hole and is in gapless connection with the sealing element through welding, the sealing element is in an ellipsoid shape and can play a good sealing role on a tubular test section, and the sealing element is made of metal, so that the corrosion resistance of the sealing element is ensured, and the safety in the test process is improved.
According to another embodiment of the invention, the electric heating element comprises a cladding tube, resistance wires are uniformly distributed in the cladding tube, gaps among the resistance wires in the cladding tube are filled with insulating materials, and the resistance wires are electrified to generate heat and can apply heat flux density to the cladding tube.
The outer wall of the cladding pipe is provided with a groove, and a thermocouple is arranged in the groove, so that the temperature of the surface of the electric heating element can be monitored in the test process.
According to another embodiment of the invention, the electric heating element and the cladding tube are detachably connected by interference fit, so that the electric heating element is convenient to detach and replace in the test process.
A preparation method of a nuclear power plant fuel cladding spontaneous heating corrosion sample comprises the following steps: cutting the cladding tube into a suitable length, and sealing one end of the cladding tube; determining the number of heating wires in the heating element according to the surface power density and the surface temperature, uniformly arranging the heating wires in the cladding tube, filling insulating materials in the cladding tube, and compacting to obtain the heating element; and (3) putting the heating element into the cladding tube by interference fit to assemble the self-heating corrosion sample.
The utility model provides a test device of spontaneous heating corrosion sample of nuclear power plant's fuel cladding, is including being pipy corrosion test section, has corrosive medium entry and corrosive medium export on the corrosion test section, and the corrosion test section is including erecting the pipe section, and the upper end centre gripping of erecting the pipe section is fixed on the fixed bolster, and vertical pipe section upper end is offered and is used for corroding sample male opening, corrodes and seals through the sealing member between sample and the vertical pipe section opening.
When the test device provided by the invention is used for testing, the corrosion sample is placed in the vertical pipe section of the test section, then the sealing between the corrosion sample and the test section is realized through the ellipsoidal metal sealing element, and the corrosion medium inlet and the corrosion medium outlet are connected with the test loop to form a loop in which the corrosion medium flows, so that the corrosion test can be carried out.
Compared with the prior art, the invention has the following advantages and beneficial effects:
1. according to the nuclear power plant fuel cladding self-heating corrosion sample provided by the embodiment of the invention, the cladding tube is prepared by adopting the cladding material, and the electric heating element is arranged in the cladding tube, so that the heat flux density generated by nuclear fuel reaction on the cladding can be simulated, the prototype working condition of the cladding in service is reduced, and the purpose of researching the corrosion behavior of the cladding material is realized;
2. the spontaneous heating corrosion sample for the fuel cladding of the nuclear power plant provided by the embodiment of the invention can realize the on-line disassembly and replacement of the heating element in the test process, and meet the engineering requirements of long-period corrosion test of the cladding material;
3. the spontaneous heating corrosion sample for the fuel cladding of the nuclear power plant provided by the embodiment of the invention has the advantages of simple structure, convenience in processing and manufacturing, convenience in disassembly and suitability for engineering evaluation of cladding material corrosion.
Drawings
In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the drawings that are required to be used in the embodiments will be briefly described below, it should be understood that the following drawings only illustrate some embodiments of the present invention and therefore should not be considered as limiting the scope, and that for those skilled in the art, other related drawings can be obtained from these drawings without inventive effort.
FIG. 1 is a diagram of a corrosion sample configuration provided by an embodiment of the present invention;
fig. 2 is a structural diagram of a testing apparatus according to an embodiment of the present invention.
Reference numbers and corresponding part names:
1-cladding tube, 2-electric heating element, 3-sealing element, 4-corrosion test section, 5-corrosion sample, 8-fixed support plate, 9-corrosion medium inlet and 10-corrosion medium outlet.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention. However, it will be apparent to one of ordinary skill in the art that: it is not necessary to employ these specific details to practice the present invention. In other instances, well-known structures, circuits, materials, or methods have not been described in detail so as not to obscure the present invention.
Throughout the specification, reference to "one embodiment," "an embodiment," "one example," or "an example" means: the particular features, structures, or characteristics described in connection with the embodiment or example are included in at least one embodiment of the invention. Thus, the appearances of the phrases "one embodiment," "an embodiment," "one example" or "an example" in various places throughout this specification are not necessarily all referring to the same embodiment or example. Furthermore, the particular features, structures, or characteristics may be combined in any suitable combination and/or sub-combination in one or more embodiments or examples. Further, those of ordinary skill in the art will appreciate that the illustrations provided herein are for illustrative purposes and are not necessarily drawn to scale. As used herein, the term "and/or" includes any and all combinations of one or more of the associated listed items.
In the description of the present invention, the terms "front", "rear", "left", "right", "upper", "lower", "vertical", "horizontal", "upper", "lower", "inner", "outer", etc. indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience of description and simplicity of description, but do not indicate or imply that the device or element being referred to must have a particular orientation, be constructed in a particular orientation, and be operated, and therefore, should not be construed as limiting the scope of the present invention.
Example 1
As shown in fig. 1, the self-heating corrosion sample for the fuel cladding of the nuclear power plant provided by the embodiment of the invention comprises a cladding tube 1, an electric heating element 2 and a sealing member 3, wherein the cladding tube 1 is a cladding material to be subjected to a corrosion test; the electric heating element 2 is arranged in the cladding tube 1; the sealing element 3 is used for sealing the cladding tube 1;
the cladding tube 1 is used for being placed in the corrosion test section 4 to carry out corrosion test examination, the cladding tube 1 is a thin-walled tube with through holes at two ends, one end of the thin-walled tube is sealed by welding and other methods, so that an electric heating element is prevented from being damaged by a corrosive medium in the test process, and an opening structure is reserved at the other end of the thin-walled tube and is used for installing the electric heating element;
the electric heating element 2 is arranged in the cladding tube 1 and used for simulating the heat flux density generated by nuclear fuel reaction on the cladding, and consists of a resistance wire, an insulating filling material, a cladding tube and a thermocouple; the resistance wires are uniformly distributed and arranged in the cladding tube, and the gaps are filled with insulating materials and compacted; the resistance wire is electrified to generate heat and is used for applying heat flux density to the cladding tube 1; the outer wall of the cladding pipe is provided with a groove, and a thermocouple is embedded and used for monitoring the surface temperature of the electric heating element;
the sealing element 3 is used for sealing the cladding tube 1 and the corrosion test section 4; the sealing element 3 is an ellipsoid-shaped metal block, a circular through hole is formed in the middle of the sealing element, the sealing element 3 is welded on the cladding tube 1 after the cladding tube 1 penetrates through the through hole, and no gap exists between the sealing element 3 and the tube wall 1.
Example 2
The embodiment of the invention provides a preparation method of a spontaneous heating corrosion sample of a nuclear power plant fuel cladding, which comprises the following preparation steps:
(1) preparation of sample unit bodies: cutting a cladding tube sample unit body with a proper length on a cladding tube along the length direction by using a numerical control slow-walking wire cutting machine, and then sealing one end of the cladding tube by welding;
(2) preparing an electric heating element: determining the power of the heating element according to parameters such as surface power density, surface temperature and the like, determining the number of the heating wires according to the power, uniformly arranging the heating wires in the cladding tube, filling insulating materials in the cladding tube, and compacting the heating wires;
(3) thermocouple assembling: a groove is formed in the outer wall of the cladding pipe, and a thermocouple is embedded and used for monitoring the surface temperature of the electric heating element;
(4) assembling a corrosion sample: the external diameter of the cladding tube is accurately controlled by turning and other methods, the electric heating element is arranged in the cladding tube from the opening end of the cladding tube by interference fit to be assembled into a self-heating corrosion sample, and the electric heating element can be disassembled and replaced by utilizing the structure;
example 3
As shown in fig. 2, the test device for the spontaneous thermal corrosion sample of the fuel cladding of the nuclear power plant provided by the embodiment of the invention comprises a tubular corrosion test section 4, wherein the corrosion test section 4 is provided with a corrosion medium inlet 9 and a corrosion medium outlet 10, the corrosion test section comprises two vertical pipe sections, the upper ends of the vertical pipe sections are clamped and fixed on a fixed support plate 8, the two vertical pipe sections are communicated with each other, the upper ends of the vertical pipe sections are provided with openings for inserting the corrosion sample, and the corrosion sample and the openings of the vertical pipe sections are sealed by a sealing element 3.
When the corrosion sample is tested, the two corrosion samples are placed in the two vertical pipe sections of the test section, then the corrosion sample is sealed with the upper end openings of the vertical pipe sections through the ellipsoidal metal sealing elements, the corrosive medium inlet and the corrosive medium outlet are connected with the test loop, a loop in which corrosive medium flows is formed, and the corrosion test can be carried out.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. A nuclear power plant fuel cladding self-heating corrosion sample is characterized by comprising a cladding tube (1) and an electric heating element (2);
one end of the cladding tube (1) is closed, and the other end of the cladding tube is open, and the cladding tube (1) is made of a cladding material to be subjected to a corrosion test;
the heating element (2) is arranged in the cladding tube (1) and can simulate the nuclear fuel reaction to apply heat flux density to the cladding tube.
2. The self-heating corrosion sample for the nuclear power plant fuel cladding as recited in claim 1, further comprising a sealing member (3), wherein the sealing member (3) is sleeved on the outer wall of the open end of the cladding tube (1), and when the closed end of the cladding tube (1) is inserted into the corrosion test section, the sealing member (3) can realize the sealing between the cladding tube (1) and the corrosion test section.
3. The self-heating corrosion sample for the nuclear power plant fuel cladding as recited in claim 2, characterized in that the sealing member (3) is an ellipsoid-shaped metal block with a circular through hole in the middle, and the cladding tube (1) passes through the through hole and is connected with the sealing member (3) without a gap by welding.
4. The self-heating corrosion sample for the nuclear power plant fuel cladding as recited in claim 1, wherein the electric heating element (2) comprises a cladding tube, resistance wires are uniformly distributed in the cladding tube, and gaps among the resistance wires in the cladding tube are filled with insulating materials.
5. The self-heating corrosion coupon for nuclear power plant fuel cladding according to claim 1, characterized in that the closed end of the cladding tube (1) is sealed by welding.
6. The self-heating corrosion sample for the nuclear power plant fuel cladding as recited in claim 4, wherein a groove is formed in an outer wall of the cladding tube, and a thermocouple is installed in the groove.
7. The self-heating corrosion coupon for nuclear power plant fuel cladding of claim 1, characterized in that the electrical heating element (2) and the cladding tube (1) are removably connected by interference fit.
8. A method for preparing a spontaneous thermal corrosion sample of the nuclear power plant fuel cladding as claimed in any one of claims 1 to 7, comprising the steps of: (1) cutting the cladding tube into a suitable length, and sealing one end of the cladding tube; (2) determining the number of heating wires in the heating element according to the surface power density and the surface temperature, uniformly arranging the heating wires in the cladding tube, filling insulating materials in the cladding tube, and compacting to obtain the heating element; (3) and (3) putting the heating element into the cladding tube by interference fit to assemble the self-heating corrosion sample.
9. A test device for a spontaneous heating corrosion sample of a nuclear power plant fuel cladding is characterized by comprising a tubular corrosion test section (4), wherein the corrosion test section (4) is provided with a corrosion medium inlet (9) and a corrosion medium outlet (10), the corrosion test section (4) comprises a vertical pipe section (5), and the upper end of the vertical pipe section (5) is provided with an opening for inserting the corrosion sample (5) according to any one of claims 1-7.
10. The test device for the spontaneous thermal corrosion sample of the nuclear power plant fuel cladding as claimed in claim 9, characterized by comprising a fixed support plate (8), wherein the upper end of the vertical pipe section (5) is clamped and fixed on the fixed support plate (8), and the corrosion sample and the opening of the vertical pipe section (5) are sealed by a sealing element (3).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111397241.0A CN114121320A (en) | 2021-11-23 | 2021-11-23 | Spontaneous thermal corrosion sample for fuel cladding of nuclear power plant, preparation method and test device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111397241.0A CN114121320A (en) | 2021-11-23 | 2021-11-23 | Spontaneous thermal corrosion sample for fuel cladding of nuclear power plant, preparation method and test device |
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| CN114121320A true CN114121320A (en) | 2022-03-01 |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009031148A (en) * | 2007-07-27 | 2009-02-12 | Nippon Nuclear Fuel Dev Co Ltd | Method and device for testing fuel-cladding tube |
| CN104034651A (en) * | 2014-06-26 | 2014-09-10 | 苏州热工研究院有限公司 | Experiment device special for evaluating corrosion performance of nuclear station cladding material in high temperature steam |
| CN207731670U (en) * | 2018-01-25 | 2018-08-14 | 中国原子能科学研究院 | High heat flux density electrical heating simulated fuel assembly |
| CN110299217A (en) * | 2019-07-24 | 2019-10-01 | 西安交通大学 | It is a kind of for studying the test section of annular fuel involucrum Explosive Failure |
| CN111477368A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Annular fuel cladding test piece capable of heating inside and outside simultaneously |
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2021
- 2021-11-23 CN CN202111397241.0A patent/CN114121320A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2009031148A (en) * | 2007-07-27 | 2009-02-12 | Nippon Nuclear Fuel Dev Co Ltd | Method and device for testing fuel-cladding tube |
| CN104034651A (en) * | 2014-06-26 | 2014-09-10 | 苏州热工研究院有限公司 | Experiment device special for evaluating corrosion performance of nuclear station cladding material in high temperature steam |
| CN207731670U (en) * | 2018-01-25 | 2018-08-14 | 中国原子能科学研究院 | High heat flux density electrical heating simulated fuel assembly |
| CN110299217A (en) * | 2019-07-24 | 2019-10-01 | 西安交通大学 | It is a kind of for studying the test section of annular fuel involucrum Explosive Failure |
| CN111477368A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Annular fuel cladding test piece capable of heating inside and outside simultaneously |
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