CN108877971B - Thermal aging monitoring device and method for main pipeline of nuclear power plant - Google Patents
Thermal aging monitoring device and method for main pipeline of nuclear power plant Download PDFInfo
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- CN108877971B CN108877971B CN201810371903.9A CN201810371903A CN108877971B CN 108877971 B CN108877971 B CN 108877971B CN 201810371903 A CN201810371903 A CN 201810371903A CN 108877971 B CN108877971 B CN 108877971B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
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- 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
Abstract
The invention discloses a thermal aging monitoring device and method for a main pipeline of a nuclear power plant, which are low in cost and accurate in monitoring. A thermal aging monitoring device of a main pipeline of a nuclear power plant, comprising: the test block is made of the same material as that of the main pipeline of the nuclear power plant; the fixing piece is used for being connected to the main pipeline of the nuclear power plant; the test block is detachably arranged on the fixing piece, the thermal aging monitoring device has a monitoring state and a testing state, and when the thermal aging monitoring device is in the monitoring state, the test block is arranged on the fixing piece to be connected with the main pipeline of the nuclear power plant; when the thermal aging monitoring device is in a test state, the test block is separated from the fixing piece to be processed into a metallographic phase, and a mechanical sample is subjected to metallographic phase and mechanical property tests.
Description
Technical Field
The invention relates to the field of nuclear power plant main pipeline monitoring, in particular to a device and a method for monitoring thermal aging of a nuclear power plant main pipeline.
Background
The nuclear power plant main pipeline is a pipeline connected with main equipment of a reactor coolant system, is an important pressure boundary for containing the reactor coolant, and belongs to first-level nuclear safety and earthquake-resistant I-type equipment. At present, the cast austenitic stainless steel material is widely applied to a main coolant pipeline of a reactor in a light water reactor nuclear power plant. Generally, the cast austenitic stainless steel material of the main pipe system has a ferrite content of 5-25%, and is therefore also referred to as austenitic-ferritic duplex stainless steel. On the one hand, these ferrites improve material strength, improve weldability and resistance to stress corrosion cracking; on the other hand, the excellent mechanical properties of the cast austenitic stainless steel material are beneficial to the manufacturing and processing of parts, parts with complex shapes (such as pump casings, valve bodies, accessories and the like) can be statically cast, and cylindrical parts (such as pipelines) can be centrifugally cast. Nevertheless, the embrittlement of cast austenitic stainless steel materials is unavoidable at high temperatures. And according to research results, the following characteristics are shown: in long-term service at the operating temperature of the light water reactor, the fracture toughness of the main austenitic stainless steel is reduced along with the service time, and the phenomenon is also called thermal aging embrittlement.
The main pipeline is an important component of the nuclear power plant, and is not suitable for destructive detection of the pressure boundary in consideration of the integrity of the pressure boundary, so that the performance of the main pipeline is generally evaluated by adopting a calculation and simulation method, and field direct detection data and methods are lacked. At present, the method for researching and evaluating the heat aging of the cast austenitic stainless steel of the main pipeline mainly comprises the steps of carrying out an accelerated heat aging test on the same material in a laboratory to obtain a series of samples, and carrying out the work of microstructure analysis, mechanical property test and the like on the test blocks to obtain test data. The accelerated thermal aging test temperature is 300-400 ℃, and the longest accelerated thermal aging time is 20000-30000 hours. The higher the accelerated heat aging temperature, the shorter the accelerated heat aging time. However, the following problems are encountered by this research and evaluation method: (1) the service environment simulated by accelerated thermal aging is always different from the actual service temperature environment of the component, and the test analysis result is easy to question; (2) the service life of a nuclear power plant is 40-60 years, and 40-60 years of aging tests cannot be carried out in a laboratory, so that the method is very expensive.
Therefore, in order to solve the above problems, there is a need for a thermal aging monitoring device and method for a main pipeline of a nuclear power plant, which can monitor thermal aging embrittlement of a main pipeline material of the nuclear power plant for a long time, save expensive cost of long-term simulation in a laboratory, and obtain a relatively accurate monitoring result.
Disclosure of Invention
In view of the above problems, the present invention provides a device and a method for monitoring thermal aging of a main pipeline of a nuclear power plant, which are low in cost and accurate in monitoring.
In order to achieve the purpose, the invention adopts the following technical scheme:
a thermal aging monitoring device of a main pipeline of a nuclear power plant, comprising:
the test block is made of the same material as that of the main pipeline of the nuclear power plant;
the fixing piece is used for being connected to the main pipeline of the nuclear power plant;
the test block is detachably arranged on the fixing piece, the thermal aging monitoring device has a monitoring state and a testing state, and when the thermal aging monitoring device is in the monitoring state, the test block is arranged on the fixing piece to be connected with the main pipeline of the nuclear power plant; when the thermal aging monitoring device is in a test state, the test block is separated from the fixing piece to be processed into a metallographic phase, and a mechanical sample is subjected to metallographic phase and mechanical property tests.
In one embodiment, the fixing member is in a ring shape matched with the outer wall of the main pipeline of the nuclear power plant.
In one embodiment, the fixing member includes two semi-ring-shaped steel belts which are semi-ring-shaped and detachably connected, and when the thermal aging monitoring device is in a monitoring state, the two semi-ring-shaped steel belts are connected to form a ring.
In an embodiment, the thermal aging monitoring device further includes a test block box disposed on the fixing member, and the test block is detachably disposed in the test block box.
In one embodiment, the test block box is composed of a side wall and a box cover, and the test block is arranged in a space formed by the side wall and the box cover.
In one embodiment, the test block and the fixing member are directly connected.
In one embodiment, the number of the test blocks is multiple, and the multiple test blocks are arranged on the fixing member at intervals; when the thermal aging monitoring device is in a test state, one test block is separated from the fixing piece to be processed into a test sample for testing.
The invention also adopts the following technical scheme:
a thermal aging monitoring method of a nuclear power plant main pipeline adopts the thermal aging monitoring device of the nuclear power plant main pipeline and comprises the following monitoring steps: arranging the test block on the fixing piece; connecting the fixing piece to a main pipeline of a nuclear power plant; after a monitoring period, the test block is removed from the fixture and the test block is fabricated into a test sample for testing.
In one embodiment, a plurality of test blocks are arranged on the fixing piece; connecting the fixing piece to a main pipeline of a nuclear power plant; after a monitoring period, taking down one of the test blocks to manufacture a test sample for testing; continuing to monitor, and after the next monitoring period, taking down another test block to manufacture a test sample for testing; and circulating the steps until all test blocks are removed.
In one embodiment, the fixing part comprises two semicircular steel belts which are semicircular and detachably connected, all the test blocks are firstly arranged on the two semicircular steel belts respectively, and then the two semicircular steel belts provided with the test blocks are connected to the outer wall of the main pipeline of the nuclear power plant through bolts.
By adopting the technical scheme, compared with the prior art, the invention has the following advantages:
the test block is fixed on a main pipeline of a nuclear power plant through a fixing piece, the test block and the main pipeline are kept in the same service environment, and the test block is taken out for analysis after a period of time (such as 5 years of service), so that the expensive cost of long-term simulation in a laboratory can be saved, and the test block which is most similar to the service condition of the main pipeline can be obtained; therefore, the method has the advantages of capability of monitoring the thermal aging embrittlement of the main pipeline material of the nuclear power plant for a long time, low cost and accurate monitoring.
Drawings
In order to more clearly illustrate the technical solution of the present invention, the drawings needed to be used in the description of the embodiments will be briefly introduced below, and it is obvious that the drawings in the following description are only some embodiments of the present invention, and it is obvious for those skilled in the art to obtain other drawings based on the drawings without creative efforts.
FIG. 1 is a schematic view of a thermal degradation monitoring device of a main pipeline of a nuclear power plant according to the present invention;
fig. 2 is a schematic diagram of monitoring a heat pipe section of a main pipeline of a nuclear power plant by using the thermal aging monitoring device shown in fig. 1.
Wherein, 1, an annular steel belt; 10. a semi-annular steel band; 11. a stud; 12. a bolt; 2. a test block box; 21. a side wall; 22. a box cover; 23. a screw; 3. testing blocks; 4. a main pipeline of a nuclear power plant.
Detailed Description
Preferred embodiments of the present invention will be described in detail below with reference to the accompanying drawings so that the advantages and features of the invention may be more readily understood by those skilled in the art. It should be noted that the description of the embodiments is provided to help understanding of the present invention, but the present invention is not limited thereto. In addition, the technical features involved in the embodiments of the present invention described below may be combined with each other as long as they do not conflict with each other.
The embodiment provides a thermal aging monitoring device for a nuclear power plant main pipeline, which is used for long-term supervision of thermal aging and embrittlement of materials of the nuclear power plant main pipeline, including a main pipeline straight pipe section, an elbow, a welding line, a welding heat affected zone and the like. Fig. 1 shows a thermal aging monitoring device of a main pipeline of a nuclear power plant of the present embodiment, including: a test block 3 made of the same material as that of the main pipeline (straight pipe section, elbow, welding line or welding heat affected zone) of the nuclear power plant; the fixing part is used for being connected to the main pipeline of the nuclear power plant. The test block 3 is detachably arranged on the fixing piece, the thermal aging monitoring device has a monitoring state and a testing state, and when the thermal aging monitoring device is in the monitoring state, the test block 3 is arranged on the fixing piece to be connected with the main pipeline of the nuclear power plant; when the thermal aging monitoring device is in a test state, the test block 3 is separated from the fixing piece to be processed into a metallographic phase, and a mechanical sample is subjected to metallographic and mechanical test analysis.
The fixing piece is in an annular shape matched with the outer wall of the main pipeline of the nuclear power plant, and specifically is an annular steel belt 1 which is composed of two semi-annular steel belts 10 which are respectively in a semi-annular shape. The two ends of the two semi-annular steel belts 10 are detachably connected through bolts 12, so that the two semi-annular steel belts can be conveniently installed and disassembled on a pipeline, and can be conveniently installed on a main pipeline of a nuclear power plant, so that an annular structure sleeved on the outer wall of the main pipeline of the nuclear power plant can be formed when the thermal aging monitoring device is in a monitoring state, and the annular structure is sleeved on a main pipeline heat pipe section 4 connecting a reactor pressure vessel and a steam generator as shown in fig. 2.
The test block 3 is specifically arranged on the annular steel belt 1 through the test block box 2, and the test block 3 is detachably arranged in the test block box 2. The test block box 2 consists of a side wall 21 and a box cover 22, and the test block 3 is arranged in a space formed by the side wall 21 and the box cover 22 and is directly connected with the outer wall of the annular steel strip 1. That is, the test block magazine 2 has no bottom wall. The side wall 21 of the test block box 2 is fixedly connected to the annular steel strip 1 through the stud 11 welded on the annular steel strip 1, after the test block 3 is put in, the box cover 22 of the test block box 2 is fixed on the side wall 21 through the screw 23, and therefore the test block 3 is limited in the test block box 2. In order to be able to display the test blocks 3 in the test block magazine 2, the lid 22 of one of the test block magazines 2 in fig. 1 is hidden from view. The cartridge 2 is substantially cubical in shape.
It should be noted that the number of the test blocks 3 is plural, and the plural test blocks 3 are arranged on the annular steel strip 1 at equal intervals along the circumferential direction; when the thermal aging monitoring device is in a test state, one test block 3 is separated from the annular steel strip 1 to be processed into a test sample for metallographic and mechanical test. In this embodiment, the annular steel strip 1 is specifically provided with 12 test block boxes 2, each test block box 2 is provided with one test block 3, when the main pipeline of the nuclear power plant operates, the thermal aging monitoring device is in a monitoring state, after a period of operation, such as 5 years, namely a monitoring period, one of the test blocks 3 is taken out for test evaluation, the test block is processed into a metallographic sample and a compact tensile sample for test analysis, namely, the thermal aging monitoring device is in a testing state, and then the test block can be continuously monitored for 60 years.
The embodiment also provides a thermal aging monitoring method for the nuclear power plant main pipeline, which adopts the thermal aging monitoring device for the nuclear power plant main pipeline and comprises the following monitoring steps:
arranging a plurality of test blocks 3 on the fixing member; connecting the fixing piece to a main pipeline of a nuclear power plant; after a monitoring period (such as 5 years), taking down one of the test blocks 3 to manufacture a metallographic phase and a mechanical sample for testing; continuing to monitor, and after the next monitoring period, taking down another test block 3 to manufacture a metallographic phase and a mechanical sample for testing; this is repeated until all the test blocks 3 are removed. Namely, every 5 years of operation, when the nuclear power plant overhaul, open the pipeline and keep warm, take out 1 test block box 2, process the test block 3 in the test block box 2 into metallographic specimen, compact tensile sample and carry out experimental analysis, obtain the fracture toughness of material.
Specifically, when the test block testing device is installed on site, all the test blocks 3 are arranged on the two semi-annular steel belts 10 outside the nuclear island respectively, and then the two semi-annular steel belts 10 with the test blocks 3 enter the nuclear island and are connected to the outer wall of the main pipeline of the nuclear power plant through bolts, so that the working time in the nuclear island is shortened, and the radiation dose of personnel is reduced.
As shown in fig. 2, the thermal aging monitoring device can be installed on the outer wall of the heat pipe section of the main pipeline 4 of the primary circuit of the nuclear power plant, so that the test block 3 and the main pipeline 4 are in the same temperature environment condition for monitoring the thermal aging condition of the main pipeline material.
The above embodiments are merely illustrative of the technical ideas and features of the present invention, and are preferred embodiments, which are intended to enable those skilled in the art to understand the contents of the present invention and implement the present invention, and not to limit the scope of the present invention. All equivalent changes or modifications made according to the spirit of the present invention should be covered within the protection scope of the present invention.
Claims (10)
1. A thermal aging monitoring device of a main pipeline of a nuclear power plant is characterized by comprising:
the test block is made of the same material as that of the main pipeline of the nuclear power plant;
the fixing piece is used for being connected to the main pipeline of the nuclear power plant;
the test block is detachably arranged on the fixing piece, the thermal aging monitoring device has a monitoring state and a testing state, and when the thermal aging monitoring device is in the monitoring state, the test block is arranged on the fixing piece to be connected with the main pipeline of the nuclear power plant; when the thermal aging monitoring device is in a test state, the test block is separated from the fixing piece to be processed into a test sample for testing.
2. The thermal aging monitoring device according to claim 1, characterized in that: the mounting be with nuclear power plant's trunk line outer wall matched with annular.
3. The thermal aging monitoring device according to claim 2, characterized in that: the mounting includes that two are semi-annular and the semi-annular steel band that detachably connects, works as when thermal ageing monitoring devices is at monitoring state, two semi-annular steel band is connected and constitutes the annular.
4. The thermal aging monitoring device according to claim 1, characterized in that: the thermal aging monitoring device further comprises a test block box arranged on the fixing piece, and the test block is detachably arranged in the test block box.
5. The thermal degradation monitoring device of claim 4, wherein: the test block box is composed of a side wall and a box cover, and the test block is arranged in a space formed by the side wall and the box cover.
6. The thermal degradation monitoring device of claim 5, wherein: the test block is directly connected with the fixing piece.
7. The thermal aging monitoring device according to claim 1, characterized in that: the number of the test blocks is multiple, and the test blocks are arranged on the fixing piece at intervals; when the thermal aging monitoring device is in a test state, one test block is separated from the fixing piece to be processed into a test sample for testing.
8. A thermal aging monitoring method for a main pipeline of a nuclear power plant is characterized by comprising the following steps: thermal ageing monitoring device for a main pipe of a nuclear power plant according to any one of claims 1 to 7 and comprising the following monitoring steps: arranging the test block on the fixing piece; connecting the fixing piece to a main pipeline of a nuclear power plant; after a monitoring period, the test block is removed from the fixture and the test block is fabricated into a test sample for testing.
9. The thermal aging monitoring method according to claim 8, characterized in that: arranging a plurality of test blocks on the fixing piece; connecting the fixing piece to a main pipeline of a nuclear power plant; after a monitoring period, taking down one of the test blocks to manufacture a test sample for testing; continuing to monitor, and after the next monitoring period, taking down another test block to manufacture a test sample for testing; and circulating the steps until all test blocks are removed.
10. The thermal aging monitoring method according to claim 8, characterized in that: the fixing piece comprises two semicircular steel belts which are connected in a semicircular and detachable mode, all the test blocks are arranged on the semicircular steel belts respectively, and then the two semicircular steel belts which are provided with the test blocks are connected to the outer wall of the main pipeline of the nuclear power plant through bolts.
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| CN201810371903.9A CN108877971B (en) | 2018-04-24 | 2018-04-24 | Thermal aging monitoring device and method for main pipeline of nuclear power plant |
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Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0443260A1 (en) * | 1990-02-16 | 1991-08-28 | Westinghouse Electric Corporation | Method for determining an equivalent average temperature associated with the thermal history of equipment |
| JP4707821B2 (en) * | 2000-11-10 | 2011-06-22 | 住友電工ファインポリマー株式会社 | Fixing belt and manufacturing method thereof |
| CN103594130A (en) * | 2013-10-24 | 2014-02-19 | 中国核电工程有限公司 | Method for preventing pressure pipeline of nuclear power plant from being quickly fractured |
| CN104181096A (en) * | 2014-09-09 | 2014-12-03 | 北京科技大学 | Method for evaluating thermal ageing state of duplex stainless steel by use of thermoelectric potential |
| CN104777280A (en) * | 2015-04-21 | 2015-07-15 | 苏州热工研究院有限公司 | Thermal ageing assessment method of cast austenitic stainless steel of CPR1000 nuclear power plant |
-
2018
- 2018-04-24 CN CN201810371903.9A patent/CN108877971B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0443260A1 (en) * | 1990-02-16 | 1991-08-28 | Westinghouse Electric Corporation | Method for determining an equivalent average temperature associated with the thermal history of equipment |
| JP4707821B2 (en) * | 2000-11-10 | 2011-06-22 | 住友電工ファインポリマー株式会社 | Fixing belt and manufacturing method thereof |
| CN103594130A (en) * | 2013-10-24 | 2014-02-19 | 中国核电工程有限公司 | Method for preventing pressure pipeline of nuclear power plant from being quickly fractured |
| CN104181096A (en) * | 2014-09-09 | 2014-12-03 | 北京科技大学 | Method for evaluating thermal ageing state of duplex stainless steel by use of thermoelectric potential |
| CN104777280A (en) * | 2015-04-21 | 2015-07-15 | 苏州热工研究院有限公司 | Thermal ageing assessment method of cast austenitic stainless steel of CPR1000 nuclear power plant |
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