CN116907680A - Offline temperature detection device for nuclear reactor - Google Patents

Offline temperature detection device for nuclear reactor Download PDF

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Publication number
CN116907680A
CN116907680A CN202310647132.2A CN202310647132A CN116907680A CN 116907680 A CN116907680 A CN 116907680A CN 202310647132 A CN202310647132 A CN 202310647132A CN 116907680 A CN116907680 A CN 116907680A
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CN
China
Prior art keywords
temperature detection
spring
temperature
detection box
memory alloy
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Application number
CN202310647132.2A
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Chinese (zh)
Inventor
王欠欠
许怡幸
扶靓虔
蒋国富
杨文华
张亮
金帅
张慧
朱伟
李虹雨
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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Publication date
Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN202310647132.2A priority Critical patent/CN116907680A/en
Publication of CN116907680A publication Critical patent/CN116907680A/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K13/00—Thermometers specially adapted for specific purposes
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K1/00—Details of thermometers not specially adapted for particular types of thermometer
    • G01K1/08—Protective devices, e.g. casings
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01K—MEASURING TEMPERATURE; MEASURING QUANTITY OF HEAT; THERMALLY-SENSITIVE ELEMENTS NOT OTHERWISE PROVIDED FOR
    • G01K1/00—Details of thermometers not specially adapted for particular types of thermometer
    • G01K1/14—Supports; Fastening devices; Arrangements for mounting thermometers in particular locations
    • 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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  • Physics & Mathematics (AREA)
  • General Physics & Mathematics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The application belongs to the technical field of nuclear reactors, and particularly relates to an offline temperature detection device for a nuclear reactor. The device comprises: the device comprises an upper end, a temperature detection box, three rib pipes and a lower end; a sample loading cavity is formed in the three-rib pipe, and two ends of the sample loading cavity are respectively welded with the upper end head and the lower end head to form a closed inert gas space; the sample and the temperature detection box are fixed inside the three-rib pipe, and the temperature detection box is filled with memory alloy for temperature measurement. The device adopts the memory alloy offline temperature measurement, realizes the accurate measurement of the temperature, has the measurement range of 0-1100 ℃, has the precision error of not more than 3 ℃, cannot cause melting phenomenon to threaten the safety of a reactor, and has the temperature measurement performance far superior to the existing offline measuring devices such as fusible links, silicon carbide and the like.

Description

Offline temperature detection device for nuclear reactor
Technical Field
The application belongs to the technical field of nuclear reactors, and particularly relates to an offline temperature detection device for a nuclear reactor.
Background
From conceptual design to application of nuclear fuel in engineering in the form of components, nuclear fuel and materials must be subjected to in-pile irradiation test during the period of application to critical objects such as nuclear fuel, cladding materials and the like so as to comprehensively evaluate irradiation resistance of the nuclear fuel and the materials and further measure indexes such as safety, reliability, economy, advancement and the like. The irradiation temperature is one of key parameters of irradiation tests in nuclear fuel and material piles, is a key technical index for evaluating the irradiation performance of the nuclear fuel and the material, and also affects the operation safety of the whole reactor. For this purpose, a temperature detector needs to be placed in the irradiation device. The adopted temperature detector needs to have high reliability, stability and accuracy under the strong neutron and gamma mixed radiation field. The static container irradiation test, the fuel center temperature and the irradiation monitoring tube temperature measurement do not have the conditions of leading out temperature signals to be measured outside the reactor, and can only be solved by an off-line temperature measurement mode, and the temperature detection is carried out after the irradiation device is out of the reactor.
The offline temperature detection boxes such as a fuse wire, a SiC thermometer and the like are applied to the current engineering. The fuse wire is arranged in the irradiation device in advance, alloy detection pieces with different melting points are arranged in the irradiation device, the temperature measuring range is less than 660 ℃, the historical highest temperature in the device is qualitatively judged according to the melting condition of the detection pieces after irradiation, the temperature in a certain range is measured, but the specific temperature value cannot be known accurately, and the temperature measuring precision is low. And the temperature measurement method using the metal melting point has great safety risk, and if the temperature measurement method is in a transient high-temperature condition, great thermal stress is generated, and the risk of penetrating the irradiation device is easily caused, so that the safety of the reactor is threatened. The principle of the SiC thermometer is that after the SiC is irradiated by neutrons and subjected to thermal shock of a reactor, when the second annealing temperature is higher than the irradiation temperature, the lattice swelling caused by irradiation can be gradually eliminated, and a relation curve between the SiC and the temperature is successfully built through the testing means such as later dimensional change, resistivity, thermal conductivity, density, lattice size and the like, so that the irradiation temperature is obtained, the current SiC temperature measuring range is 300-1500 ℃, the precision is within 15 ℃, and the precision is low.
Disclosure of Invention
The application aims to provide an offline temperature detection device for a nuclear reactor, which solves the problem of low temperature measurement precision in the prior art.
The technical scheme for realizing the purpose of the application comprises the following steps:
the embodiment of the application provides an off-line temperature detection device for a nuclear reactor, which comprises the following components: the device comprises an upper end, a temperature detection box, three rib pipes and a lower end;
a sample loading cavity is formed in the three-rib pipe, and two ends of the sample loading cavity are respectively welded with the upper end head and the lower end head to form a closed inert gas space;
the sample and the temperature detection box are fixed inside the three-rib pipe, and the temperature detection box is filled with memory alloy for temperature measurement.
Optionally, the memory alloy is TiNi memory alloy.
Optionally, the device comprises a plurality of temperature detection boxes, and the plurality of temperature detection boxes and the test block are alternately fixed in the three-rib tube.
Optionally, different types of TiNi memory alloys are loaded in each temperature detection box.
Optionally, a test block is fixed between two adjacent temperature detection boxes through a clamping block;
the clamp splice adopts the tongs structure, stretches out four tongs respectively for the six degrees of freedom of fixed sample.
Optionally, the apparatus further includes: the spring assembly, the spring support block and the bottom support rod;
the upper end head is connected with the uppermost test block through a spring assembly and a spring supporting block;
the lower end is connected with the lowest temperature detection box through a bottom support rod.
Optionally, the spring assembly includes: the spring base, the spring pressing block and the spring supporting rod;
the spring pressing block is provided with a through hole, the spring supporting rod is provided with a groove, and the upper end of the spring base is provided with a boss;
the lower end of the spring base passes through the through hole and is inserted into the groove; the spring is sleeved on the spring base, one end of the spring is clamped on the boss, and the other end of the spring is clamped on the spring pressing block.
Optionally, the temperature detection box includes: the temperature detection box cover and the temperature detection box body;
the temperature detection box body and the temperature detection box cover are connected through threads;
the memory alloy is loaded in the box body of the temperature detection box.
Optionally, a vent hole for filling inert gas into the sample-filling cavity is formed in the lower end head.
Optionally, the device is made of aluminum alloy.
The beneficial technical effects of the application are as follows:
1) The off-line temperature detection device for the nuclear reactor provided by the embodiment of the application realizes an off-line temperature measurement function by implanting the memory alloy. The device adopts memory alloy off-line temperature measurement, has realized the accurate measurement of temperature. The measuring range of the detecting device can reach 0-1100 ℃, the precision error is not more than 3 ℃, and the cumulative fast neutron fluence of the memory alloy is not less than 1 multiplied by 10 19 n/cm 2 (i.e. E>1 MeV) can not generate melting phenomenon to threaten the safety of a reactor, and the temperature measurement performance is far superior to that of the existing offline measuring devices such as a fuse wire, silicon carbide and the like.
2) According to the offline temperature detection device for the nuclear reactor, provided by the embodiment of the application, the temperature of each sample can be subjected to multiple monitoring by the method of distributing the temperature detection box and the irradiation sample at intervals, so that the offline temperature measurement accuracy is ensured.
3) The off-line temperature detection device for the nuclear reactor provided by the embodiment of the application adopts a structure of a plurality of temperature detection boxes, a sample and a temperature detection box, wherein the temperature detection boxes, the sample and the temperature detection box are arranged at intervals, so that a plurality of temperature results are ensured for each sample, and the temperature measurement error is reduced.
Drawings
FIG. 1 is a schematic diagram of an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application;
FIG. 2 is a schematic view of a three-ribbed tube structure in an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application;
FIG. 3 is a schematic view of a temperature testing box in an off-line temperature detecting device for a nuclear reactor according to an embodiment of the present application;
FIG. 4 is a schematic diagram showing a connection structure between a temperature test box and a sample in an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application;
FIG. 5 is a schematic view of a structure of a clamp block in an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application;
fig. 6a and 6b are schematic structural diagrams of a spring assembly in an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application.
In the figure:
1-an upper end; a 2-spring assembly; 3-a spring support block; 4-sample; 5-a temperature detection box; 6-three-rib pipe; 7-clamping blocks and 71-grippers; 8-a bottom support bar; 9-lower end; 10-a temperature detection box cover; 11-a temperature detection box body; 12-a memory alloy; 13-a spring base; 14-a spring; 15-a spring compression block; 16-spring support bar.
Detailed Description
In order to enable those skilled in the art to better understand the present application, a technical solution in the embodiments of the present application will be clearly and completely described below with reference to the accompanying drawings in the embodiments of the present application. It will be apparent that the embodiments described below are only some, but not all, of the embodiments of the present application. All other embodiments, which can be made by a person skilled in the art without any inventive effort, are within the scope of the present application based on the embodiments described herein.
In-reactor offline temperature measurement technology, because the temperature signal does not have the condition of leading out the measurement outside the reactor, and the existing measurement means are limited, the temperature measurement in a static container, a fuel center and an irradiation monitoring pipe is difficult, and the measurement accuracy is low.
Therefore, the embodiment of the application provides an offline temperature detection device for a nuclear reactor, which overcomes the defects of offline temperature measurement of a fuse wire and a SiC thermometer, offline measures the historical highest temperature of the reactor by utilizing the TiNi memory alloy temperature memory effect, loads TiNi memory alloy with different temperature measurement intervals resistant to strong neutrons and gamma irradiation into the temperature detection device, and improves the offline temperature measurement capability. According to the temperature measurement requirement of the reactor, the temperature detection device loads the two-channel redundant TiNi memory alloy in the temperature measurement zone, the temperature signal is not required to be led out of the reactor for measurement, the strong neutron and gamma irradiation memory alloy representing the temperature measurement zone is placed in the reactor for irradiation along with the reactor, the history highest temperature of the reactor can be obtained through the temperature memory effect test on the memory alloy after the reactor is discharged, and the off-line temperature detection function of the reactor is finally realized.
Based on the foregoing, in order to clearly and specifically describe the above advantages of the present application, a specific embodiment of the present application will be described below with reference to the accompanying drawings.
Referring to fig. 1, the schematic structure of an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application is shown.
The embodiment of the application provides an offline temperature detection device for a nuclear reactor, which comprises the following components: an upper end head 1, a temperature detection box 5, three rib pipes 6 and a lower end head 9;
a sample-loading cavity is formed in the three-rib pipe 6, and two ends of the sample-loading cavity are respectively welded with the upper end head 1 and the lower end head 9 to form a closed inert gas space;
the sample 4 and the temperature detecting box 5 are fixed inside the three-rib pipe 6, and the temperature detecting box 5 is provided with a memory alloy 12 for measuring temperature.
In the embodiment of the application, the device adopts a three-rib pipe type, as shown in fig. 2, and three ribs are additionally arranged on the pipe to adapt to the structural requirement of an irradiation duct. In particular embodiments, the device may be an aluminum alloy material. The device is packaged by adopting an aluminum alloy material, and has reliable sealing performance.
In one example, the lower end 9 is provided with a vent hole for filling inert gas into the sample-filling cavity. The two ends of the three-rib pipe 6 are respectively welded and sealed with the upper end head 1 and the lower end head 9, after the welding is finished, a sufficient amount of inert gas is filled through the vent hole at the lower end head 9, and then the vent hole 9 is welded to be dead, so that a closed inert gas space is formed in the device.
In some possible implementations of the embodiments of the present application, as shown in fig. 3, the temperature detection box 5 includes: a temperature detection box cover 10 and a temperature detection box body 11;
the temperature detection box body 11 and the temperature detection box cover 10 are connected through threads;
the memory alloy 12 is loaded inside the temperature detecting case 11.
The memory alloy 12 is filled in the temperature detection box 5, and the temperature detection box cover 10 and the temperature detection box body 11 are fixed through threads, so that the memory alloy 12 is protected.
As one example, the memory alloy 12 is a TiNi memory alloy, and the reactor historical maximum temperature is measured offline using the TiNi memory alloy temperature memory effect. Through the research and development of the TiNi memory alloy in the earlier stage, the strong neutron radiation and the gamma radiation have no influence on the temperature measurement function of the TiNi memory alloy.
In some possible implementations of the embodiments of the present application, to ensure accuracy of offline temperature measurement, the apparatus includes a plurality of temperature detection boxes 5, and the plurality of temperature detection boxes 5 and the test block 4 are alternately fixed in a three-bar tube 6.
In the embodiment of the application, the temperature of each sample 4 can be subjected to multiple monitoring by the method of distributing the temperature detection boxes 5 and the samples 4 at intervals, and a redundant configuration mode is adopted in the same temperature measuring interval to ensure the accuracy of off-line temperature measurement.
In one example, each temperature probe cartridge 5 is loaded with a different kind of TiNi memory alloy.
In order to ensure the measurement reliability, the embodiment of the application is provided with different types of TiNi memory alloys in different temperature measuring intervals, so that the measurement reliability and the measurement repeatability of the device are ensured.
In some possible implementations of the embodiments of the present application, as shown in fig. 4, a test block 4 is fixed between two adjacent temperature detecting boxes 5 through a clamping block 7. The structure of the clamping block 7 is shown in fig. 5; the clamping blocks 7 are in a gripper structure, and respectively extend out of four grippers 71 to fix the six degrees of freedom of the sample 4. One end of the clamp block 7 is fixed between the grips 71 protruding from the clamp block 7.
In some possible implementations of the embodiments of the present application, the apparatus further includes: a spring assembly 2, a spring support block 3 and a bottom support bar 8;
the upper end head 1 is connected with the uppermost test block 4 through the spring assembly 2 and the spring supporting block 3;
the lower end 9 is connected with the lowest temperature detection box 5 through a bottom support rod 8.
It will be appreciated that when the sample 4 is exposed to irradiation swelling and thermal expansion, sufficient extension margin may be provided by compressing the spring of the spring assembly 2.
As an example, as shown in fig. 6a and 6b, the spring assembly 2 may include: a spring base 13, a spring 14, a spring compression block 15 and a spring support bar 16;
the spring pressing block 15 is provided with a through hole, the spring supporting rod 16 is provided with a groove, and the upper end of the spring base 13 is provided with a boss;
the lower end of the spring base 13 is inserted into the groove through the through hole; the spring 14 is sleeved on the spring base 13, one end of the spring is clamped on the boss, and the other end of the spring is clamped on the spring pressing block 15.
The following describes in detail a specific example of a specific use method of an off-line temperature detection device for a nuclear reactor according to an embodiment of the present application.
In the offline temperature detection device for the nuclear reactor provided by the embodiment of the application, two ends of the sample 4 are respectively inserted into two clamping blocks 7 so as to fix the square sample in the inner hole of the three-rib pipe 6. The clamping blocks 7 are in a gripper structure, and respectively extend out of four grippers 71 to fix the six degrees of freedom of the sample 4. After the two ends of the sample 4 are fixed, a temperature detection box 5 is installed, a temperature memory alloy 12 is filled in the temperature detection box 5, and a box cover 10 of the temperature detection box and a box body 11 of the temperature detection box are fixed through threads, so that the memory alloy 12 is protected. After the required samples 4 are overlapped and placed in the above manner, one end of each sample is placed at the bottom support rod 8, and the other end of each sample is supported by the spring base 13. The spring assembly 2 is then inserted into the spring base 13, and sufficient extension margin can be provided by compressing the spring 14 of the spring assembly 2 when irradiation swelling and thermal expansion of the sample occur. The two ends of the three-rib pipe 6 are respectively welded and sealed with the upper end head 1 and the lower end head 9, after the welding is finished, a sufficient amount of inert gas is filled through the vent hole at the lower end head 9, and then the vent hole is welded to be dead, so that a closed inert gas space is formed in the device.
The present application has been described in detail with reference to the drawings and the embodiments, but the present application is not limited to the embodiments described above, and various changes can be made within the knowledge of those skilled in the art without departing from the spirit of the present application. The application may be practiced otherwise than as specifically described.

Claims (10)

1. An off-line temperature sensing device for a nuclear reactor, the device comprising: an upper end (1), a temperature detection box (5), three reinforcement pipes (6) and a lower end (9);
a sample loading cavity is formed in the three-rib pipe (6), and two ends of the sample loading cavity are respectively welded with the upper end head (1) and the lower end head (9) to form a closed inert gas space;
the sample (4) and the temperature detection box (5) are fixed inside the three-rib pipe (6), and the temperature detection box (5) is provided with a memory alloy (12) for temperature measurement.
2. The off-line temperature detection device for nuclear reactors according to claim 1, characterized in that the memory alloy (12) is a TiNi memory alloy.
3. The off-line temperature detection device for nuclear reactor according to claim 2, characterized in that it comprises a plurality of temperature detection boxes (5), the plurality of temperature detection boxes (5) and the test block (4) being alternately fixed in a triple-ribbed tube (6).
4. An off-line temperature detection device for nuclear reactors according to claim 3, characterized in that each temperature detection box (5) is loaded with a different kind of TiNi memory alloy.
5. An off-line temperature detection device for nuclear reactors according to claim 3, characterized in that a test block (4) is fixed between two adjacent temperature detection boxes (5) by means of a clamping block (7);
the clamping blocks (7) adopt a gripper structure, and respectively extend out of the four grippers to fix the degrees of freedom of the sample (4) in six directions.
6. The offline temperature-sensing device for a nuclear reactor of claim 3, further comprising: the spring assembly (2), the spring supporting block (3) and the bottom supporting rod (8);
the upper end head (1) is connected with the uppermost test block (4) through the spring assembly (2) and the spring supporting block (3);
the lower end head (9) is connected with the lowest temperature detection box (5) through a bottom support rod (8).
7. The offline temperature-detecting device for nuclear reactors according to claim 6, characterized in that the spring assembly (2) comprises: a spring base (13), a spring (14), a spring pressing block (15) and a spring supporting rod (16);
the spring pressing block (15) is provided with a through hole, the spring supporting rod (16) is provided with a groove, and the upper end of the spring base (13) is provided with a boss;
the lower end of the spring base (13) passes through the through hole and is inserted into the groove; the spring (14) is sleeved on the spring base (13), one end of the spring is clamped on the boss, and the other end of the spring is clamped on the spring pressing block (15).
8. The offline temperature-detecting device for nuclear reactors according to any one of claims 1 to 7, characterized in that the temperature-detecting box (5) comprises: a temperature detection box cover (10) and a temperature detection box body (11);
the temperature detection box body (11) is connected with the temperature detection box cover (10) through threads;
the memory alloy (12) is loaded in the temperature detection box body (11).
9. The off-line temperature detection device for nuclear reactor according to any one of claims 1 to 7, characterized in that the lower end (9) is provided with a vent hole for filling inert gas into the sample-containing cavity.
10. The off-line temperature detection device for a nuclear reactor according to any one of claims 1 to 7, wherein the device is made of an aluminum alloy material.
CN202310647132.2A 2023-06-02 2023-06-02 Offline temperature detection device for nuclear reactor Pending CN116907680A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202310647132.2A CN116907680A (en) 2023-06-02 2023-06-02 Offline temperature detection device for nuclear reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202310647132.2A CN116907680A (en) 2023-06-02 2023-06-02 Offline temperature detection device for nuclear reactor

Publications (1)

Publication Number Publication Date
CN116907680A true CN116907680A (en) 2023-10-20

Family

ID=88353897

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202310647132.2A Pending CN116907680A (en) 2023-06-02 2023-06-02 Offline temperature detection device for nuclear reactor

Country Status (1)

Country Link
CN (1) CN116907680A (en)

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