CN114609184A - Radioactive material high-temperature steam oxidation test device and using method thereof - Google Patents
Radioactive material high-temperature steam oxidation test device and using method thereof Download PDFInfo
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Abstract
The invention provides a radioactive material high-temperature steam oxidation test device relating to the technical field of oxidation test devices, which comprises a stepping motor, a condenser, a circulating water purification/discharge system, a quenching water tank, a steam generator, a circulating pump, a sample clamp, an electric furnace, a quartz tube support, a sample loading cavity, a computer and an electric thermocouple sleeve, wherein the condenser, the circulating water purification/discharge system, the quenching water tank, the steam generator, the circulating pump and the quartz tube are sequentially connected to form a loop; the sample clamp is connected in the quartz tube and the sample loading cavity, the quartz tube is connected on the electric furnace through the quartz tube support, the electric furnace performs multi-section temperature rise on the quartz tube, and the computer acquires a position-temperature distribution curve in the quartz tube through the thermocouple sleeve. The high-temperature steam oxidation test device for the reactor material with radioactivity under the condition of simulating the loss of coolant accident can realize the functions of automatic operation, accurate temperature control, high test efficiency, less radioactive waste and controllable cooling condition.
Description
Technical Field
The invention relates to the technical field of oxidation test devices, in particular to a radioactive material high-temperature steam oxidation test device and a using method thereof.
Background
Nuclear power safety is the basis of nuclear power development. Most of the radioactive material of the nuclear power plant is present in the fuel elements, and the fuel element cladding material becomes the first barrier for containment of the radioactive material of the nuclear power plant. Under the accident condition, if the fuel cladding is damaged, the first barrier of the radioactive substance of the nuclear power station fails, so that the radioactive substance enters a primary circuit, and the local melting of a reactor core can be caused under the more serious condition, so that the serious accident of the nuclear power station is caused.
A nuclear power plant coolant loss accident (LOCA, loss of coolant accident for short) is a design benchmark accident for nuclear power plants. Under the working condition of LOCA, the fuel element is exposed to the environment of high-temperature steam above 1000 ℃, the internal pressure of the zirconium alloy cladding tube is rapidly increased, the zirconium alloy cladding material is rapidly oxidized and rapidly absorbs hydrogen in the high-temperature steam, embrittlement is promoted, and swelling and cracking are possibly caused by the high internal pressure of the cladding. After the emergency cooling water system is filled with water, the zirconium alloy cladding is suddenly quenched and cooled at high temperature, and the thermal shock effect can further cause the material of the cladding to be embrittled, so that the integrity of the fuel element is damaged.
Under high fuel consumption, an oxidation film generated by water side corrosion of the zirconium alloy cladding can reach dozens of microns, the hydrogen absorption amount of a zirconium alloy matrix can reach hundreds of mg/kg, a great amount of irradiation defects are generated on the zirconium alloy cladding matrix by neutron irradiation, and the microstructure of the zirconium alloy cladding is changed by irradiation. At this point, the fuel element cladding material has undergone more severe embrittlement directly resulting in performance degradation of the fuel element. The LOCA accident, which occurs on this basis, has a greater probability of causing the fuel clad to break.
At present, the behavior of fuel elements under the LOCA accident of the domestic zirconium alloy is researched in China, the performance data of the materials under the LOCA accident are obtained, and an analysis model is established according to the performance data. However, the experiments all use new samples which are not irradiated and corroded, and the high-temperature oxidation performance of the cladding material with burnup is not reported in China, and particularly the performance data of the material under the simulated LOCA accident of the fuel cladding under the high burnup is lacked.
Therefore, the behavior of the zirconium alloy cladding material for the fuel element with burnup under the LOCA accident needs to be researched, and the integrity of the zirconium alloy under high burnup after the LOCA working condition is simulated is evaluated, so that the method has very important significance for improving the material research and development level of the high-performance fuel element in China, improving the autonomous design capability of the fuel element and the component in China, forming a fuel element safety analysis model and analysis and calculation software with autonomous intellectual property rights in China, ensuring the safe operation of a nuclear power station and the like.
On the basis, the high-fuel-consumption sample has higher radioactivity, so that the high-temperature steam oxidation test device for simulating the LOCA has higher requirements.
The invention discloses a high-temperature steam oxidation test device, which belongs to the technical field of oxidation test devices and comprises a deoxygenation water tank, a water supply tank, an evaporator, an electric furnace, a condenser, a circulating water tank, a water pump, a metering pump, a circulating water pump, a plurality of valves and pipelines, wherein the upper end of the deoxygenation water tank is connected with a water replenishing port through the pipeline and the valves arranged on the pipeline, the interior of the evaporator is provided with a deoxygenation pipe, the interior of the electric furnace is provided with a test chamber, a plurality of samples processed by different processes are placed in the electric furnace of the high-temperature steam oxidation test device, the test temperature is changed to obtain the data of oxidation tests at different temperatures, the oxidation resistance of the materials can be compared according to the oxidation test results of the samples processed by different processes under the same parameter conditions, the analysis difference of the oxidation resistance of different surface treatment processes of each sample pressure-bearing part can be obtained, the process for improving the anti-oxidation property of each sample is provided and can be practically realized in engineering. The invention provides a high-temperature steam oxidation test device for a radioactive sample, and solves the special design problem of the radioactive sample. Therefore, the method disclosed in the document and the invention belong to different inventive concepts.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a radioactive material high-temperature steam oxidation test device and a using method thereof.
The radioactive material high-temperature steam oxidation test device provided by the invention comprises a stepping motor, a condenser, a circulating water purification/discharge system, a quenching water tank, a steam generator, a circulating pump, a sample clamp, an electric furnace, a quartz tube support, a sample loading cavity, a computer and a thermocouple sleeve, wherein the condenser, the circulating water purification/discharge system, the quenching water tank, the steam generator, the circulating pump and the quartz tube are sequentially connected to form a loop;
the quartz tube top is connected with the sample loading cavity, the sample clamp is connected in the quartz tube and the sample loading cavity, the quartz tube is connected on the electric furnace through the quartz tube support, the electric furnace performs multi-section temperature rise on the quartz tube, and the computer acquires a position-temperature distribution curve in the quartz tube through the thermocouple sleeve.
Preferably, a plurality of thermocouples are arranged in the thermocouple sleeve, the thermocouples are respectively arranged in the quartz tube at different heights, and the temperature distribution in the quartz tube is measured through the thermocouples.
Preferably, the stepping motor is positioned on the sample loading cavity, one end of the condenser is connected with the quartz tube through a pipeline, the other end of the condenser is connected with the circulating water purifying/discharging system through a pipeline, the circulating water purifying/discharging system is connected with one end of the quenching water tank through a pipeline, the top of the quenching water tank is connected with the bottom of the quartz tube, the other end of the quenching water tank is connected with the circulating pump through a pipeline, and the circulating pump is connected with the steam generator.
Preferably, the quenching water tank comprises a quenching valve, a lifting platform and a sampling valve, and the quenching valve is positioned between the quenching water tank and the quartz tube;
and opening a quenching valve to enable the sample to fall into a quenching water tank for quenching, lifting the quenched sample by a lifting platform, and opening a sampling valve to take out the sample on the lifting platform.
Preferably, the steam generator is provided with an inlet, an outlet and a gas carrying control valve, the inlet is connected with the circulating pump, the outlet and the pipeline at the bottom of the quartz tube are provided with steam valves, and the steam flow rate of the steam generator is adjusted through the gas carrying control valve.
Preferably, the heating temperature of the electric furnace is 0 to 1300 ℃.
Preferably, the sample loading cavity is connected with the sample loading clamp through a sample loading valve, and the sample loading cavity is connected with the quartz tube through a sealing valve.
Preferably, the circulating water purification/discharge system comprises a water quality monitoring system, a cooling water purification system and a cooling water discharge system, the water quality monitoring system, the cooling water purification system and the cooling water discharge system are sequentially connected, and the cooling water monitoring, purification and discharge functions are realized through the water quality monitoring system, the cooling water purification system and the cooling water discharge system.
The invention also provides a use method of the radioactive material high-temperature steam oxidation test device, which comprises the following steps:
s0, calibrating the temperature of a test section before testing, arranging a thermocouple sleeve consisting of a plurality of temperature thermocouples in the test section, heating to a target temperature before testing, reading the temperature measurement results of the thermocouples of a plurality of temperature measurement points in the kettle to obtain the temperature distribution of the test section, and combining the temperature measurement points by a computer to obtain a test section position-temperature distribution curve;
s1, setting a propelling device program on a computer according to the required temperature rise and drop curve, placing a sample on a sample clamp, placing the sample clamp into a sample loading cavity through a mechanical arm, and closing a sample loading valve;
s2, starting a steam generator to introduce steam, introducing the steam into the gas path system to clean, and placing the sample at a position above the quartz tube at a temperature of less than or equal to 150 ℃;
s3, heating the central uniform temperature zone of the test section to a target temperature through a heating program, executing a propulsion program, and propelling the sample to the central uniform temperature zone through a stepping motor, namely after the required position of the oxidation reaction is kept for the required oxidation time, automatically pushing the sample out of the central uniform temperature zone at the required cooling rate according to the set speed; finally, the stepping motor executes a unhooking procedure on the sample, firstly, the quenching valve is opened, then, the sample is separated from the sample clamp, and the sample falls into the quenching water tank to finish the quenching process;
and S4, starting a sampling program for the quenched sample, lifting the sampling table, opening a sampling valve, and sampling by a mechanical arm to finish the experimental process.
Preferably, in steps S2 and S3, the water vapor in the loop is automatically condensed by the condenser to a circulating water purification/discharge system, the circulating water purification/discharge system ensures the quality requirement of the condensed water and discharges the waste, and the circulating pump pumps the purified normal temperature water to the steam generator for the steam generator to continue generating steam.
Compared with the prior art, the invention has the following beneficial effects:
(1) the invention adopts a loop design, water and steam are self-circulated in the test and are purified to discharge sewage, and no additional radioactive waste water and waste gas is generated.
(2) The stepping motor and the valve are controlled by a computer to realize remote control, the sample loading and sampling are simple and convenient, the sample loading and sampling can be finished by a mechanical arm, and additional manual operation is not needed.
(3) The temperature control of the test section is more accurate, the temperature distribution of the test section is accurately obtained by adopting multi-point temperature measurement, and the real-time temperature curve in the test process of the sample is obtained by regulating and controlling the temperature curve of the test sample through the output signal of the computer.
(4) The cooling condition of the invention is controllable, and the quenching water tank is arranged, so that the quenching or re-submerging test can be carried out on a sample, and the temperature rising and falling process of the fuel element under the LOCA working condition can be simulated more accurately.
Drawings
Other features, objects and advantages of the invention will become more apparent upon reading of the detailed description of non-limiting embodiments with reference to the following drawings:
FIG. 1 is a schematic view of the structure of the present invention;
FIG. 2 is a schematic view of the structure of the quenching water tank of the invention.
Reference numbers in the figures:
the device comprises a stepping motor 1, a condenser 2, a circulating water purifying/discharging system 3, a quenching water tank 4, a quenching valve 40, a lifting platform 41, a sampling valve 42, a steam generator 6, a circulating pump 5, a steam valve 7, a sample clamp 8, an electric furnace 9, a quartz tube 10, a quartz tube support 11, a sample loading cavity 12, a computer 13 and a thermocouple well 14.
Detailed Description
The present invention will be described in detail with reference to specific examples. The following examples will assist those skilled in the art in further understanding the invention, but are not intended to limit the invention in any way. It should be noted that it would be obvious to those skilled in the art that various changes and modifications can be made without departing from the spirit of the invention. All falling within the scope of the present invention.
Example 1
The invention provides a radioactive material high-temperature steam oxidation test device which comprises a stepping motor 1, a condenser 2, a circulating water purification/discharge system 3, a quenching water tank 4, a steam generator 6, a circulating pump 5, a steam valve 7, a sample clamp 8, an electric furnace 9, a quartz tube 10, a quartz tube support 11, a sample loading cavity 12, a computer 13 and a thermocouple well 14. The stepping motor 1 is positioned on the sample loading cavity 12, and the stepping motor 1 is connected with the computer 13. One end of the condenser 2 is connected with the quartz tube 10 through a pipeline, the other end of the condenser 2 is connected with the circulating water purifying/discharging system 3 through a pipeline, the circulating water purifying/discharging system 3 is connected with one end of the quenching water tank 4 through a pipeline, and the top of the quenching water tank 4 is connected with the bottom of the quartz tube 10 through a quenching valve 40. The quenching water tank 4 is internally connected with a lifting platform 41, the quenched sample is lifted through the lifting platform 41, a sampling valve 42 is arranged on the quenching water tank 4, and the sample on the lifting platform 41 is taken out by opening the sampling valve 42. The other end of the quenching water tank 4 is connected with a circulating pump 5 through a pipeline, and the circulating pump 5 is connected with a steam generator 6. The steam generator 6 is provided with an inlet, an outlet and a carrier gas control valve, the inlet is connected with the circulating pump 5, the outlet and the pipeline at the bottom of the quartz tube 10 are provided with a steam valve 7, and the steam flow rate of the steam generator 6 is adjusted through the carrier gas control valve.
The condenser 2, the circulating water purifying/discharging system 3, the quenching water tank 4, the steam generator 6, the circulating pump 5 and the quartz tube 10 are connected in sequence to form a loop. The circulating water purification/discharge system 3 comprises a water quality monitoring system, a cooling water purification system and a cooling water discharge system, wherein the water quality monitoring system, the cooling water purification system and the cooling water discharge system are sequentially connected, and the functions of monitoring, purifying and discharging cooling water are realized through the water quality monitoring system, the cooling water purification system and the cooling water discharge system.
The sample loading cavity 12 is connected to the top of the quartz tube 10, the sample loading cavity 12 is connected with the sample loading clamp 8 through a sample loading valve, and the sample loading cavity 12 is connected with the quartz tube 10 through a sealing valve. The sample clamp 8 is connected to the quartz tube 10 and the sample loading cavity 12, the quartz tube 10 is connected to the electric furnace 9 through the quartz tube support 11, and the electric furnace 9 heats the quartz tube 10 in a multi-section mode. Preferably, the electric furnace 9 can realize controllable heating at 0-1300 ℃, and the temperature of the whole test section can be controlled and measured through a multi-temperature test. The quartz tube 10 is used as a high-temperature steam oxidation test section and can bear the high temperature of more than 1300 ℃. The thermowell 14 is provided with a plurality of thermocouples disposed at different heights in the quartz tube 10, respectively, for measuring temperature distribution in the quartz tube, and a computer 13 obtains a position-temperature distribution curve in the quartz tube 10. Preferably, the number of the thermocouples is more than or equal to 3.
Example 2
The invention also provides a use method of the radioactive material high-temperature steam oxidation test device, which comprises the following steps:
s0, calibrating the temperature of the test section before testing, arranging a thermocouple sleeve 14 in the test section, heating to the target temperature before testing, reading the temperature measurement result of a thermocouple of a multi-section temperature measurement point in the kettle to obtain the temperature distribution of the test section, and combining the position of the temperature measurement point by the computer 13 to obtain a position-temperature distribution curve of the test section;
s1, setting a propelling device program on the computer 13 according to the required temperature rise and drop curve, placing the sample on the sample clamp 8, placing the sample clamp 8 into the sample loading cavity 12 through the mechanical arm, and closing the sample loading valve;
s2, starting a steam generator 6 to introduce steam, introducing steam into the gas path system to clean, and placing the sample above the quartz tube 10 at a temperature of less than or equal to 150 ℃;
s3, heating the central uniform temperature zone of the test section to a target temperature of 1200 ℃ through a heating program, executing a propulsion program, and propelling the sample to the central uniform temperature zone by the stepping motor 1, namely after the required position of the oxidation reaction is kept for the required oxidation time, automatically pushing the sample out of the central uniform temperature zone at a set speed at the rate of cooling to 800 ℃ in 30S; finally, the stepping motor 1 executes a unhooking procedure on the sample, firstly the quenching valve 40 is opened, then the sample is separated from the sample clamp 8, and the sample falls into the quenching water tank 4 to complete the quenching process;
and S4, starting a sampling program for the quenched sample, lifting the sampling table 41, opening the sampling valve 42, and sampling by the mechanical arm to complete the experimental process.
In the above steps S2 and S3, the water vapor in the loop is automatically condensed to the circulating water purification/discharge system 3 through the condenser 2, the circulating water purification/discharge system 3 ensures the water quality requirement of the condensed water and discharges the waste, and the circulating pump 5 pumps the purified normal temperature water to the steam generator 6 for the steam generator 6 to continue to generate steam.
In the description of the present application, it is to be understood that the terms "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", and the like indicate orientations or positional relationships based on those shown in the drawings, and are only for convenience in describing the present application and simplifying the description, but do not indicate or imply that the referred device or element must have a specific orientation, be constructed in a specific orientation, and be operated, and thus, should not be construed as limiting the present application.
The foregoing description of specific embodiments of the present invention has been presented. It is to be understood that the present invention is not limited to the specific embodiments described above, and that various changes or modifications may be made by one skilled in the art within the scope of the appended claims without departing from the spirit of the invention. The embodiments and features of the embodiments of the present application may be combined with each other arbitrarily without conflict.
Claims (10)
1. The radioactive material high-temperature steam oxidation test device is characterized by comprising a stepping motor (1), a condenser (2), a circulating water purification/discharge system (3), a quenching water tank (4), a circulating pump (5), a steam generator (6), a sample clamp (8), an electric furnace (9), a quartz tube (10), a quartz tube support (11), a sample loading cavity (12), a computer (13) and a thermocouple sleeve (14), wherein the condenser (2), the circulating water purification/discharge system (3), the quenching water tank (4), the steam generator (6), the circulating pump (5) and the quartz tube (10) are sequentially connected to form a loop;
quartz tube (10) top is connected dress appearance chamber (12), sample anchor clamps (8) connect in quartz tube (10) with in dress appearance chamber (12), quartz tube (10) pass through quartz tube support (11) connect in on electric stove (9), electric stove (9) are right quartz tube (10) carry out the multistage formula and heat up, computer (13) pass through thermocouple sleeve pipe (14) acquire position-temperature distribution curve in quartz tube (10).
2. The radioactive material high-temperature steam oxidation test apparatus according to claim 1, wherein a plurality of thermocouples are disposed in the thermocouple sleeve (14), the plurality of thermocouples are disposed at different heights in the quartz tube (10), and the temperature distribution in the quartz tube (10) is measured by the thermocouples.
3. The radioactive material high-temperature steam oxidation test device according to claim 1, wherein the stepping motor (1) is located on the sample loading cavity (12), one end of the condenser (2) is connected with the quartz tube (10) through a pipeline, the other end of the condenser (2) is connected with the circulating water purifying/discharging system (3) through a pipeline, the circulating water purifying/discharging system (3) is connected with one end of the quenching water tank (4) through a pipeline, the top of the quenching water tank (4) is connected with the bottom of the quartz tube (10), the other end of the quenching water tank (4) is connected with the circulating pump (5) through a pipeline, and the circulating pump (5) is connected with the steam generator (6).
4. The radioactive material high-temperature steam oxidation test device according to claim 3, wherein the quenching water tank (4) comprises a quenching valve (40), a lifting table (41) and a sampling valve (42), and the quenching valve (40) is located between the quenching water tank (4) and the quartz tube (10);
the quenching valve (40) is opened to enable the sample to fall into the quenching water tank (4) for quenching, the lifting platform (41) lifts the quenched sample, and the sampling valve (42) is opened to take out the sample on the lifting platform (41).
5. The radioactive material high-temperature steam oxidation test device according to claim 2, wherein an inlet, an outlet and a carrier gas control valve are arranged on the steam generator (6), the inlet is connected with the circulating pump (5), a steam valve (7) is arranged on a pipeline between the outlet and the bottom of the quartz tube (10), and the steam flow rate of the steam generator (6) is adjusted through the carrier gas control valve.
6. The radioactive material high temperature steam oxidation test apparatus according to claim 1, wherein the heating temperature of the electric furnace (9) is 0 to 1300 ℃.
7. The radioactive material high-temperature steam oxidation test device according to claim 1, wherein the sample loading cavity (12) is connected with the sample loading clamp (8) through a sample loading valve, and the sample loading cavity (12) is connected with the quartz tube (10) through a sealing valve.
8. The radioactive material high-temperature steam oxidation test device according to claim 1, wherein the circulating water purification/discharge system (3) includes a water quality monitoring system, a cooling water purification system, and a cooling water discharge system, which are connected in sequence, and cooling water monitoring, purification, and discharge functions are realized by the water quality monitoring system, the cooling water purification system, and the cooling water discharge system.
9. Use of a radioactive material high temperature steam oxidation test apparatus according to any one of claims 1 to 8, comprising the steps of:
s0, calibrating the temperature of the test section before testing, arranging the thermocouple sleeve (14) in the test section, heating to the target temperature before testing, reading the temperature measurement result of the thermocouple at a plurality of temperature measurement points in the kettle to obtain the temperature distribution of the test section, and obtaining a position-temperature distribution curve of the test section by the computer (13) according to the position of the temperature measurement points;
s1, setting a propelling device program on the computer (13) according to the required temperature rise and drop curve, placing a sample on the sample clamp (8), placing the sample clamp (8) into the sample loading cavity (12) through a mechanical arm, and closing a sample loading valve;
s2, starting the steam generator (6) to introduce steam, introducing steam into the gas path system to clean, and placing the sample at the position of an inlet above the quartz tube (10);
s3, heating the central uniform temperature zone of the test section to a target temperature through a heating program, executing a propulsion program, and propelling the sample to the central uniform temperature zone through the stepping motor (1), namely after the required position of the oxidation reaction is kept for the required oxidation time, automatically pushing the sample out of the central uniform temperature zone at the required cooling rate according to the set speed; finally, the stepping motor (1) carries out unhooking procedure on the sample, firstly the quenching valve (40) is opened, then the sample is separated from the sample clamp (8), and the sample falls into the quenching water tank (4) to complete the quenching process;
s4, starting a sampling program for the sample after quenching, lifting the sampling platform (41), opening the sampling valve (42), and sampling through a mechanical arm to finish the experimental process.
10. The method for using the radioactive material high-temperature steam oxidation test device according to claim 9, wherein in steps S2 and S3, the water vapor in the loop is automatically condensed to the circulating water purification/discharge system (3) through the condenser (2), the circulating water purification/discharge system (3) ensures the quality requirement of the condensed water and discharges waste, and the circulating pump (5) pumps the purified normal-temperature water to the steam generator (6) for the steam generator (6) to continue to generate steam.
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115266794A (en) * | 2022-07-29 | 2022-11-01 | 中国核动力研究设计院 | UO after LOCA high-temperature irradiation2Pore evolution behavior acquisition method |
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Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115266794A (en) * | 2022-07-29 | 2022-11-01 | 中国核动力研究设计院 | UO after LOCA high-temperature irradiation2Pore evolution behavior acquisition method |
| CN115266794B (en) * | 2022-07-29 | 2024-06-04 | 中国核动力研究设计院 | UO after LOCA high-temperature irradiation2Air hole evolution behavior acquisition method |
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