A nuclear material performance testing device and testing method

By designing a nuclear material performance testing device including an accelerator host, a test platform and an oxygen-controlled circuit system, the problems of heavy ion irradiation depth and liquid metal oxygen content adjustment are solved, and material performance testing is achieved under multiple coupling effects is achieved, supporting the development of fourth-generation nuclear reactor materials.

CN116223243BActive Publication Date: 2025-07-04SICHUAN UNIV
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Patent Information

Application Number
CN202211462950.7
Authority / Receiving Office
CN · China
Patent Type
Patents(China)
Current Assignee / Owner
Filing Date
2022-11-21
Publication Date
2025-07-04
Estimated Expiration
2042-11-21

AI Technical Summary

Technical Problem

The existing nuclear material performance testing devices cannot achieve ideal control of heavy ion irradiation depth and precise regulation of oxygen content in liquid metals, and it is difficult to meet the multi-field coupling effect testing requirements of fourth-generation nuclear reactor materials.

Method used

A nuclear material performance testing device including an accelerator host, a test platform, a liquid metal corrosion circuit system and an oxygen-controlled circuit system were designed. The accelerator pipeline was connected to the test platform, and the oxygen-controlled circuit system was introduced to realize the precise control and mechanical testing of liquid metals, and a multi-field coupling experiment was conducted in combination with a single-axis tensile machine.

Benefits of technology

Performance testing under the effect of proton radiation, high-temperature liquid corrosion and mechanical multi-field coupling, can more accurately analyze the macroscopic performance changes of materials, and provide technical support for the development of fourth-generation nuclear reactor materials.

✦ Generated by Eureka AI based on patent content.

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Abstract

The present invention discloses a nuclear material performance testing device and a testing method, belonging to the technical field of nuclear materials. The device includes an accelerator mainframe, a testing platform, a liquid metal corrosion loop system, and an oxygen control loop system. The accelerator mainframe is connected to the testing platform through an accelerator pipeline. The liquid metal corrosion loop system is connected to the testing platform, and the oxygen control loop system is connected to the liquid metal corrosion loop system. The device effectively solves problems such as shallow heavy ion irradiation depth and inability to accurately adjust the oxygen content in liquid metal. It also introduces a material mechanics testing system, realizing performance testing under the combined action of proton irradiation, high-temperature liquid corrosion, and mechanical multi-field coupling, which can be used to further verify the change behavior of the performance of candidate materials under the presence of stress, so as to explore the potential impacts brought about under such operating conditions. The method can obtain an ideal material irradiation depth, thus facilitating more accurate analysis and evaluation of the macroscopic performance of materials.
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Description

Technical Field

[0001] The present invention belongs to the technical field of nuclear materials, and particularly relates to a nuclear material performance testing device and a testing method. Background Art

[0002] The research and development of fourth-generation nuclear reactor technologies such as lead-cooled fast reactors (LFRs), molten salt reactors (MSRs), and sodium-cooled fast reactors (SFRs) are being carried out globally. Different from traditional commercial light water reactors, structural materials will face higher operating temperatures, higher neutron irradiation doses, and more severe corrosion environments. In this case, structural materials have to bear a higher burden, posing more stringent challenges to the service performance of the materials. At the same time, it becomes particularly important to test their performance under the coupling of multiple physical fields close to actual working conditions.

[0003] Ideally, the performance testing of nuclear materials should usually be carried out in a test reactor. However, the number of currently available test reactors is very limited, and there are also disadvantages such as high cost, large analysis difficulty, and long cycle, which pose serious obstacles to the development of nuclear materials that meet engineering applications and seriously affect the process of the deployment of fourth-generation reactors. In contrast, ion irradiation experiments bring new hope to this dilemma. In recent years, some accelerator-based multi-field coupling experimental devices have been developed internationally. Using these devices, it is possible to more effectively simulate the in-reactor service environment of materials for performance testing, including the following devices: the proton irradiation / lead-bismuth corrosion device developed by the Paul Scherrer Institute in Switzerland based on an accelerator, the proton irradiation / lead-bismuth corrosion device developed by the Los Alamos National Laboratory in the United States based on an accelerator, the proton irradiation / high-temperature molten salt corrosion device developed by the Massachusetts Institute of Technology in the United States based on an accelerator, the proton irradiation / high-temperature high-pressure water corrosion device developed by the University of Michigan in the United States based on an accelerator, and the heavy ion irradiation / lead-bismuth corrosion device developed by the Institute of Modern Physics of the Chinese Academy of Sciences in Lanzhou, China based on an accelerator. However, these devices also have some disadvantages. For example, except for the proton irradiation / lead-bismuth corrosion device designed by the Paul Scherrer Institute in Switzerland, which can meet the testing under the coupling of irradiation / corrosion / mechanics multi-fields, the remaining devices can only conduct research on the coupling effect of material irradiation / high-temperature liquid corrosion. However, the proton irradiation / lead-bismuth corrosion device designed by the Paul Scherrer Institute in Switzerland cannot achieve precise control of the oxygen content in the high-temperature liquid and the adjustment of the liquid flow rate. In addition, for the only device developed in China, using heavy ions as irradiation particles, it is difficult to obtain an ideal material irradiation depth, and the oxygen content in the high-temperature liquid cannot be precisely controlled, which is not conducive to the testing and characterization analysis of the macroscopic properties of materials. Therefore, in order to effectively solve these problems and facilitate the development of nuclear materials, the development of more advanced ion irradiation / high-temperature liquid corrosion / mechanics multi-field coupling performance testing devices and their experimental methods has become an important research direction in the field of nuclear materials. Summary of the Invention

[0004] An object of an embodiment of the present invention is to provide a nuclear material performance testing device, which has a simple structure, is convenient to use, and can preferably improve the above problems.

[0005] Another object of an embodiment of the present invention is to provide a nuclear material performance testing method, by which an ideal material irradiation depth can be obtained, so as to facilitate more accurate analysis of the macroscopic properties of the material.

[0006] The embodiment of the present invention is implemented as follows:

[0007] The embodiment of the present invention provides a nuclear material performance testing device, including an accelerator mainframe, a testing platform, a liquid metal corrosion loop system, and an oxygen control loop system. The accelerator mainframe is communicated with the testing platform through an accelerator pipeline. The liquid metal corrosion loop system includes a liquid storage tank and an oxygen control tank. The oxygen control tank is communicated with the liquid inlet of the testing platform through a first infusion pipe. A permanent magnet pump, a flowmeter, and a first liquid control valve are sequentially arranged on the first infusion pipe. The oxygen control tank is communicated with the liquid outlet of the testing platform through a second infusion pipe. The liquid storage tank is communicated with the oxygen control tank through a third infusion pipe. A second liquid control valve is arranged on the third infusion pipe. The oxygen control loop system is communicated with the liquid storage tank and the oxygen control tank through air pipes respectively.

[0008] Furthermore, the testing platform includes a uniaxial tensile machine, a second computer, and a sensor. The sensor is arranged on the uniaxial tensile machine. The second computer is communicatively connected with the sensor and the uniaxial tensile machine. The accelerator mainframe is communicated with the proton inlet of the uniaxial tensile machine through an accelerator pipeline. The oxygen control tank is communicated with the liquid inlet of the uniaxial tensile machine through a first infusion pipe. The oxygen control tank is communicated with the liquid outlet of the uniaxial tensile machine through a second infusion pipe.

[0009] Furthermore, a first liquid level probe and a first temperature probe are arranged in the oxygen control tank. A first pressure gauge is arranged on the outer wall of the oxygen control tank. A second liquid level probe and a second temperature probe are arranged in the liquid storage tank. A second pressure gauge is arranged on the outer wall of the liquid storage tank.

[0010] Furthermore, expansion joints are arranged on both the first infusion pipe and the second infusion pipe.

[0011] Furthermore, heat tracing and insulation layers are arranged on the outer side walls of the liquid storage tank, the oxygen control tank, the first infusion pipe, the second infusion pipe, and the third infusion pipe.

[0012] Further, the oxygen control loop system includes a first computer, a vacuum pump, a filter box, an oxygen probe, a first high-pressure gas cylinder, a second high-pressure gas cylinder, a third high-pressure gas cylinder, a fourth high-pressure gas cylinder, and a flow controller. The liquid storage tank is communicated with the filter box through a first air pipe, and a first air control valve and a second air control valve are arranged on the first air pipe; the vacuum pump is arranged on the first air pipe and between the second air control valve and the filter box; the oxygen control box is communicated with the first air pipe through a second air pipe, and the connection point is between the first air control valve and the second air control valve, and a third air control valve is arranged on the second air pipe; the oxygen control box is also directly connected to the filter box through a third air pipe, and a fourth air control valve is arranged on the third air pipe; the first high-pressure gas cylinder is communicated with the first air pipe through a fourth air pipe, and the connection point is between the first air control valve and the second air control valve, and a fifth air control valve is arranged on the fourth air pipe; the flow controller is communicated with the oxygen control box through a fifth air pipe, and a sixth air control valve is arranged on the fifth air pipe; the second high-pressure gas cylinder is communicated with the flow controller through a sixth air pipe, and a seventh air control valve is arranged on the sixth air pipe; the third high-pressure gas cylinder is communicated with the flow controller through a seventh air pipe, and an eighth air control valve is arranged on the seventh air pipe; the fourth high-pressure gas cylinder is communicated with the flow controller through an eighth air pipe, and a ninth air control valve is arranged on the eighth air pipe; the oxygen probe is arranged in the oxygen control box; an exhaust pipe is arranged on the filter box, and the first computer is communicatively connected to the oxygen probe and the flow controller.

[0013] An embodiment of the present invention also provides a method for testing the performance of nuclear materials, including the following steps:

[0014] S1: Fix the first experimental sample and the second experimental sample on the corresponding workstations of the test section of the uniaxial tensile machine respectively;

[0015] S2: Put the corrosive material into the liquid storage tank and seal it. Open the first air control valve, the second air control valve, and the third air control valve, and then turn on the vacuum pump to evacuate the liquid storage tank and the oxygen control box. When the vacuum degrees of the liquid storage tank and the oxygen control box are lower than 10 -4 Pa, close the first air control valve, the second air control valve, the third air control valve, and the vacuum pump;

[0016] S3: Open the seventh air control valve, the sixth air control valve, the fifth air control valve, and the first air control valve respectively. Introduce the gas in the first high-pressure gas cylinder into the liquid storage tank, and introduce the gas in the second high-pressure gas cylinder into the oxygen control box until the air pressures shown on the first pressure gauge and the second pressure gauge reach one standard atmospheric pressure. Then close all the air control valves to establish a complete protection atmosphere;

[0017] S4: Heat the liquid storage tank, oxygen control tank, first infusion tube, second infusion tube, and third infusion tube through the tracing and heat preservation layer until the corrosive material in the liquid storage tank is completely liquefied, and maintain the heating temperature.

[0018] S5: Open the fifth pneumatic control valve and the first pneumatic control valve, and introduce the gas in the first high-pressure gas cylinder into the liquid storage tank. When the air pressure in the liquid storage tank is greater than 2 standard atmospheric pressures, close the fifth pneumatic control valve and the first pneumatic control valve.

[0019] S6: Open the third pneumatic control valve, the fourth pneumatic control valve, and the second liquid control valve, so that the liquid corrosive material in the liquid storage tank flows into the oxygen control tank under the action of the pressure difference. When the first liquid level probe monitors that the liquid level in the oxygen control tank reaches the set value, close the second liquid control valve, and then open the first pneumatic control valve. After the pressure in the liquid storage tank is the same as the atmospheric pressure, close the first pneumatic control valve.

[0020] S9: After maintaining the flow rate and oxygen content of the liquid corrosive material stable, start the accelerator mainframe, so that the protons generated by the accelerator mainframe act on the first experimental sample and the second experimental sample. Then, set the required static load value and the size parameters of the sample through the second computer, and load the static load onto the tensile sample through the uniaxial tensile machine, where the magnitude of the tensile stress is set to the required value in the experiment. The sensor will transmit the static load value and the displacement value to the second computer, so as to carry out the coupling test according to the requirements.

[0021] S8: Open the sixth pneumatic control valve, the eighth pneumatic control valve, and the ninth pneumatic control valve, and control the gas flow rate through the flow control valve, so that the gas in the third high-pressure gas cylinder and the fourth high-pressure gas cylinder flows into the oxygen control tank as needed, ensuring that the oxygen content of the liquid corrosive material in the oxygen control tank reaches the required value in the experiment.

[0022] S9: After maintaining the flow rate and oxygen content of the liquid corrosive material stable, start the accelerator mainframe, so that the protons generated by the accelerator mainframe act on the first experimental sample and the second experimental sample. Then, set the required static load value and the size parameters of the sample through the second computer, and load the static load onto the tensile sample through the uniaxial tensile machine, where the magnitude of the tensile stress is set to the required value in the experiment. The sensor will transmit the static load value and the displacement value to the second computer, so as to carry out the coupling test according to the requirements.

[0023] S10: After the coupling test is completed, first turn off the uniaxial tensile machine and the accelerator host, then turn off the ninth pneumatic control valve, the eighth pneumatic control valve, the sixth pneumatic control valve, the third pneumatic control valve and the fourth pneumatic control valve. Gradually reduce the loop temperature through the heat tracing and insulation layer, then turn off the permanent magnet pump, open the second hydraulic control valve, and the liquid corrosion material in the oxygen control box flows back into the liquid storage tank under the action of gravity. After the liquid corrosion material in the oxygen control box has finished flowing back, close the second hydraulic control valve, then turn on the permanent magnet pump to clean and flow back the remaining part of the liquid corrosion material in the pipeline into the oxygen control box, and turn off the permanent magnet pump. Finally, continue to reduce the loop temperature. When the temperature of the liquid metal corrosion loop system drops to room temperature, remove the first experimental sample and the second experimental sample respectively.

[0024] Further, the heating and maintaining temperature in step S4 is not lower than the melting point of the corrosion material medium; in step S8, the oxygen content of the liquid corrosion material is controlled to be 10 -8 -10 -4 wt%.

[0025] Further, in step S9, the parameters of the accelerator host, the proton energy and the proton beam current intensity, are set to the values required by the experiment.

[0026] Further, the diameter of the first experimental sample is 3 - 10 mm, and the thickness is 50 - 500 μm; the length of the second experimental sample is 5 - 50 cm, the thickness is 50 μm - 1 mm, and the distance between the first experimental sample and the second experimental sample is 1 mm - 1 cm.

[0027] The beneficial effects of the present invention are as follows:

[0028] The nuclear material performance testing device provided by the embodiment of the present invention effectively solves problems such as shallow heavy ion irradiation depth and inability to accurately adjust the oxygen content in liquid metal. The device introduces a material mechanics testing system, realizes performance testing under the coupling action of proton irradiation, high-temperature liquid corrosion and mechanics multi-fields, and can be used to further verify the change behavior of the performance of candidate materials under the existence of stress, so as to explore the potential influence brought by such operating conditions.

[0029] The nuclear material performance testing method provided by the embodiment of the present invention is convenient to operate. Through this method, an ideal material irradiation depth can be obtained, so as to facilitate more accurate analysis and evaluation of the macroscopic performance of the material, and provide an effective technical guarantee for advanced nuclear materials to meet reactor applications in the future. Description of the Drawings

[0030] To more clearly illustrate the technical solutions of the embodiments of the present invention, the following will briefly introduce the drawings required for the embodiments. It should be understood that the following drawings only show some embodiments of the present invention, and thus should not be regarded as limiting the scope. For those of ordinary skill in the art, without creative efforts, other related drawings can also be obtained based on these drawings.

[0031] Figure 1 Schematic structural diagram of the nuclear material performance testing device provided by the embodiments of the present invention;

[0032] In the figure: 10 - accelerator mainframe; 11 - accelerator pipeline; 20 - uniaxial tensile machine; 21 - second computer; 22 - sensor; 30 - liquid storage tank; 31 - oxygen control box; 32 - first infusion tube; 33 - permanent magnet pump; 34 - flowmeter; 35 - first liquid control valve; 36 - second infusion tube; 37 - expansion joint; 38 - third infusion tube; 39 - second liquid control valve; 40 - first liquid level probe; 41 - first temperature probe; 42 - first pressure gauge; 43 - second liquid level probe; 44 - second temperature probe; 45 - second pressure gauge; 50 - first computer; 51 - vacuum pump; 52 - filter box; 53 - oxygen probe; 54 - first high-pressure gas cylinder; 55 - second high-pressure gas cylinder; 56 - third high-pressure gas cylinder; 57 - fourth high-pressure gas cylinder; 58 - flow controller; 60 - first air pipe; 61 - second air pipe; 62 - third air pipe; 63 - fourth air pipe; 64 - fifth air pipe; 65 - sixth air pipe; 66 - seventh air pipe; 67 - eighth air pipe; 70 - first air control valve; 71 - second air control valve; 72 - third air control valve; 73 - fourth air control valve; 74 - fifth air control valve; 75 - sixth air control valve; 76 - seventh air control valve; 77 - eighth air control valve; 78 - ninth air control valve. Specific embodiments

[0033] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the following will clearly and completely describe the technical solutions in the embodiments of the present invention in conjunction with the drawings in the embodiments of the present invention. Obviously, the described embodiments are part of the embodiments of the present invention, rather than all of the embodiments. Usually, the components of the embodiments of the present invention described and shown in the drawings here can be arranged and designed in various different configurations. Based on the embodiments of the present invention, all other embodiments obtained by those of ordinary skill in the art without creative efforts fall within the scope of protection of the present invention.

[0034] In the description of the present invention, it should be noted that the terms "first", "second", "third", etc. are only used for distinguishing descriptions and cannot be understood as indicating or implying relative importance.

[0035] In the description of the present invention, it should also be noted that unless otherwise clearly specified and defined, the terms "arrangement", "installation", "connection", and "coupling" should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection, a direct connection, or an indirect connection through an intermediate medium, and it can be the communication inside two components. For those of ordinary skill in the art, the specific meanings of the above terms in the present invention can be understood according to specific situations.

[0036] Embodiment 1

[0037] Reference Figure 1 As shown, Embodiment 1 of the present invention provides a nuclear material performance testing device, which includes an accelerator mainframe 10, a testing platform, a liquid metal corrosion loop system, and an oxygen control loop system.

[0038] The accelerator mainframe 10 is used to generate proton energy. In this embodiment, the accelerator mainframe 10 adopts a CS-30 cyclotron produced by The Cyclotron Corporation of the United States, and the proton energy it generates is 30 MeV, and the proton beam current is 15 μA.

[0039] The testing platform includes a uniaxial tensile machine 20, a second computer 21, and a sensor 22. The sensor 22 is arranged on the uniaxial tensile machine 20. The second computer 21 is communicatively connected to the sensor 22 and the uniaxial tensile machine 20. The accelerator mainframe 10 is connected to the proton inlet of the test section of the uniaxial tensile machine 20 through an accelerator pipeline 11. The maximum tensile force of the uniaxial tensile machine 20 satisfies 15 kN.

[0040] The liquid metal corrosion loop system includes a liquid storage tank 30 and an oxygen control tank 31. The oxygen control tank 31 is connected to the liquid inlet of the test section of the uniaxial tensile machine 20 through a first infusion pipe 32. A permanent magnet pump 33, a flow meter 34, and a first liquid control valve 35 are sequentially arranged on the first infusion pipe 32. The oxygen control tank 31 is connected to the liquid outlet of the test section of the uniaxial tensile machine 20 through a second infusion pipe 36. Expansion joints 37 are arranged on both the first infusion pipe 32 and the second infusion pipe 36. The main purpose of the expansion joint 37 is to absorb the thermal stress and thermal deformation generated during the heating and cooling stages of the high-temperature loop through its own contraction, protecting the equipment and pipelines. The permanent magnet pump 33 is used to drive the liquid metal in the oxygen control tank 31 to circulate along the loop. The liquid storage tank 30 is connected to the oxygen control tank 31 through a third infusion pipe 38. A second liquid control valve 39 is arranged on the third infusion pipe 38.

[0041] Inside the oxygen control box 31, there are a first liquid level probe 40 and a first temperature probe 41. On the outer wall of the oxygen control box 31, there is a first pressure gauge 42. The first liquid level probe 40 is used to monitor the liquid level inside the oxygen control box 31, the first temperature probe 41 is used to monitor the temperature inside the oxygen control box 31, and the first pressure gauge 42 is used to monitor the pressure inside the oxygen control box 31. Inside the liquid storage tank 30, there are a second liquid level probe 43 and a second temperature probe 44. On the outer wall of the liquid storage tank 30, there is a second pressure gauge 45. The second liquid level probe 43 is used to monitor the liquid level inside the liquid storage tank 30, the second temperature probe 44 is used to monitor the temperature inside the liquid storage tank 30, and the second pressure gauge 45 is used to monitor the pressure inside the liquid storage tank 30. In this embodiment, the first liquid level probe 40 and the second liquid level probe 43 are commercial liquid lead-bismuth alloy liquid level detectors, and the first temperature probe 41 and the second temperature probe 44 are made of thermocouple materials.

[0042] On the outer side walls of the liquid storage tank 30, the oxygen control box 31, the first infusion pipe 32, the second infusion pipe 36, and the third infusion pipe 38, there are all heat tracing and insulation layers, which are used to heat the liquid storage tank 30, the oxygen control box 31, the first infusion pipe 32, the second infusion pipe 36, and the third infusion pipe 38, and can also ensure the stability of the internal temperatures of the liquid storage tank 30, the oxygen control box 31, the first infusion pipe 32, the second infusion pipe 36, and the third infusion pipe 38.

[0043] The liquid storage tank 30 and the oxygen control box 31 are made of T91 steel material and internally coated with an Al2O3 coating. The first infusion pipe 32, the second infusion pipe 36, and the third infusion pipe 38 can be made of 316L steel material.

[0044] The oxygen control loop system includes a first computer 50, a vacuum pump 51, a filter box 52, an oxygen probe 53, a first high-pressure gas cylinder 54, a second high-pressure gas cylinder 55, a third high-pressure gas cylinder 56, a fourth high-pressure gas cylinder 57, and a flow controller 58.

[0045] The liquid storage tank 30 is communicated with the filtration tank 52 through a first air pipe 60. A first pneumatic control valve 70 and a second pneumatic control valve 71 are provided on the first air pipe 60. The vacuum pump 51 is arranged on the first air pipe 60 and is located between the second pneumatic control valve 71 and the filtration tank 52. The oxygen control tank 31 is communicated with the first air pipe 60 through a second air pipe 61, and the connection point is located between the first pneumatic control valve 70 and the second pneumatic control valve 71. A third pneumatic control valve 72 is provided on the second air pipe 61. The oxygen control tank 31 is also directly connected to the filtration tank 52 through a third air pipe 62. A fourth pneumatic control valve 73 is provided on the third air pipe 62. The first high-pressure gas cylinder 54 is communicated with the first air pipe 60 through a fourth air pipe 63, and the connection point is located between the first pneumatic control valve 70 and the second pneumatic control valve 71. A fifth pneumatic control valve 74 is provided on the fourth air pipe 63. The flow controller 58 is communicated with the oxygen control tank 31 through a fifth air pipe 64. A sixth pneumatic control valve 75 is provided on the fifth air pipe 64. The second high-pressure gas cylinder 55 is communicated with the flow controller 58 through a sixth air pipe 65. A seventh pneumatic control valve 76 is provided on the sixth air pipe 65. The third high-pressure gas cylinder 56 is communicated with the flow controller 58 through a seventh air pipe 66. An eighth pneumatic control valve 77 is provided on the seventh air pipe 66. The fourth high-pressure gas cylinder 57 is communicated with the flow controller 58 through an eighth air pipe 67. A ninth pneumatic control valve 78 is provided on the eighth air pipe 67.

[0046] An oxygen probe 53 is arranged in the oxygen control tank 31. The oxygen probe 53 is used to monitor the oxygen content of the liquid metal in the oxygen control tank 31. The oxygen probe 53 uses a commercially available Pt alloy material oxygen sensor 22. An exhaust pipe is provided on the filtration tank 52. The first computer 50 is communicatively connected to the oxygen probe 53 and the flow controller 58.

[0047] In this embodiment, the first high-pressure gas cylinder 54 contains high-purity Ar gas, the second high-pressure gas cylinder 55 contains high-purity Ar gas, the third high-pressure gas cylinder 56 contains a mixed gas of Ar and H2, and the fourth high-pressure gas cylinder 57 contains a mixed gas of Ar and O2.

[0048] Embodiment 2

[0049] Embodiment 2 of the present invention provides a method for testing the performance of nuclear materials, which uses the testing device of Embodiment 1 for testing.

[0050] The testing method includes the following steps:

[0051] S1: Fix the first experimental sample and the second experimental sample on the corresponding workstations of the test section of the uniaxial tensile machine 20 respectively; and perform a leak detection process to ensure the airtightness during the experimental process.

[0052] In this embodiment, the first experimental sample and the second experimental sample use commercially available 9Cr ferritic / martensitic steel (F / M steel).

[0053] The diameter of the first experimental sample is 3 - 10 mm, and the thickness is 50 - 500 μm; the length of the second experimental sample is 5 - 50 cm, the thickness is 50 μm - 1 mm, and the distance between the first experimental sample and the second experimental sample is 1 mm - 1 cm.

[0054] It should be noted that the samples in this step are prepared as follows. Based on the proton energy generated by the accelerator, using the SRIM - 2013 software, the theoretically selectable thicknesses of the first experimental sample for the study of the proton irradiation / liquid metal corrosion coupling effect and the second experimental sample for the study of the proton irradiation / liquid metal corrosion / mechanical multi - field coupling effect are 0.1 mm and 0.4 mm respectively, and the distance between them is 1 mm. Here, it should be noted that the sample / liquid metal coupling interface should be far from the irradiation damage Bragg peak region to effectively reduce the spatial variation of irradiation damage caused by uneven thickness; subsequently, a stress - free, flat and smooth surface is prepared successively using a wire - cut electrical discharge machine, 400# sandpaper, 2000# sandpaper, 3000# sandpaper, a grinding and polishing machine, and a vibration polishing machine. The thickness is measured by a micrometer and further confirmed by a scanning electron microscope (error ≤ 3%).

[0055] S2: Put the corrosion material into the liquid storage tank 30 and seal it. Open the first pneumatic control valve 70, the second pneumatic control valve 71, the third pneumatic control valve 72, and then turn on the vacuum pump 51 to evacuate the liquid storage tank 30 and the oxygen control box 31. When the vacuum degrees of the liquid storage tank 30 and the oxygen control box 31 are lower than 10 -4 Pa, close the first pneumatic control valve 70, the second pneumatic control valve 71, the third pneumatic control valve 72 and the vacuum pump 51.

[0056] In this embodiment, the corrosion material is a lead - bismuth eutectic alloy, its melting point is 125 °C, and the mass ratio of Pb and Bi elements is 44.5:55.5.

[0057] S3: Open the seventh pneumatic control valve 76, the sixth pneumatic control valve 75, the fifth pneumatic control valve 74, and the first pneumatic control valve 70 respectively. Introduce the gas in the first high - pressure gas cylinder 54 into the liquid storage tank 30, and introduce the gas in the second high - pressure gas cylinder 55 into the oxygen control box 31 until the first pressure gauge 42 and the second pressure gauge 45 show that the air pressure reaches one standard atmosphere, and then close all the pneumatic control valves, thus establishing a protective atmosphere.

[0058] S4: Heat the liquid storage tank 30, the oxygen control box 31, the first liquid delivery pipe 32, the second liquid delivery pipe 36 and the third liquid delivery pipe 38 through the heat - tracing and heat - preservation layer until the corrosion material in the liquid storage tank 30 is completely liquefied, and maintain the heating temperature.

[0059] In this step, the heating temperature is maintained not lower than the melting point of the corrosive material medium. In this embodiment, the heating temperature is maintained not lower than 200 °C (taking 200 °C here), and the temperature is accurately monitored by the first temperature probe 41 and the second temperature probe 44.

[0060] S5: Open the fifth pneumatic control valve 74 and the first pneumatic control valve 70, and introduce the gas (Ar gas) in the first high-pressure gas cylinder 54 into the liquid storage tank 30. When the air pressure in the liquid storage tank 30 is greater than 2 standard atmospheric pressures, close the fifth pneumatic control valve 74 and the first pneumatic control valve 70.

[0061] S6: Open the third pneumatic control valve 72, the fourth pneumatic control valve 73 and the second liquid control valve 39, so that the liquid corrosive material in the liquid storage tank 30 flows into the oxygen control box 31 under the action of the pressure difference. When the first liquid level probe 40 monitors that the liquid level in the oxygen control box 31 reaches the set value, close the second liquid control valve 39, and then open the first pneumatic control valve 70. After the pressure in the liquid storage tank 30 is equal to the atmospheric pressure, close the first pneumatic control valve 70.

[0062] S7: Start the permanent magnet pump 33 and the first liquid control valve 35, so that the liquid corrosive material flows from the oxygen control box 31 through the first infusion tube 32 into the test section of the uniaxial tensile machine 20, and then flows back to the oxygen control box 31 through the second infusion tube 36, keeping the liquid corrosive material circulating. The flow rate meets 0.5 - 3 m / s, and then heat the oxygen control box 31, the first infusion tube 32 and the second infusion tube 36 to the required experimental temperature through the heat tracing and insulation layer. The maximum temperature can reach 650 °C.

[0063] In this embodiment, the corrosion temperature is set to 500 °C, and the flow rate of the liquid corrosive material is maintained at 1 m / s. The flow rate is monitored by the flow meter 34.

[0064] S8: Open the sixth pneumatic control valve 75, the eighth pneumatic control valve 77 and the ninth pneumatic control valve 78, and control the gas flow rate through the flow controller 58, so that the gases in the third high-pressure gas cylinder 56 and the fourth high-pressure gas cylinder 57 flow into the oxygen control box 31 as needed, ensuring that the oxygen content of the liquid corrosive material in the oxygen control box 31 reaches the required experimental value.

[0065] In this embodiment, the oxygen content of the liquid corrosive material is controlled to be 10 -8 -10 -4 wt%, preferably 10 -6 wt%, and the oxygen content is monitored by the oxygen probe 53. In this process, the first computer 50 reasonably adjusts the gas flow rate according to the real-time oxygen signal, so as to achieve accurate adjustment of the oxygen content. The tail gas is discharged into the air after being treated by the filter box 52.

[0066] S9: After maintaining the flow rate and oxygen content of the liquid corrosion material stable, turn on the accelerator mainframe 10 so that the protons generated by the accelerator mainframe act on the first experimental sample and the second experimental sample. Then, set the static load value and the size parameters of the sample required for the experiment through the second computer 21. Load the static load onto the tensile sample through the uniaxial tensile machine 20, where the magnitude of the tensile stress is set to the value required for the experiment. The sensor 22 will transmit the static load value and the displacement value to the second computer 21, thereby conducting the coupling test according to the requirements.

[0067] In this step, the parameters of the accelerator mainframe 10 are set as proton energy 30 MeV and proton beam intensity 15 μA. The magnitude of the tensile stress is set to 100 Mpa.

[0068] S10: After the coupling test is completed, first turn off the uniaxial tensile machine 20 and the accelerator mainframe 10, then turn off the ninth pneumatic control valve 78, the eighth pneumatic control valve 77, the sixth pneumatic control valve 75, the third pneumatic control valve 72 and the fourth pneumatic control valve 73. Gradually reduce the loop temperature through the heat tracing and insulation layer (at this time, the loop temperature still needs to be higher than the liquefaction temperature of the corrosion material to ensure that the liquid corrosion material in the loop will not solidify, and it can be reduced to 200 °C). Then turn off the permanent magnet pump 33, open the second liquid control valve 39, and the liquid corrosion material in the oxygen control box 31 will flow back into the liquid storage tank 30 under the action of gravity. After the liquid corrosion material in the oxygen control box 31 has finished flowing back, close the second liquid control valve 39, then turn on the permanent magnet pump 33 to clean and flow back the remaining part of the liquid corrosion material in the pipeline into the oxygen control box 31, and turn off the permanent magnet pump 33. Finally, continue to reduce the loop temperature. When the temperature of the liquid metal corrosion loop system drops to room temperature, remove the first experimental sample and the second experimental sample respectively.

[0069] The present invention is not limited to the above optional embodiments. Anyone can obtain other various forms of products under the inspiration of the present invention. However, no matter what changes are made in its shape or structure, as long as the technical solutions fall within the scope defined by the claims of the present invention, they all fall within the protection scope of the present invention.

Claims

1. A nuclear material performance testing device, characterized in that: It includes an accelerator mainframe, a test platform, a liquid metal corrosion loop system and an oxygen control loop system. The accelerator mainframe is communicated with the test platform through an accelerator pipeline. The liquid metal corrosion loop system includes a liquid storage tank and an oxygen control tank. The oxygen control tank is communicated with the liquid inlet of the test platform through a first liquid delivery pipe. A permanent magnet pump, a flowmeter and a first liquid control valve are successively arranged on the first liquid delivery pipe. The oxygen control tank is communicated with the liquid outlet of the test platform through a second liquid delivery pipe. The liquid storage tank is communicated with the oxygen control tank through a third liquid delivery pipe. A second liquid control valve is arranged on the third liquid delivery pipe. The oxygen control loop system is communicated with the liquid storage tank and the oxygen control tank through air pipes respectively; The test platform includes a uniaxial tensile machine, a second computer and sensors. The sensors are arranged on the uniaxial tensile machine. The second computer is communicatively connected with the sensors and the uniaxial tensile machine. The accelerator mainframe is communicated with the proton inlet of the uniaxial tensile machine through an accelerator pipeline. The oxygen control tank is communicated with the liquid inlet of the uniaxial tensile machine through a first liquid delivery pipe. The oxygen control tank is communicated with the liquid outlet of the uniaxial tensile machine through a second liquid delivery pipe; A first liquid level probe and a first temperature probe are arranged in the oxygen control tank. A first pressure gauge is arranged on the outer wall of the oxygen control tank. A second liquid level probe and a second temperature probe are arranged in the liquid storage tank. A second pressure gauge is arranged on the outer wall of the liquid storage tank; The oxygen control loop system includes a first computer, a vacuum pump, a filter tank, an oxygen probe, a first high-pressure gas cylinder, a second high-pressure gas cylinder, a third high-pressure gas cylinder, a fourth high-pressure gas cylinder, and a flow controller. The liquid storage tank is communicated with the filter tank through a first air pipe. A first air control valve and a second air control valve are arranged on the first air pipe. The vacuum pump is arranged on the first air pipe and is located between the second air control valve and the filter tank. The oxygen control tank is communicated with the first air pipe through a second air pipe, and the connection point is located between the first air control valve and the second air control valve. A third air control valve is arranged on the second air pipe. The oxygen control tank is also directly connected to the filter tank through a third air pipe. A fourth air control valve is arranged on the third air pipe. The first high-pressure gas cylinder is communicated with the first air pipe through a fourth air pipe, and the connection point is located between the first air control valve and the second air control valve. A fifth air control valve is arranged on the fourth air pipe. The flow controller is communicated with the oxygen control tank through a fifth air pipe. A sixth air control valve is arranged on the fifth air pipe. The second high-pressure gas cylinder is communicated with the flow controller through a sixth air pipe. A seventh air control valve is arranged on the sixth air pipe. The third high-pressure gas cylinder is communicated with the flow controller through a seventh air pipe. An eighth air control valve is arranged on the seventh air pipe. The fourth high-pressure gas cylinder is communicated with the flow controller through an eighth air pipe. A ninth air control valve is arranged on the eighth air pipe. The oxygen probe is arranged in the oxygen control tank. An exhaust pipe is arranged on the filter tank. The first computer is communicatively connected with the oxygen probe and the flow controller.

2. The nuclear material performance testing device according to claim 1, characterized in that: Expansion joints are arranged on both the first liquid delivery pipe and the second liquid delivery pipe.

3. The nuclear material performance testing device according to claim 2, wherein: The outer sidewalls of the liquid storage tank, the oxygen control tank, the first infusion tube, the second infusion tube, and the third infusion tube are all provided with heat tracing and insulation layers.

4. A method for testing the performance of nuclear materials using the nuclear material performance testing device according to any one of claims 1 to 3, characterized in that: It includes the following steps: S1: Fix the first experimental sample and the second experimental sample on the corresponding workstations of the test section of the uniaxial tensile machine respectively; S2: Put the corrosive material into the liquid storage tank and seal it. Open the first pneumatic control valve, the second pneumatic control valve, and the third pneumatic control valve, and then turn on the vacuum pump to evacuate the liquid storage tank and the oxygen control tank. When the vacuum degrees of the liquid storage tank and the oxygen control tank are lower than 10 -4 Pa, close the first pneumatic control valve, the second pneumatic control valve, the third pneumatic control valve, and the vacuum pump; S3: Open the seventh pneumatic control valve, the sixth pneumatic control valve, the fifth pneumatic control valve, and the first pneumatic control valve respectively, and introduce the gas in the first high-pressure gas cylinder into the liquid storage tank, and introduce the gas in the second high-pressure gas cylinder into the oxygen control tank until the air pressures shown on the first pressure gauge and the second pressure gauge reach one standard atmospheric pressure, then close all the pneumatic control valves, thus completing the establishment of the protection atmosphere; S4: Heat the liquid storage tank, the oxygen control tank, the first infusion tube, the second infusion tube, and the third infusion tube through the heat tracing and insulation layers until the corrosive material in the liquid storage tank is completely liquefied, and maintain the heating temperature; S5: Open the fifth pneumatic control valve and the first pneumatic control valve, and introduce the gas in the first high-pressure gas cylinder into the liquid storage tank. When the air pressure in the liquid storage tank is greater than 2 standard atmospheric pressures, close the fifth pneumatic control valve and the first pneumatic control valve; S6: Open the third pneumatic control valve, the fourth pneumatic control valve, and the second liquid control valve, so that the liquid corrosive material in the liquid storage tank flows into the oxygen control tank under the action of the pressure difference. When the first liquid level probe monitors that the liquid level in the oxygen control tank reaches the set value, close the second liquid control valve, and then open the first pneumatic control valve. After the pressure in the liquid storage tank is the same as the atmospheric pressure, close the first pneumatic control valve; S7: Start the permanent magnet pump and the first liquid control valve, so that the liquid corrosive material flows from the oxygen control tank through the first infusion tube into the test section of the uniaxial tensile machine, and then flows back to the oxygen control tank through the second infusion tube, keeping the liquid corrosive material circulating, with the flow rate meeting 0.5 - 3 m / s. Then heat the oxygen control tank, the first infusion tube, and the second infusion tube to the temperature required for the experiment through the heat tracing and insulation layers; S8: Open the sixth pneumatic control valve, the eighth pneumatic control valve, and the ninth pneumatic control valve, and control the gas flow through the flow control valve, so that the gases in the third high-pressure gas cylinder and the fourth high-pressure gas cylinder flow into the oxygen control tank as needed, ensuring that the oxygen content of the liquid corrosive material in the oxygen control tank reaches the value required for the experiment; S9: After maintaining the flow rate and oxygen content of the liquid corrosive material stable, start the accelerator mainframe, so that the protons generated by the accelerator mainframe act on the first experimental sample and the second experimental sample. Then set the static load value required for the experiment and the size parameters of the sample through the second computer, and load the static load onto the tensile sample through the uniaxial tensile machine, where the tensile stress magnitude is set to the value required for the experiment. The sensor will transmit the static load value and the displacement value to the second computer, thus carrying out the coupling test according to the requirements; S10: After the coupling test is completed, first turn off the uniaxial tensile machine and the accelerator host, then turn off the ninth pneumatic control valve, the eighth pneumatic control valve, the sixth pneumatic control valve, the third pneumatic control valve and the fourth pneumatic control valve. Gradually reduce the loop temperature through the heat tracing and insulation layer, then turn off the permanent magnet pump, open the second hydraulic control valve, and the liquid corrosion material in the oxygen control box flows back into the liquid storage tank under the action of gravity. After the liquid corrosion material in the oxygen control box has finished flowing back, close the second hydraulic control valve, then turn on the permanent magnet pump to clean and flow back the remaining part of the liquid corrosion material in the pipeline into the oxygen control box, and turn off the permanent magnet pump. Finally, continue to reduce the loop temperature. When the temperature of the liquid metal corrosion loop system drops to room temperature, remove the first experimental sample and the second experimental sample respectively.

5. The nuclear material performance testing method according to claim 4, characterized in that: The heating maintenance temperature in step S4 is not lower than the melting point of the corrosive material medium; in step S8, the oxygen content of the liquid corrosive material is controlled to be 10 -8 -10 -4 wt%.

6. The nuclear material property testing method according to claim 4, characterized in that: In step S9, the parameters of the accelerator host, the proton energy and the proton beam current intensity, are set to the values required for the experiment.

7. The method for testing the performance of nuclear materials according to claim 4, characterized in that: The diameter of the first experimental sample is 3 - 10 mm, and the thickness is 50 - 500 μm; the length of the second experimental sample is 5 - 50 cm, the thickness is 50 μm - 1 mm, and the distance between the first experimental sample and the second experimental sample is 1 mm - 1 cm.

Citation Information

Patent Citations

  • High temperature water vapor oxidation experiment device capable of accurately controlling oxygen content

    CN104729979A

  • High-temperature water vapor oxidation experiment device with accurate oxygen content control function

    CN204495695U