Steam electric heating pipeline device for nuclear reactor simulation test

By installing connecting electrodes and thermocouples on the steam flow pipeline, efficient heating and temperature control of steam were achieved, solving the problems of temperature loss and insufficient pressure during steam transmission and ensuring the effectiveness of the nuclear reactor simulation test.

CN223550444UActive Publication Date: 2025-11-14CHONGQING JINHONG ELECTRICAL ENG CO LTD
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Patent Information

Application Number
CN202422938431.4
Authority / Receiving Office
CN · China
Patent Type
Utility models(China)
Current Assignee / Owner
Filing Date
2024-11-29
Publication Date
2025-11-14
Estimated Expiration
2034-11-29

AI Technical Summary

Technical Problem

In the existing technology, steam is prone to temperature loss and insufficient pressure during pipeline transmission in nuclear reactor simulation tests, which affects the test results. In addition, the electric heating element is inconvenient to set up and hinders the steam flow.

Method used

Metal pipes are used with connecting electrodes at both ends. Steam is heated by passing electricity through the electrodes. Thermocouples are used to detect and automatically control the temperature to ensure that the steam temperature meets the standard, while avoiding obstruction of steam flow.

Benefits of technology

It achieves precise control of steam temperature, avoids steam pressure loss, ensures test results, and reduces the impact on the test.

✦ Generated by Eureka AI based on patent content.

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Abstract

The utility model discloses a steam electric heating pipeline device for a nuclear reactor simulation test, which comprises a steam circulation pipeline and is characterized in that the steam circulation pipeline is a metal pipe, a connecting electrode is fixedly arranged on the side surface of each of two ends of the metal pipe close to the end part, and a thermocouple device is further mounted at the outlet end of the metal pipe. According to the utility model, the steam can be heated before entering the nuclear reactor simulation test device, the temperature can be ensured to meet the test requirement, the influence on the test can be better reduced, and the test effect can be better ensured.
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Description

Technical Field

[0001] This utility model relates to the field of electric heating element technology, specifically to a steam electric heating pipeline device for nuclear reactor simulation experiments. Background Technology

[0002] With traditional resources facing gradual depletion, nuclear power generation is becoming increasingly promising. Nuclear power research, particularly in simulating nuclear reactor tests, requires the use of high-temperature steam to simulate the steam and power conversion system.

[0003] In existing technologies, water is typically heated into steam first, then the steam is heated to the required temperature before being piped to the testing apparatus for experimentation. However, this method is prone to temperature loss during steam transport, resulting in insufficient steam temperature and pressure reaching the testing apparatus, thus affecting the test results. Currently, a common solution is to install an electric heating element inside the steam pipe at the connection point with the testing apparatus to heat the steam and ensure the temperature meets the requirements. However, the electric heating element is inconvenient to install, and its presence can obstruct steam flow, leading to pressure loss, which also affects the test results.

[0004] Therefore, those skilled in the art need to consider designing a steam electric heating pipeline device for nuclear reactor simulation experiments that can better reduce the impact on the experiment and better ensure the experimental results. Utility Model Content

[0005] In view of the shortcomings of the prior art, the technical problem to be solved by this utility model is: how to provide a steam electric heating pipe device for nuclear reactor simulation test that can better reduce the impact on the test and better ensure the test effect.

[0006] To solve the above-mentioned technical problems, the present invention adopts the following technical solution:

[0007] A steam electric heating pipe device for nuclear reactor simulation test includes a steam flow pipe, characterized in that the steam flow pipe is a metal pipe, and a connecting electrode is fixedly installed on the side of each end of the metal pipe near the end, and a thermocouple device is also installed at the outlet end of the metal pipe.

[0008] In this way, the metal tube can be heated by energizing the connecting electrodes, and the steam passing through it can be directly heated by the metal tube. Thermocouple devices at the steam outlet of the steam flow pipe detect and ensure that the heating temperature reaches the required level before outputting the steam. This achieves both heating of the steam to ensure the required temperature for the test and avoids pressure loss due to obstruction of steam flow, thus minimizing the impact on the test and ensuring the test results. In specific implementation, the connecting electrodes are connected to the power supply via a current control device. The thermocouple is connected to the current control device and feeds back the temperature signal to the current controller to adjust the current magnitude, thereby adjusting the heat output of the metal tube and achieving the aforementioned automatic control of the steam temperature at the outlet.

[0009] Furthermore, the metal tube is a straight tube.

[0010] This ensures better heating performance.

[0011] Furthermore, the connecting electrode is made of metal material, and its overall shape is a rectangular plate with a connecting hole in the middle, which is welded and fixed to one side of the metal tube.

[0012] This facilitates the connection between the electrodes and the power supply line, and enables the conduction of a larger current.

[0013] Furthermore, a tee connector is also connected to the metal tube outlet, and a detection tube is connected to the side interface of the tee connector, on which the thermocouple device is installed.

[0014] This facilitates the installation of thermocouples and ensures that the thermocouples themselves do not obstruct the flow of steam or cause pressure loss, thus better reducing the impact on the test and guaranteeing the test results.

[0015] Furthermore, a threaded straight-through union is welded to each end of the metal tube.

[0016] This makes it easier to install and use the device itself.

[0017] In summary, this invention can heat steam before it enters the nuclear reactor simulation test device, ensuring that the temperature meets the test requirements, and can better reduce the impact on the test, thus better ensuring the test results. Attached Figure Description

[0018] Figure 1 This is a structural schematic diagram of a specific embodiment of the present utility model.

[0019] Figure 2 for Figure 1 AA sectional view. Detailed Implementation

[0020] The present invention will now be described in further detail with reference to the accompanying drawings.

[0021] In practical implementation: such as Figure 1 and Figure 2 As shown, a steam electric heating pipeline device for nuclear reactor simulation test includes a steam flow pipeline. The steam flow pipeline is a metal pipe 1, and a connecting electrode 2 is fixedly installed on the side of each end of the metal pipe 1 near the end. A thermocouple device 3 is also installed at the outlet end of the metal pipe.

[0022] In this way, the metal tube can be heated by energizing the connecting electrodes, and the steam passing through it can be directly heated by the metal tube. Thermocouple devices at the steam outlet of the steam flow pipe detect and ensure that the heating temperature reaches the required level before outputting the steam. This achieves both heating of the steam to ensure the required temperature for the test and avoids pressure loss due to obstruction of steam flow, thus minimizing the impact on the test and ensuring the test results. In specific implementation, the connecting electrodes are connected to the power supply via a current control device. The thermocouple is connected to the current control device and feeds back the temperature signal to the current controller to adjust the current magnitude, thereby adjusting the heat output of the metal tube and achieving the aforementioned automatic control of the steam temperature at the outlet.

[0023] The metal tube 1 is a straight tube.

[0024] This ensures better heating performance.

[0025] The connecting electrode 2 is made of metal and is a rectangular plate with a connecting hole 4 in the middle, which is welded and fixed to one side of the metal tube.

[0026] This facilitates the connection between the electrodes and the power supply line, and enables the conduction of a larger current.

[0027] A tee connector 5 is also connected to the metal tube outlet. A detection tube 6 is connected to the side interface of the tee connector 5, and the thermocouple device 3 is installed on the detection tube 6.

[0028] This facilitates the installation of thermocouples and ensures that the thermocouples themselves do not obstruct the flow of steam or cause pressure loss, thus better reducing the impact on the test and guaranteeing the test results.

[0029] Among them, a threaded straight-through union 7 is welded and fixed at each end of the metal pipe 1.

[0030] This makes it easier to install and use the device itself.

Claims

1. A steam electric heating pipeline device for nuclear reactor simulation experiments, comprising a steam flow pipeline, characterized in that, The steam flow pipe is a metal pipe, and a connecting electrode is fixedly installed on the side of each end of the metal pipe near the end. A thermocouple device is also installed at the outlet of the metal pipe.

2. The steam electric heating pipeline device for nuclear reactor simulation test according to claim 1, characterized in that: The metal tube is a straight tube.

3. The steam electric heating pipeline device for nuclear reactor simulation test according to claim 1, characterized in that: The connecting electrode is made of metal and is in the shape of a rectangular plate with a connecting hole in the middle, and is welded and fixed to one side of the metal tube.

4. The steam electric heating pipeline device for nuclear reactor simulation test according to claim 1, characterized in that: A tee connector is also connected to the metal tube outlet. A detection tube is connected to the side interface of the tee connector, and the thermocouple device is installed on the detection tube.

5. The steam electric heating pipeline device for nuclear reactor simulation test according to claim 1, characterized in that: Each end of the metal pipe is also welded with a threaded straight-through union.