A research reactor test loop component damage monitoring system and method

Abstract

A research reactor test loop element damage monitoring system and method, relating to the field of irradiation technology for research reactors, includes a test heat exchanger, a first control valve, a delayed neutron monitor, a total gamma monitor, and an online nuclide monitor connected in sequence. The cooling inlet of the test heat exchanger is connected to the test loop, and the cooling outlet of the test heat exchanger is connected to the inlet of the delayed neutron monitor via the first control valve. The outlet of the delayed neutron monitor is connected to the inlet of the total gamma monitor. The outlet of the total gamma monitor is connected to the inlet of the online nuclide monitor. The outlet of the online nuclide monitor is connected to the regeneration inlet of the test heat exchanger via a first flow regulating valve. The regeneration outlet of the test heat exchanger is connected to the test loop. This system can accurately determine whether fuel elements have been damaged.

Description

Technical Field

[0001] This invention relates to the field of irradiation technology for research reactors, and in particular to a system and method for monitoring the damage of test loop components in research reactors. Background Technology

[0002] The research reactor test loop, also known as the irradiation test loop, is a fuel element performance verification platform. By precisely controlling the main parameters of the loop system, such as temperature, pressure, and flow rate, it simulates the real operating conditions of the fuel elements in the reactor and completes the performance verification of the fuel elements.

[0003] The test loop is mainly used for the release of heat from in-reactor components and the removal of residual heat from the system. However, during the operation of the loop, the fuel elements are subjected to extreme conditions such as high temperature and high pressure, which makes it impossible to absolutely guarantee the integrity of the fuel elements. If the fuel elements are damaged and not detected in time and corresponding countermeasures are not taken, a large amount of radioactive media will spread, causing contamination of the loop system, resulting in huge economic losses, and the operational safety of the reactor and the loop will also be affected.

[0004] Currently, among the research methods for detecting damage to reactor test loops, the most mature method is the heat transferr radiation separation method, which combines the slow-emission neutron method and the total gamma method. This method monitors the integrity of fuel elements by simultaneously monitoring slow-emission neutrons and total gamma rays in the primary loop water. The slow-emission neutron method measures the fission products of 235U, 238U, and 239U in the loop using a slow-emission neutron detector, which can directly monitor whether fuel elements are damaged. However, false alarms can occur due to the stability and sensitivity issues of the detector itself. The total gamma monitoring method monitors the total gamma rays in the loop using a total gamma monitor, which can indirectly reflect whether fuel elements are damaged. However, in addition to fuel element damage, loop equipment or pipelines also release small amounts of gamma rays due to long-term operation, which can also cause false alarms.

[0005] Therefore, a combination of the two is usually used to verify each other to improve system reliability. In order to match the delayed neutron monitor and thus further improve the system stability, the total gamma monitor is usually selected as a NaI scintillator detector, with an effective energy range below 800 keV.

[0006] However, during the design and actual operation of the test loop element damage monitoring system, the extremely short decay period of delayed neutrons (0.2s–54.5s) and the need to avoid interference from 16N and 19O present very demanding measurement conditions. This significantly increases the difficulty of designing the system's equipment and piping, as well as selecting measurement locations. Furthermore, because there are many key nuclides with energies below 800 keV that can interfere with each other, distinguishing each nuclide is extremely difficult. Therefore, this method is only suitable for detecting fuel element damage and monitoring total gamma levels; it does not have the capability to monitor the content of radioactive nuclides.

[0007] Therefore, we propose a component damage monitoring system that can accurately determine the results. Summary of the Invention

[0008] To overcome the shortcomings of the prior art, the present invention discloses a system and method for monitoring the damage of reactor test loop components.

[0009] To achieve the above-mentioned objectives, the present invention adopts the following technical solution:

[0010] A research reactor test loop component damage monitoring system includes a test heat exchanger, a first control valve, a delayed neutron monitor, a total gamma monitor, and an online nuclide monitor connected in sequence;

[0011] The cooling inlet of the breaking heat exchanger is connected to the test circuit, and the cooling outlet of the breaking heat exchanger is connected to the water inlet of the slow-emission neutron monitor through the first control valve.

[0012] The outlet of the delayed neutron monitor is connected to the inlet of the total gamma monitor.

[0013] The outlet of the total gamma monitor is connected to the inlet of the online radionuclide monitor;

[0014] The outlet of the online radionuclide monitor is connected to the regeneration inlet of the breaking heat exchanger via a first flow regulating valve;

[0015] The regeneration outlet of the test heat exchanger is connected to the test circuit.

[0016] Preferably, the heat exchanger used in the testing process is a regenerative heat exchanger, which includes a primary cooling circuit and a secondary cooling circuit. The cooling inlet of the primary cooling circuit is connected to the main water inlet of the testing circuit, and the cooling outlet of the primary cooling circuit is connected to the cooling inlet of the secondary cooling circuit. The regeneration inlet of the primary cooling circuit is connected to the outlet of the online radionuclide monitor, and the regeneration inlet of the primary cooling circuit is connected to the main water outlet of the testing circuit.

[0017] The cooling outlet of the secondary cooling circuit is connected to the first control valve, the regeneration inlet of the secondary cooling circuit is connected to the secondary water inlet of the test circuit through the second flow regulating valve, and the regeneration outlet of the secondary cooling circuit is connected to the secondary water outlet of the test circuit.

[0018] Preferably, the flow regulation range of the first flow regulating valve is 0m. 3 / h~1m 3 / h.

[0019] Preferably, the flow regulation range of the second flow regulating valve is 0m. 3 / h~4m 3 / h.

[0020] Preferably, a second control valve is connected in parallel to the total gamma monitor, and a third control valve is connected in parallel to the online nuclide monitor.

[0021] Preferably, the delayed neutron detector is a digital BF3 counter tube detector, and the energy range of the detector is thermal neutrons ~ 2 MeV.

[0022] Preferably, the total gamma monitor uses a NaI scintillator detector with an energy range of 100 keV to 800 keV and a measurement range of 3.7 × 10⁶ Bq / m². 3 ~3.7×10¹⁰ Bq / m 3 .

[0023] Preferably, the online nuclide monitor uses an HPGe detector with an energy range of 100 keV to 3 MeV and a measurement range of 3.7 × 10⁶ Bq / m³. 3 ~3.7×10¹² Bq / m 3 .

[0024] Preferably, the key nuclide selected by the online nuclide monitoring instrument is... 138 Cs、 92 Sr、 135 I, 89 Rb、 134 I, 142 La、 133 I, 138 Xe.

[0025] A method for monitoring the failure of reactor test loop components, comprising the following steps:

[0026] 1) Use a heat exchanger to cool the water in the test circuit;

[0027] 2) After cooling, the water is passed sequentially through a slow-emission neutron monitor, a total gamma monitor, and an online nuclide monitor to measure whether the water contains radioactive nuclides;

[0028] 3) The measured water is then returned to the test circuit via the breaking heat exchanger;

[0029] 4) Based on the measurement results of the delayed neutron monitor, the total gamma monitor, and the online nuclide monitor, the host computer determines whether the fuel element in the test circuit is damaged and decides whether to stop the operation of the test circuit.

[0030] By employing the technical solution described above, the present invention has the following beneficial effects:

[0031] The present invention discloses a research reactor test loop component damage monitoring system and method. By introducing an online nuclide monitor, it is possible to perform secondary measurements on the nuclides measured by the delayed neutron monitor and the total gamma monitor, thereby improving the accuracy of nuclide measurement and thus improving the reliability of the component damage monitoring system.

[0032] In addition, the heat exchanger can effectively reduce the temperature difference between the primary cooling circuit and the secondary cooling circuit, thereby reducing the thermal stress caused by excessive temperature difference.

[0033] In addition, the flow rate of the water in the main water path of the test loop can be adjusted by regulating the first flow rate, which reduces the difficulty of obtaining slow-emitted neutrons and makes it easier to select the installation location of the slow-emitted neutron monitor. Attached Figure Description

[0034] Figure 1 This is a schematic diagram of one structure of the present invention.

[0035] In the diagram: 1. Testing heat exchanger; 11. Primary cooling circuit; 12. Secondary cooling circuit; 2. First control valve; 3. Slow-emission neutron monitor; 4. Total gamma monitor; 5. Online nuclide monitor; 6. First flow regulating valve; 7. Second flow regulating valve; 8. Second control valve; 9. Third control valve; 10. Testing circuit; 101. Main water circuit; 102. Secondary water circuit. Detailed Implementation

[0036] The technical solution of the present invention will now be described with reference to the accompanying drawings of the embodiments of the present invention. In the description, it should be understood that the terms "upper," "lower," "front," "rear," "left," and "right," etc., indicating directions or positional relationships, are only used to correspond to the accompanying drawings of the present invention for the purpose of facilitating the description of the present invention, and are not intended to indicate or imply that the device or element referred to must have a specific orientation.

[0037] Example 1 is as follows:

[0038] Combined with appendix Figure 1 The aforementioned research reactor test loop component damage monitoring system includes a test heat exchanger 1, a first control valve 2, a delayed neutron monitor 3, a total gamma monitor 4, and an online nuclide monitor 5 connected in sequence.

[0039] The cooling inlet of the heat exchanger 1 is connected to the test circuit 10, and the cooling outlet of the heat exchanger 1 is connected to the inlet of the slow-emission neutron monitor 3 through the first control valve 2.

[0040] The cooling inlet of the heat exchanger 1 is connected to the test circuit 10 through the fourth control valve and the fifth control valve. The fourth and fifth control valves are used to turn the operation of this damage monitoring system on or off.

[0041] It should be noted that the first control valve 2 and the slow-emission neutron monitor 3 are also equipped with a flow meter and a thermometer to detect the water flow rate and water temperature flowing into the slow-emission neutron monitor 3;

[0042] In addition, the slow-emission neutron monitor 3 is used to measure whether there are slow-emission neutrons generated by fuel element fission products in the water of the test circuit 10. The detector uses paraffin as a neutron moderator and is equipped with a coil inside for measuring slow-emission neutrons in the water.

[0043] In addition, the distance between the inlet of the delayed neutron monitor 3 and the cooling outlet pipeline of the breaking heat exchanger 1 should be no less than 300m, so that the total time from the outlet of the test circuit 10 through the breaking heat exchanger 1 to the delayed neutron monitor 3 is about 50s, thus ensuring the monitoring accuracy of the delayed neutron monitor 3.

[0044] As required, the delayed neutron detector employs a digital BF3 counter tube detector, with an energy range of thermal neutrons up to 2 MeV, primarily used for detecting neutrons with relatively short half-lives of 0.2–55 s. 235 U、 238 U、 239 fission products of U 87 Br、 137 I, 88 The delayed neutrons of Br are monitored, and this type of delayed neutron monitor 3 has a good monitoring effect in the HFETR reactor;

[0045] The outlet of the slow-emission neutron monitor 3 is connected to the inlet of the total gamma monitor 4, which is used to measure whether the total gamma amount in the water of the test loop 10 exceeds the standard.

[0046] Furthermore, the total gamma monitor 4 employs a NaI scintillator detector with an energy range of 100 keV to 800 keV and a measurement range of 3.7 × 10⁻⁶. 6 Bq / m 3~3.7×10 10 Bq / m 3 , 87 Br、 137 I, 88 When the decay energy of nuclides such as B is within this energy range, the NaI scintillation device will also alarm when the delayed neutron detector alarms, which can improve the reliability of the system.

[0047] The outlet of the total gamma monitor 4 is connected to the inlet of the online nuclide monitor 5, which is used to measure whether the content of a specific radionuclide in the water of the test loop 10 exceeds the standard.

[0048] Furthermore, the online nuclide monitor 5 employs an HPGe detector with an energy range of 100 keV to 3 MeV and a measurement range of 3.7 × 10⁶ Bq / m³. 3 ~3.7×10¹² Bq / m 3 It is mainly used to measure fission products with relatively long half-lives, high decay energies, and high abundance in HFETR reactors, such as... 38 Cs、 92 Sr、 135 The content of I, etc., can be monitored by an online nuclide monitoring system to monitor the damage to the fuel element cladding when the delayed neutron detector fails to monitor due to the lack of a suitable installation location.

[0049] Furthermore, the key nuclides selected by the online nuclide monitor 5 are... 138 Cs、 92 Sr、 135 I, 89 Rb、 134 I, 142 La、 133 I, 138 Xe, the aforementioned nuclide, has a high content in the main water channel 101 of the test loop 10 of the HFETR reactor and can be used as a key characteristic nuclide for monitoring fuel cladding integrity.

[0050] The outlet of the online nuclide monitor 5 is connected to the regeneration inlet of the test heat exchanger 1 via the first flow regulating valve 6. Since the delayed neutron monitor 3 has very high requirements for environmental conditions, especially temperature sensitivity, excessively high water temperature may cause the paraffin material in the delayed neutron monitor 3 to melt, affecting the monitor's performance. Therefore, the water temperature before entering the delayed neutron monitor 3 needs to be controlled within a suitable range, typically below 40°C. Adjusting the water flow rate in the return test loop 10 indirectly controls the water temperature and flow rate entering the delayed neutron monitor 3, ensuring the monitor operates under optimal conditions and facilitating the identification of the optimal installation location for the delayed neutron monitor 3, thus reducing the design complexity of the equipment and pipelines.

[0051] In addition, the first flow regulating valve 6 is an electric regulating valve, which allows the above-mentioned water temperature regulating mechanism to dynamically adjust the flow rate as needed to adapt to the different monitoring requirements of the slow-emission neutron monitor 3 and improve the overall performance and reliability of the monitoring system.

[0052] It should be noted that the flow regulation range of the first flow regulating valve 6 is 0m. 3 / h~1m 3 / h.

[0053] The regeneration outlet of the test heat exchanger 1 is connected to the test circuit 10;

[0054] In one example, the test heat exchanger 1 is connected to the test circuit 10 in sequence via a thermometer, a sixth control valve, and a seventh control valve. The thermometer is used to detect the temperature of the water flow in this damage monitoring system and to determine whether the water temperature will affect the measurement results of the delayed neutron monitor 3. The sixth and seventh control valves are used to turn the operation of this damage monitoring system on or off.

[0055] When the fourth, fifth, sixth, and seventh control valves are all opened, the main water path 101 of the test loop 10 will be connected to the damage detection system to form a loop. The water in the main water path 101 will be cooled by the damage detection heat exchanger 1, and then pass through the delayed neutron monitor 3, the total gamma monitor 4, and the online nuclide monitor 5 in sequence to measure the nuclides in the water, thereby determining whether the fuel element in the test loop 10 has experienced radioactive nuclide leakage due to shell damage. Furthermore, the water in the main water path 101 is continuously flowing, thus achieving the purpose of damage detection.

[0056] Example 2 is as follows:

[0057] Based on Example 1, the heat exchanger 1 for breaking through the test circuit is further defined as follows: the heat exchanger 1 for breaking through the test circuit adopts a regenerative heat exchanger, and the heat exchanger includes a primary cooling circuit 11 and a secondary cooling circuit 12. The cooling inlet of the primary cooling circuit 11 is connected to the inlet of the main water channel 101 of the test circuit 10, and the cooling outlet of the primary cooling circuit 11 is connected to the cooling inlet of the secondary cooling circuit 12. The regeneration inlet of the primary cooling circuit 11 is connected to the outlet of the online radionuclide monitor 5, and the regeneration inlet of the primary cooling circuit 11 is connected to the outlet of the main water channel 101 of the test circuit 10.

[0058] The cooling outlet of the secondary cooling circuit 12 is connected to the first control valve 2, the regeneration inlet of the secondary cooling circuit 12 is connected to the inlet of the secondary water circuit 102 of the test circuit 10 through the second flow regulating valve 7, and the regeneration outlet of the secondary cooling circuit 12 is connected to the outlet of the secondary water circuit 102 of the test circuit 10.

[0059] The regenerative heat exchanger can effectively reduce the temperature difference between the primary cooling circuit 11 and the secondary cooling circuit 12, thereby reducing the thermal stress caused by the large temperature difference between the two cooling circuits and ensuring the safety and stability of the system.

[0060] It is important to note that the primary side outlet temperature of the regenerative heat exchanger is controlled below 40 degrees Celsius. This prevents the paraffin material in the slow-emission neutron monitor 3 from melting due to overheating, thereby further ensuring the accuracy and reliability of the monitoring system.

[0061] In addition, the primary cooling circuit 11 is connected to the main water circuit 101 and is responsible for cooling the high-temperature water in the main water circuit 101 to provide a suitable working environment for the subsequent delayed neutron monitor 3, total gamma monitor 4 and online nuclide monitor 5; while the secondary cooling circuit 12 is connected to the independent secondary water circuit 102 in the test circuit 10, which helps to maintain cooling efficiency and maintain system stability.

[0062] It should be noted that the flow regulation range of the second flow regulating valve 7 is 0m. 3 / h~4m 3 / h;

[0063] In addition, an eighth control valve and a thermometer are sequentially provided between the second flow regulating valve 7 and the secondary water circuit 102 of the test circuit 10, and a ninth control valve, a tenth control valve and a thermometer are sequentially provided between the regeneration outlet of the secondary cooling circuit 12 and the drain outlet of the secondary water circuit 102 of the test circuit 10.

[0064] The second flow regulating valve 7, the eighth control valve, the ninth control valve, and the tenth control valve work together to control the start or stop of the secondary cooling circuit 12 of the heat exchanger 1. The two thermometers in the secondary cooling circuit 12 can determine the cooling effect of the secondary cooling circuit 12 of the heat exchanger 1 by the difference in their readings, which makes it convenient to calculate the temperature difference between the secondary cooling circuit 12 and the primary cooling circuit 11.

[0065] Example 3 is as follows:

[0066] Based on Example 1, the control loops of the total gamma monitor 4 and the online nuclide monitor 5 are further defined, wherein the total gamma monitor 4 is connected in parallel with a second control valve 8, and the online nuclide monitor 5 is connected in parallel with a third control valve 9.

[0067] During the operation of this damage monitoring system, when the total gamma monitor 4 fails, the second control valve 8 can be opened to allow water to flow away through the second control valve 8, isolating and repairing the total gamma monitor and preventing overall system failure. When the linear nuclide monitor 5 fails, the third control valve 9 can be opened to isolate and repair the linear nuclide monitor 5, preventing overall system failure and further ensuring that this damage monitoring system can accurately measure nuclides in the water.

[0068] As a specific example: Based on Example 1, when the delayed neutron monitor 3 fails to monitor the delayed neutron due to the lack of a suitable installation location, if the total gamma monitor 4 alarms but the key nuclide in the nuclide online monitoring system does not show a significant increase and does not alarm, it is determined that the fuel element cladding is intact, and the gamma increment comes from the equipment or process pipeline, and the damaged element monitoring system does not alarm.

[0069] As another specific example: Based on Example 1, when the delayed neutron monitor 3 fails to monitor the delayed neutron due to the lack of a suitable installation location, if the total gamma monitor 4 alarms and the key nuclide in the online nuclide monitoring system shows a significant increase and alarms, it is determined that the fuel element cladding is damaged. The gamma increment comes from the fuel element. The maintenance personnel can judge the damage of the element and evaluate the consequences of the event based on the content of the key nuclide and take corresponding emergency measures.

[0070] A method for monitoring the failure of reactor test loop components, comprising the following steps:

[0071] 1) Use the heat exchanger 1 to cool the water in the test circuit 10 by heat exchange;

[0072] It should be noted that in the two cooling circuits of the test heat exchanger 1, the water in the main water channel 101 of the test circuit 10 is cooled by the primary cooling circuit 11, and the subsequent nuclide measurement is also for the water in the main water channel 101. The secondary cooling circuit 12, on the other hand, cools the independent secondary water channel 102 in the test circuit 10, thereby reducing the thermal stress caused by the large temperature difference between the two cooling circuits.

[0073] Specifically, the fourth, fifth, sixth and seventh control valves are opened to connect the test circuit 10 with the damage detection heat exchanger 1 to form a circuit, and the water in the test circuit 10 will flow in this damage monitoring system;

[0074] 2) After cooling, the water passes sequentially through a slow-emission neutron monitor 3, a total gamma monitor 4, and an online nuclide monitor 5 to measure whether the water contains radioactive nuclides;

[0075] 3) The measured water is then returned to the test circuit 10 via the test heat exchanger 1;

[0076] To enable continuous monitoring of the flowing water in test loop 10;

[0077] 4) Based on the measurement results of the delayed neutron monitor 3, the total gamma monitor 4 and the online nuclide monitor 5, the host computer determines whether the fuel element in the test circuit 10 is damaged and decides whether to stop the operation of the test circuit 10.

[0078] Furthermore, if either the delayed neutron monitor 3 or the total gamma monitor 4 malfunctions, the online nuclide monitor 5 can independently measure the presence of nuclides in the water, thereby determining whether the fuel element of the test loop is damaged. If only the online nuclide monitor 5 malfunctions, the combined operation of the delayed neutron monitor 3 and the total gamma monitor 4 can measure whether the water contains nuclides. 87 Br、 137 I or 88 Slow-released neutrons of Br nuclides, and 87 Br、 137 I or 88 The decay energy of nuclides such as Br, i.e. whether the water contains radioactivity, is used to determine whether the fuel element of test circuit 10 is damaged.

[0079] Since the delayed neutron monitor 3, the total gamma monitor 4, and the on-line nuclide monitor 5 operate online simultaneously, a failure in any of the two monitoring systems will not affect the continuous measurement of water in the test loop 10, thus ensuring the accuracy of this damage monitoring method.

[0080] The parts of this invention not described in detail are prior art. It will be apparent to those skilled in the art that this invention is not limited to the details of the above exemplary embodiments, and that the invention can be implemented in other specific forms without departing from the spirit or essential characteristics of the invention. Therefore, the embodiments should be regarded as exemplary and non-limiting in all respects. The scope of this invention is defined by the appended claims rather than the foregoing description. Therefore, it is intended to include all changes that fall within the meaning and scope of the equivalents of the claims within this invention, and no reference numerals in the claims should be regarded as limiting the scope of the claims.

Claims

1. A research reactor test loop component failure monitoring system characterized by: It comprises a broken probe heat exchanger (1), a first control valve (2), a delayed neutron monitor (3), a total gamma monitor (4) and an online nuclide monitor (5) connected in sequence. The broken probe heat exchanger (1) adopts a regenerative heat exchanger, and the heat exchanger comprises a primary side cooling circuit (11) and a secondary side cooling circuit (12), wherein the cooling inlet of the primary side cooling circuit (11) is in communication with the water inlet of the main water circuit (101) of the test circuit (10), and the cooling outlet of the primary side cooling circuit (11) is in communication with the cooling inlet of the secondary side cooling circuit (12); the cooling outlet of the secondary side cooling circuit (12) is connected with the water inlet of the delayed neutron monitor (3) through the first control valve (2). The water outlet of the delayed neutron monitor (3) is connected with the water inlet of the total gamma monitor (4). The water outlet of the total gamma monitor (4) is connected with the water inlet of the online nuclide monitor (5). The water outlet of the online nuclide monitor (5) is in communication with the regeneration inlet of the primary side cooling circuit (11) through the first flow regulating valve (6), and the regeneration outlet of the primary side cooling circuit (11) is in communication with the water outlet of the main water circuit (101) of the test circuit (10). The regeneration inlet of the secondary side cooling circuit (12) is in communication with the water inlet of the secondary water circuit (102) of the test circuit (10) through the second flow regulating valve (7), and the regeneration outlet of the secondary side cooling circuit (12) is in communication with the water outlet of the secondary water circuit (102) of the test circuit (10). Based on the research reactor test circuit element breakage monitoring system, a research reactor test circuit element breakage monitoring method is provided, and the specific steps are as follows: 1) The broken probe heat exchanger (1) is used to exchange heat and cool the water in the test circuit (10); 2) The cooled water passes through the delayed neutron monitor (3), the total gamma monitor (4) and the online nuclide monitor (5) in sequence to measure whether the water contains radioactive nuclides; 3) The measured water is returned to the test circuit (10) through the broken probe heat exchanger (1); 4) The upper computer judges whether the fuel element in the test circuit (10) is broken according to the measurement results of the delayed neutron monitor (3), the total gamma monitor (4) and the online nuclide monitor (5), and decides whether to stop the operation of the test circuit (10).

2. The research reactor test loop component failure monitoring system of claim 1 wherein: The flow regulating range of the first flow regulating valve (6) is 0 m 3 / h~1 m 3 / h.

3. The research reactor test loop component failure monitoring system as described in claim 1, wherein: the at least one sensor is a pressure sensor. The flow regulating range of the second flow regulating valve (7) is within 0 m 3 / h~4 m 3 / h.

4. The research reactor test loop component failure monitoring system as described in claim 1, wherein: the pressure sensor is a pressure transducer. The total gamma monitor (4) is connected in parallel with the second control valve (8), and the online nuclide monitor (5) is connected in parallel with the third control valve (9).

5. The research reactor test loop component failure monitoring system as described in claim 1, wherein: the pressure sensor is a pressure transducer. The delayed neutron monitor (3) adopts a digital BF3 counter tube detector, and the energy range of the detector is thermal neutron~2Mev.

6. The research reactor test loop component failure monitoring system as described in claim 1, wherein: the pressure sensor is a pressure transducer. The total gamma monitor (4) adopts NaI scintillator detector, the energy range of the detector is 100kev~800kev, the measurement range is 3.7×106Bq / m 3 ~3.7×1010 Bq / m 3 .

7. The research reactor test loop component failure monitoring system as described in claim 1, wherein: the pressure sensor is a pressure transducer. The online nuclide monitor (5) adopts an HPGe detector, which has an energy range of 100 keV-3 MeV and a measurement range of 3.7×106 Bq / m 3 ~3.7×1012 Bq / m 3 .

8. The research reactor test loop component failure monitoring system as described in claim 1, wherein: the pressure sensor is a pressure transducer. The online nuclide monitor (5), the selected key nuclide is 138 Cs, 92 Sr, 135 I, 89 Rb, 134 I, 142 La, 133 I or 138 Xe.

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