CN110931140B - Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof - Google Patents
Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof Download PDFInfo
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Abstract
The invention belongs to the technical field of radiation protection, and provides a device for measuring the leakage rate of a primary loop of a water-cooled reactor and a working method thereof, wherein the device comprises a high-temperature oxidation device, a cooling device, a laser generator, a laser multi-reflection absorption device, a spectrometer and a waste gas treatment device; carbon in various forms is converted into CO in a high-temperature oxidation device by absorbing gas in a containment vessel 2 The oxidized gas is cooled to normal temperature after being treated by a cooling device, and is filled into a laser multi-reflection absorption device after impurity removal, a laser generator emits laser into a light inlet and outlet small hole of the laser multi-reflection absorption device, a spectrometer receives and analyzes the emitted laser, and if C-11 exists in the air of the containment, the spectrometer can measure the emergent light of the emergent light 11 CO 2 Infrared absorption peak, the area of the absorption peak is in direct proportion to the concentration of C-11 in the air, and the gas is discharged into a waste gas treatment device after the measurement is finished. The invention has simple structure, convenient operation and high measurement efficiency.
Description
Technical Field
The invention belongs to the technical field of radiation protection, and particularly relates to a device for measuring the leakage rate of a primary loop of a water-cooled reactor and a working method thereof.
Background
At present, the monitoring of the leakage rate of a reactor primary circuit mainly comprises a non-radioactive measurement method and a radioactive measurement method.
The non-radioactive measurement method finds the leakage of the primary loop by monitoring the liquid level of the reactor voltage stabilizer, the lower measurement limit is 200L/h at present, and the leakage flowing to the secondary loop of the reactor and the containment cannot be distinguished.
The radioactive measurement method directly or indirectly converts a radiation signal into an electric signal by monitoring the radioactivity of the radioactive nuclide leaked from the primary circuit into the secondary circuit or the containment vessel, and finds the leakage of the primary circuit. The activity concentration of part of short-life water activation products in a loop can be accurately calculated in real time according to the power of a reactor, and the leakage rate of the loop can be quantified by measuring the radioactive nuclides. After leakage to the containment vessel occurs in the primary circuit, wherein the volatility of the radioactive nuclide is influenced by various factors, the volatile nuclide is partially diffused to the air in a gaseous state, and the non-volatile nuclide is diffused to the air in an aerosol state. For gaseous radionuclides, the current measurement method is to filter the gas and place it in a measurement container, and detect the gas in the measurement container using a radiation detector. For radioactive aerosol, the measurement method is to use a filter device to retain the aerosol and use a radiation detector to measure the radioactive aerosol on the filter paper. The radioactive measurement of gaseous substances is difficult to reach a low lower limit of measurement because the gaseous substances are difficult to separate and enrich. The measurement of the radioactive substance of the aerosol has a plurality of uncertain factors due to the complex process of nuclide aerosolization and aerosol transportation and a plurality of influencing factors. In addition, the radioactivity measurement is interfered by other radionuclides, and false alarm or the situation that a signal to be measured cannot be separated can occur.
In the prior art, a liquid level monitoring method of the voltage stabilizer cannot distinguish leakage flowing to a secondary loop and a containment vessel of a reactor, and the lower limit of a measuring threshold is higher.
The major drawbacks of the radioactive measurement include:
a. are susceptible to interference from other complex nuclides within the nuclear facility and are susceptible to false alarms or failure to isolate the target nuclide.
b. Most of radioactive nuclides in a loop are fission products and corrosion activation products, the concentration of the radioactive nuclides in the loop is influenced by the integrity of a cladding, the burning depth and the physical and chemical properties of a coolant, the radioactive nuclides have an accumulation effect, unexpected fluctuation can occur, and the radioactive nuclides are not suitable for quantitative measurement of loop leakage.
c. The measurement methods for gaseous and aerosol radioactive materials differ. The volatility of the radionuclide in the primary loop and the aerosolisation factors of the radionuclide when leakage occurs are influenced by various factors such as the physical and chemical properties of primary loop coolant, leakage positions, the size of a crevasse, the covering condition near the crevasse and the like, and the form of the radioactive substance in the containment after leakage is often difficult to determine, so that quantitative measurement is not facilitated.
Infrared spectroscopic absorption is a method of quantitatively analyzing the composition of a substance by utilizing the selective absorption characteristics of the substance to infrared electromagnetic radiation.
At present, a plurality of infrared spectrum absorption methods are used for measuring CO in air 2 Means for measuring the concentration of trace CO 2 However, no equipment related to the field of loop leakage rate monitoring is available.
Disclosure of Invention
The invention aims to solve the problems in the existing primary circuit leakage monitoring, and provides a device for measuring the primary circuit leakage rate of a water-cooled reactor and a working method thereof, which have the advantages of simple structure, convenience in operation and high measurement efficiency.
In order to realize the purpose, the invention adopts the following technical scheme: a device for measuring the leakage rate of a primary loop of a water-cooled reactor comprises a high-temperature oxidation device, a cooling device, a laser generator, a laser multi-reflection absorption device, a spectrometer and a waste gas treatment device;
the device sampling port is positioned in the containment vessel, gas in the containment vessel is sucked near a primary circuit pipeline, and the rest part of the device sampling port is positioned in the nuclear power plant equipment room;
the high-temperature oxidation device comprises a combustion chamber and a gas flow chamber, wherein the combustion chamber and the gas flow chamber are cylindrical, and the gas flow chamber is connected with a gas inlet and a gas outlet and has good heat conduction and resistance(ii) a thermal capacity; the structural principle of the combustion chamber is similar to that of a common industrial boiler, and the internal environment can be heated to more than 800 ℃; the sampled gas is heated to over 700 ℃ in the process of slowly flowing through the gas flowing chamber, and C-11 existing in various forms in the gas is oxidized into C-11 11 CO 2 ；
The cooling device comprises a water-cooling cavity and a gas flow chamber, the water-cooling cavity and the gas flow chamber are both cylindrical, the gas flow chamber is connected with a gas inlet and a gas outlet and has good heat conduction and heat resistance, and a liquid discharge port is arranged at the lower point of the gas flow chamber; cooling water with the temperature of 4 ℃ is left in the water cooling cavity; the sampled gas is cooled to below 20 ℃ in the process of slowly flowing through the gas flowing chamber, and most of water vapor in the gas is condensed and discharged;
the laser generator is used for generating a wave number of 2150-2550 cm -1 (ii) continuous spectrum infrared laser light;
the laser multi-reflection absorption device is internally provided with a reflection absorption cavity, the cavity is filled with gas treated by the condensation filtering device, the side surface of the cavity is provided with a reflective coating, two ends of the cavity are provided with two Herriott pool concave mirrors with high reflectivity, a small hole is formed in the middle shaft of one of the Herriott pool concave mirrors and can be used for emitting laser, the focuses of the two concave mirrors are positioned in the center of the cavity, the laser generated by the laser generator passes through the small hole after being emitted into the cavity and reflected for even times, the times can be determined by an incident angle, and the laser multi-reflection absorption device prolongs the optical path of the laser in target gas, so that an absorption peak is more obvious, and low-concentration target molecules are detected;
the spectrometer is used for analyzing the laser emitted from the laser multi-reflection absorption device and measuring an absorption peak;
and the waste gas treatment device is used for treating the measured gas.
The invention also provides a working method of the device for measuring the primary circuit leakage rate of the water-cooled reactor, which is characterized in that the gas in the containment vessel is absorbed, and carbon existing in various forms is converted into CO in a high-temperature oxidation device 2 The oxidized gas is cooled to normal temperature after being treated by a cooling device, and is filled into a laser multi-reflection absorption device after impurity removal, and a laser generator emits laser for multiple timesThe light inlet and outlet small holes of the reflection and absorption device inject laser, the spectrometer receives and analyzes the injected laser, and if C-11 exists in the air of the containment, the spectrometer can measure the emergent light 11 CO 2 Infrared absorption peak, the area of the absorption peak is in direct proportion to the concentration of C-11 in the air, and the gas is discharged into a waste gas treatment device after the measurement is finished.
Compared with the prior art, the invention has the following advantages:
1. the method has the advantages that the leakage rate of the primary loop leaked from the primary loop to the containment vessel is quantified by monitoring the concentration of the primary loop nuclide leaked into the containment vessel, and the problem that the leakage flowing to the secondary loop of the reactor and the containment vessel cannot be distinguished by a voltage stabilizer liquid level monitoring method is solved.
2. Selecting target nuclide as C-11, C-11 in a primary loop of a reactor 11 B(p,n) 11 C reaction, the service life is 20.36 min, the activity concentration of the boron in a loop can be accurately calculated from the boron concentration in the loop and the recent power of the reactor, no unexpected fluctuation exists, and the typical activity concentration value in a pressurized water reactor loop is 10 3 Bq•cm -3 . The method can solve the problems that target nucleic acid in a radioactive measurement method has an accumulation effect, can generate unexpected fluctuation and is not suitable for quantitative measurement of loop leakage.
3. C-11 leaked into a containment and existing in various forms is oxidized into 11 CO 2 And gas molecules solve the problems that the material form is difficult to determine after the radioactive material of the primary circuit leaks, and the quantitative leakage rate is not facilitated.
4. Using differences in isotope masses 11 CO 2 Infrared spectrum absorption peak wave number less than 12 CO 2 By infrared absorption spectroscopy 11 CO 2 The concentration of (2) solves the problems that a radioactive measurement method is easily interfered by other complex nuclides in nuclear facilities, and false alarm is easily caused or target nuclides cannot be separated.
Drawings
FIG. 1 is a schematic view of the apparatus of the present invention.
FIG. 2 is a schematic view of a high-temperature oxidation apparatus according to the present invention.
Fig. 3 is a schematic view of a cooling device of the present invention.
Wherein: 1. an air inlet, 2, a high-temperature oxidation device, 3, a cooling device, 4, a laser multi-reflection absorption device, 5, an exhaust gas treatment device, 6, a laser generator, 7, a spectrometer, 8, laser, 9, a combustion chamber, 10, a gas flowing chamber, 11, a gas inlet, 12, a gas outlet, 13, a water cooling cavity, 14, a gas flowing chamber, 15, a gas inlet, 16, a gas outlet and 17, and a liquid discharging port.
Detailed Description
The technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiment is only one embodiment, not all embodiments, of the present invention.
As shown in fig. 1, the present embodiment provides a device for measuring a primary circuit leakage rate of a water-cooled reactor, including a high temperature oxidation device 2, a cooling device 3, a laser generator 6, a laser multiple reflection absorption device 4, a spectrometer 7, and an exhaust gas treatment device 5, where a device sampling port is located in a containment, gas in the containment is sucked near a primary circuit pipeline, and the rest of the device is located in an equipment room.
As shown in fig. 2, the high-temperature oxidation apparatus 2 comprises a combustion chamber 9 and a gas flow chamber 10, wherein the combustion chamber 9 and the gas flow chamber 10 are both cylindrical, and the gas flow chamber 10 is connected with a gas inlet 11 and a gas outlet 12, so that the high-temperature oxidation apparatus has good heat conduction and heat resistance; the structure principle of the combustion chamber 9 is similar to that of a common industrial boiler, and the internal environment can be heated to more than 800 ℃; the sampled gas is heated to above 700 ℃ in the process of slowly flowing through the gas flowing chamber 10, and C-11 existing in various forms in the gas is oxidized into C-11 11 CO 2 。
The cooling device 3, as shown in fig. 3, comprises a water-cooling cavity 13 and a gas-flowing chamber 14, wherein the water-cooling cavity 13 and the gas-flowing chamber 14 are both cylindrical, the gas-flowing chamber 14 is connected with a gas inlet 15 and a gas outlet 16, and has good heat conduction and heat resistance, and a liquid discharge port 17 is arranged at the lower point of the gas-flowing chamber 14; cooling water with the temperature of 4 ℃ is left in the water cooling cavity 13; the sampled gas is cooled to below 20 ℃ in the process of slowly flowing through the gas flowing chamber 14, and most of water vapor in the gas is condensed and discharged.
The laser generator 6 is used for generating a wave number of 2150-2550 cm -1 Of (3) a continuous spectrum infrared laser.
The laser multi-reflection absorption device 4 is internally provided with a reflection absorption cavity, the cavity is filled with gas treated by the condensation filtering device, the side surface of the cavity is provided with a reflective coating, two ends of the cavity are provided with two Herriott pool concave mirrors with high reflectivity, a small hole is formed in the middle shaft of one of the Herriott pool concave mirrors and can be used for emitting laser, the focuses of the two concave mirrors are arranged in the center of the cavity, the laser generated by the laser generator passes through the small hole after being emitted into the small hole, the laser is emitted from the incident hole after passing through the cavity for even reflection times, the times can be determined by the incident angle, and the laser multi-reflection absorption device prolongs the optical path of the laser in target gas, so that the absorption peak is more obvious, and low-concentration target molecules can be detected.
And the spectrometer 7 is used for analyzing the laser emitted from the laser multi-reflection absorption device and measuring an absorption peak.
And the waste gas treatment device 5 is used for treating the measured gas.
The working method of the device of the embodiment is as follows:
the high-temperature oxidation device converts carbon existing in various forms in the air into CO 2 . And the oxidized gas is treated by a cooling device and then is filled into a laser multiple reflection absorption device. The laser generator injects laser into the light inlet and outlet small hole of the laser multi-reflection absorption device. The spectrometer receives and analyzes the emitted laser and determines the laser 11 CO 2 Activity concentration. After the measurement is finished, the gas is discharged into the waste gas treatment device for simple treatment and then discharged back into the containment.
The device can switch the air inlet direction from the containment sampling port to a high-pressure air source so as to flush the device contaminated by radioactive air. The matched software system calculates the concentration of C-11 activity in the loop in real time according to the state of the reactor, and the concentration is measured 11 CO 2 And calculating whether the primary circuit leaks or not by using the activity concentration. According to measured 11 CO 2 And calculating the leakage rate of the primary circuit according to the change rate of the activity concentration.
The reactor loop pressure boundary refers to a main coolant closed circulation loop with radioactivity, high temperature and high pressure, and comprises a reactor pressure vessel, a steam generator (primary side), a voltage stabilizer, a main circulation pump and other equipment, and pipe systems among the equipment. A breach in the integrity of the primary pressure boundary will result in an abnormal leakage of the primary coolant, directly affecting the normal operation of the reactor, and possibly causing health hazards to personnel in the vicinity of the nuclear facility. Therefore, monitoring of primary circuit pressure boundary leakage is an important measure for ensuring normal operation and safety of the reactor and guaranteeing the health and personal safety of the nuclear power plant personnel. At present, more and more reactors require a loop leakage monitoring device based on radiation measurement to be additionally arranged. The market price of a primary leakage monitoring device based on radiation measurement is about 1,000,000 yuan/station.
The hardware cost of a set of the equipment shown in figure 1 is estimated to be about 1.5 times that of the current loop leakage radiation monitoring equipment, but the former measurement precision is far higher than the latter. The current calculation shows that it is, 11 CO 2 and 12 CO 2 has an infrared absorption peak wave number difference of 0.2 cm -1 The wavelength difference is 0.5 nm, and the spectrometer can identify the wavelength difference. The absorption being in the general air content 12 CO 2 The background detects 5 Bq/m 3 Is 11 CO 2 Is greatly superior to the lower limit of detection of beta radionuclide by the current radiometric method (about 3.7 multiplied by 10) 3 Bq/ m 3 ). For general civil reactors, 5 Bq/m 3 Is 11 CO 2 The detection capability represents that 1L/h of return circuit leakage into the containment can be found within one hour, and is greatly superior to any existing return circuit detection means (about 200L/h). The great improvement of the measurement precision can ensure the accuracy of loop monitoring and the safety of nuclear facilities and workers.
All the functional components in the embodiment are common in the market and can be purchased conveniently in the market. Details not described in this specification are within the skill of the art that are well known to those skilled in the art.
The present invention is not intended to be limited to the particular embodiments shown and described, and various modifications, equivalents, improvements and the like which are within the spirit and scope of the invention are intended to be included within the scope of the invention.
Claims (3)
1. The utility model provides a device for measuring water-cooled reactor return circuit leakage rate which characterized in that: comprises a high-temperature oxidation device, a cooling device, a laser generator, a laser multi-reflection absorption device, a spectrometer and a waste gas treatment device;
the device sampling port is positioned in the containment vessel, gas in the containment vessel is sucked near a primary circuit pipeline, and the rest part of the device sampling port is positioned in the nuclear power plant equipment room;
the high-temperature oxidation device comprises a combustion chamber and a gas flow chamber, wherein the combustion chamber and the gas flow chamber are cylindrical, and the gas flow chamber is connected with a gas inlet and a gas outlet and has good heat conduction and heat resistance; the combustion chamber can heat the internal environment to above 800 ℃; the sampled gas is heated to over 700 ℃ in the process of slowly flowing through the gas flowing chamber, and C-11 existing in various forms in the gas is oxidized into C-11 11 CO 2 ；
The cooling device comprises a water-cooling cavity and a gas flow chamber, wherein the water-cooling cavity and the gas flow chamber are both cylindrical, the gas flow chamber is connected with a gas inlet and a gas outlet and has good heat conduction and heat resistance, and a liquid discharge port is arranged at the lower point of the gas flow chamber; cooling water with the temperature of 4 ℃ is left in the water cooling cavity; the sampled gas is cooled to below 20 ℃ in the process of slowly flowing through the gas flowing chamber, and most of water vapor in the gas is condensed and discharged;
the laser generator is used for generating a wave number of 2150-2550 cm -1 (ii) continuous spectrum infrared laser light;
the laser multi-reflection absorption device is internally provided with a reflection absorption cavity, the cavity is filled with gas treated by the condensation filtering device, the side surface of the cavity is provided with a reflective coating, two ends of the cavity are provided with two Herriott pool concave mirrors with high reflectivity, a small hole is formed in the middle shaft of one of the Herriott pool concave mirrors and can be used for emitting laser, the focuses of the two concave mirrors are positioned in the center of the cavity, the laser generated by the laser generator passes through the small hole after being emitted into the cavity and reflected for even times, the times can be determined by an incident angle, and the laser multi-reflection absorption device prolongs the optical path of the laser in target gas, so that an absorption peak is more obvious, and low-concentration target molecules are detected;
the spectrometer is used for analyzing the laser emitted from the laser multi-reflection absorption device and measuring an absorption peak;
and the waste gas treatment device is used for treating the gas after the measurement is finished.
2. The apparatus for measuring the primary circuit leakage rate of a water-cooled reactor as set forth in claim 1, wherein: the device can switch the air inlet direction from the containment sampling port to a high-pressure air source so as to flush the device contaminated by radioactive air.
3. A method of operating an apparatus for measuring a primary loop leakage rate of a water-cooled reactor as set forth in claim 1, wherein: extracting gas in a containment vessel, and converting carbon existing in various forms in the gas into CO in a high-temperature oxidation device 2 The oxidized gas is cooled to normal temperature after being treated by a cooling device, and is filled into a laser multi-reflection absorption device after impurity removal, a laser generator injects laser into a light inlet and outlet small hole of the laser multi-reflection absorption device, a spectrometer receives and analyzes the injected laser, and if C-11 exists in the air of the containment, the spectrometer can measure the emergent light 11 CO 2 Infrared absorption peak, the area of the absorption peak is in direct proportion to the concentration of C-11 in the air, and the gas is discharged into a waste gas treatment device after the measurement is finished.
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| CN116776039A (en) * | 2023-06-27 | 2023-09-19 | 阳江核电有限公司 | Method and device for evaluating containment breach leakage rate, storage medium and electronic equipment |
| CN117079848B (en) * | 2023-10-17 | 2023-12-19 | 四川大学 | Nuclear power plant primary loop optimal temperature measurement point selection method |
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