CN110931140A - Device for measuring leakage rate of primary loop of water-cooled reactor and working method of device - Google Patents

Device for measuring leakage rate of primary loop of water-cooled reactor and working method of device Download PDF

Info

Publication number
CN110931140A
CN110931140A CN201911033067.4A CN201911033067A CN110931140A CN 110931140 A CN110931140 A CN 110931140A CN 201911033067 A CN201911033067 A CN 201911033067A CN 110931140 A CN110931140 A CN 110931140A
Authority
CN
China
Prior art keywords
gas
laser
cavity
water
spectrometer
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN201911033067.4A
Other languages
Chinese (zh)
Other versions
CN110931140B (en
Inventor
黄欣杰
万新峰
石松杰
郭晓彬
沈明明
柳彬
毕明德
刘舜
陈祥磊
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
719th Research Institute of CSIC
Original Assignee
719th Research Institute of CSIC
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by 719th Research Institute of CSIC filed Critical 719th Research Institute of CSIC
Priority to CN201911033067.4A priority Critical patent/CN110931140B/en
Publication of CN110931140A publication Critical patent/CN110931140A/en
Application granted granted Critical
Publication of CN110931140B publication Critical patent/CN110931140B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/002Detection of leaks
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N21/00Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
    • G01N21/01Arrangements or apparatus for facilitating the optical investigation
    • G01N21/03Cuvette constructions
    • G01N21/0303Optical path conditioning in cuvettes, e.g. windows; adapted optical elements or systems; path modifying or adjustment
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N21/00Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
    • G01N21/17Systems in which incident light is modified in accordance with the properties of the material investigated
    • G01N21/25Colour; Spectral properties, i.e. comparison of effect of material on the light at two or more different wavelengths or wavelength bands
    • G01N21/31Investigating relative effect of material at wavelengths characteristic of specific elements or molecules, e.g. atomic absorption spectrometry
    • G01N21/39Investigating relative effect of material at wavelengths characteristic of specific elements or molecules, e.g. atomic absorption spectrometry using tunable lasers
    • GPHYSICS
    • G01MEASURING; TESTING
    • G01NINVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
    • G01N21/00Investigating or analysing materials by the use of optical means, i.e. using sub-millimetre waves, infrared, visible or ultraviolet light
    • G01N21/17Systems in which incident light is modified in accordance with the properties of the material investigated
    • G01N21/25Colour; Spectral properties, i.e. comparison of effect of material on the light at two or more different wavelengths or wavelength bands
    • G01N21/31Investigating relative effect of material at wavelengths characteristic of specific elements or molecules, e.g. atomic absorption spectrometry
    • G01N21/39Investigating relative effect of material at wavelengths characteristic of specific elements or molecules, e.g. atomic absorption spectrometry using tunable lasers
    • G01N2021/391Intracavity sample
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • General Health & Medical Sciences (AREA)
  • Biochemistry (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • Analytical Chemistry (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Immunology (AREA)
  • Pathology (AREA)
  • Optics & Photonics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Investigating Or Analysing Materials By Optical Means (AREA)

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; by extracting the gas in the containment, the carbon in the high-temperature oxidation device existing in various forms is converted into CO2The 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 light11CO2Infrared absorption peak, absorptionThe peak area 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

Device for measuring leakage rate of primary loop of water-cooled reactor and working method of device
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 radiation signals into electric signals by monitoring the radioactivity of radioactive nuclides leaked from a primary circuit to a secondary circuit or a containment vessel, and finds out 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 the primary circuit leaks to the containment, 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 form. For gaseous radionuclides, the current measurement method is to filter the gas and place it in a measurement container, and use a radiation detector to detect the gas in the measurement container. 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 the loop are fission products and corrosion activation products, the concentration of the radionuclide in the loop is influenced by the integrity of cladding, the burning depth and the physical and chemical properties of coolant, the radionuclide has an accumulation effect, and unexpected fluctuation can occur, so that the radionuclide is 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 absorption spectroscopy is a method of quantitative analysis of the composition of matter using the selective absorption characteristics of matter for infrared electromagnetic radiation.
At present, a plurality of infrared spectrum absorption methods are used for measuring CO in air2Means for measuring the concentration of trace CO2However, 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 achieve 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 heat resistance; the structure 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-1111CO2
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) a continuous spectrum infrared laser;
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 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.
The invention also provides a working method of the device for measuring the leakage rate of the primary circuit of the water-cooled reactor, which is characterized in that the carbon existing in various forms in the containment vessel is converted into CO in the high-temperature oxidation device by absorbing the gas in the containment vessel2The 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 light11CO2Infrared 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 the primary loop of reactor11B(p,n)11C reaction, the service life is 20.36 min, the activity concentration of the C in a loop can be accurately calculated by the boron concentration in the loop and the recent power of the reactor, no unexpected fluctuation exists, and the typical activity concentration value in the pressurized water reactor loop is 103Bq•cm-3. Can solve the problems of accumulation effect of target nucleic in radioactive measurement method, unexpected fluctuation, and unsuitability for being used as a circuit leakageThe problem of quantitative measurement.
3. C-11 leaked into a containment and existing in various forms is oxidized into11CO2And 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 isotope mass differences11CO2Infrared spectrum absorption peak wave number less than12CO2By infrared absorption spectroscopy11CO2The 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 according to the present invention.
Wherein: 1. the device comprises an air inlet, a high-temperature oxidation device, a cooling device, a laser multi-reflection absorption device, a waste gas treatment device, a laser generator, a spectrometer, a laser, a combustion chamber, a flow gas chamber, a gas inlet, a gas outlet, a water cooling cavity, a gas flow chamber, a gas inlet, a gas outlet, a gas discharge port and a gas discharge port, wherein the high-temperature oxidation device comprises a gas inlet, a high-temperature oxidation device, a cooling device, a laser multi-reflection absorption device, a.
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-1111CO2
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-1Of (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 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:
high-temperature oxidation deviceThe carbon in the air in various forms is converted into CO2. 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 light to determine the laser light11CO2Activity 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 C-11 activity concentration in the loop in real time according to the state of the reactor, and measures the activity concentration according to the measured activity concentration11CO2And calculating whether the primary circuit leaks or not by using the activity concentration. According to measured11CO2And 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. The failure of the integrity of the primary loop pressure boundary will result in abnormal leakage of the primary loop 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 estimate for a set of devices as shown in fig. 1 is about 1.5 times that of the current loop leakage radiation monitoring device, but the former is much higher than the latter. The current calculations show that it is not possible to calculate,11CO2and12CO2has an infrared absorption peak wave number difference of 0.2 cm-1The wavelength difference is 0.5 nm, and the spectrometer can identify the wavelength difference. The absorption being in the general air content12CO2The background detects 5Bq/m3Is/are as follows11CO2Is greatly superior to the detection lower limit of current radiation measurement method for β radionuclide (about 3.7 multiplied by 10)3Bq/ m3). For general civil reactors, 5Bq/m3Is/are as follows11CO2The 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 above description is only exemplary of the invention and should not be taken as limiting the invention, as any modification, equivalent replacement, or improvement made without departing from the spirit and principle of the invention should fall within the protection 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-1111CO2
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) a continuous spectrum infrared laser;
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 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 of 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 device2The 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 injects laser into a light inlet and outlet small hole of the laser multi-reflection absorption deviceThe spectrometer receives and analyzes the emitted laser, and if C-11 exists in the air of the containment, the spectrometer can measure the emergent light11CO2Infrared 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.
CN201911033067.4A 2019-10-28 2019-10-28 Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof Active CN110931140B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201911033067.4A CN110931140B (en) 2019-10-28 2019-10-28 Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201911033067.4A CN110931140B (en) 2019-10-28 2019-10-28 Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof

Publications (2)

Publication Number Publication Date
CN110931140A true CN110931140A (en) 2020-03-27
CN110931140B CN110931140B (en) 2023-03-07

Family

ID=69849710

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201911033067.4A Active CN110931140B (en) 2019-10-28 2019-10-28 Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof

Country Status (1)

Country Link
CN (1) CN110931140B (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN116052912A (en) * 2023-04-03 2023-05-02 四川晟蔚智能科技有限公司 Nuclear leakage detection method and system based on aerosol transport analysis
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
CN117079848A (en) * 2023-10-17 2023-11-17 四川大学 Nuclear power plant primary loop optimal temperature measurement point selection method

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1308472A (en) * 1970-05-08 1973-02-21 Avco Corp Apparatus for and method of producing a population inversion in a flowing gaseous laser medium
EP0506579A1 (en) * 1991-03-29 1992-09-30 Commissariat A L'energie Atomique Process and device for incinerating graphite, in particular irradiated graphite-blocks
CN103928068A (en) * 2013-01-14 2014-07-16 上海核工程研究设计院 System and method for quantitatively measuring pressurized water reactor nuclear power plant circuit coolant leakage rate
CN109459396A (en) * 2018-12-04 2019-03-12 南京信息工程大学 The online laser acquisition analyzer of Atmospheric particulates carbon isotope and its application method
US20190101230A1 (en) * 2017-09-29 2019-04-04 Quest Engines, LLC Apparatus and methods for controlling the movement of matter
CN110349067A (en) * 2019-06-26 2019-10-18 中国船舶重工集团公司第七一九研究所 A kind of intelligent operational system and method for ocean nuclear power platform

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1308472A (en) * 1970-05-08 1973-02-21 Avco Corp Apparatus for and method of producing a population inversion in a flowing gaseous laser medium
EP0506579A1 (en) * 1991-03-29 1992-09-30 Commissariat A L'energie Atomique Process and device for incinerating graphite, in particular irradiated graphite-blocks
CN103928068A (en) * 2013-01-14 2014-07-16 上海核工程研究设计院 System and method for quantitatively measuring pressurized water reactor nuclear power plant circuit coolant leakage rate
US20190101230A1 (en) * 2017-09-29 2019-04-04 Quest Engines, LLC Apparatus and methods for controlling the movement of matter
CN109459396A (en) * 2018-12-04 2019-03-12 南京信息工程大学 The online laser acquisition analyzer of Atmospheric particulates carbon isotope and its application method
CN110349067A (en) * 2019-06-26 2019-10-18 中国船舶重工集团公司第七一九研究所 A kind of intelligent operational system and method for ocean nuclear power platform

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN116052912A (en) * 2023-04-03 2023-05-02 四川晟蔚智能科技有限公司 Nuclear leakage detection method and system based on aerosol transport analysis
CN116052912B (en) * 2023-04-03 2023-06-16 四川晟蔚智能科技有限公司 Nuclear leakage detection method and system based on aerosol transport analysis
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
CN117079848A (en) * 2023-10-17 2023-11-17 四川大学 Nuclear power plant primary loop optimal temperature measurement point selection method
CN117079848B (en) * 2023-10-17 2023-12-19 四川大学 Nuclear power plant primary loop optimal temperature measurement point selection method

Also Published As

Publication number Publication date
CN110931140B (en) 2023-03-07

Similar Documents

Publication Publication Date Title
CN110931140B (en) Device for measuring leakage rate of primary circuit of water-cooled reactor and working method thereof
CN201811870U (en) Self-starting type sampling and analyzing device for measuring concentration of hydrogen in containment
US9208907B2 (en) Method of validating nuclear reactor in-vessel detector output signals
KR101285479B1 (en) Steam generator tube on-line leak monitoring and methodology by using ion chromatography in pwr
CN207096165U (en) Mixed gas concentration on-line measurement device
JP2008096345A (en) System for and method of monitoring leakage in nuclear facility
JPH06300849A (en) Method for detecting leakage of radioactive gas of nuclear reactor and radioactivity monitor for nuclear reactor
Bonavigo et al. Issues for nuclear power plants steam generators
US4882122A (en) Method and apparatus for obtaining a water sample from the core of a boiling water reactor
RU2355055C1 (en) Method of controlling air-tightness of fuel element can of nuclear reactor
KR101519799B1 (en) Method and System for Detecting Trace Boron using Ultraviolet-Visible Spectrophotometer and Ion Chromatography for Steam Generator Tube Leakage On-line Monitoring
Alberman et al. Technique for power ramp tests in the ISABELLE 1 loop of the OSIRIS reactor
CN110689978B (en) Iodine steam generation and online detection recovery system for mandrel test
Gupta et al. Laser based technique for monitoring heavy water leaks in nuclear reactors: performance validation with conventional techniques
Wong et al. The role of leak-before-break in assessments of flaws detected in CANDU pressure tubes
Bae Study on Early Leak Detection of PCS Coolant Using Integrated System by means of Multi-Sensors Technique
RU2727072C1 (en) Method for detecting depressurization of process equipment at an early stage by reducing the value of the minimum detectable fluid activity of a radiometric unit (versions)
Aleksandrov et al. lnvestigation of β-Emission Methods of Monitoring Coolant Water Level in Nuclear Power Plants
Babu et al. Twenty years of experience in handling sodium in experimental sodium facilities
Park et al. A laser leak detector for leakage monitoring of fuel channel closure plugs in pressurized heavy water reactors
JPH02159599A (en) Determination of leakage source in nuclear reactor containment
Loubet et al. Development of a Gamma Radiotracer Method for the Analysis of Clogging in Steam Generators With COLENTEC Loop
Ha et al. Digital Radiation Monitoring System for High-functioning Auto Radionuclide Analysis
JP2023052158A (en) System of detecting uf6 gas leak in nuclear fuel manufacturing process
Horvath et al. Computer technics in corrosion product activation research for shut-down dose reduction at Paks NPP

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant