CN108877972A - A kind of presurized water reactor primary Ioops boundary leaking monitoring method, system and monitor - Google Patents
A kind of presurized water reactor primary Ioops boundary leaking monitoring method, system and monitor Download PDFInfo
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- CN108877972A CN108877972A CN201810563211.4A CN201810563211A CN108877972A CN 108877972 A CN108877972 A CN 108877972A CN 201810563211 A CN201810563211 A CN 201810563211A CN 108877972 A CN108877972 A CN 108877972A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
- G21C17/07—Leak testing
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a kind of presurized water reactor primary Ioops boundary leaking monitoring method, system and monitors, the described method comprises the following steps：At sample point, gas sampled is obtained by sampling pipe；It calculates in the gas sampled13N and18The sampling concentration ratio of F；According to13N and18F leakage point initial concentration ratio and13N and18F is calculated in the sampling concentration ratio of sample point13N and18Diffusion time of the F from leakage point to sample point；The diffusion time is compared with preset time threshold, to obtain the leakage dot position information of presurized water reactor primary Ioops boundary leaking, is conducive to improve repair personnel's repairing speed, reduces the dose of radiation that repair personnel is subject to during repairing.
Description
Technical field
The present invention relates to nuclear power station radiation leakage monitoring field more particularly to a kind of monitorings of presurized water reactor primary Ioops boundary leaking
Method, system and monitor.
Background technique
Nuclear safety is the life of nuclear power, the autonomous nuclear power technology in research and development China, most important to be how to improve safety.
Although nuclear power still has a possibility that nuclear leakage due to being related to the discharge of radiation as a kind of clean energy resource.To ensure
Nuclear power steady development and the situation walked out, nuclear plant safety operation are related to nuclear power steady development and walk out with monitoring
One of key, one loop of nuclear power station pressure boundary leakage monitoring are the core components of nuclear plant safety monitoring.Because pressing water
Contain high-temperature high pressure water in reactor of nuclear power plant primary Ioops, this water had not only made coolant but also made neutron moderator.Due to nuclear fuel element
The neutron activation of corrosion product, makes to contain radionuclide in water in the leakage of involucrum and primary Ioops water.Pressurized-water reactor nuclear power plant one
The reator body in circuit and each welding position in pipeline at mechanical interface etc., are generated due to pressure, corrosion and irradiation etc.
Crackle and crack, especially pressure vessels top cover control rod drive mechanism are let out with the bad primary Ioops water that can generate of each valve seal
Leakage cannot such as find, crack is increasing in time, leak more and more.Capacity factor measure can not only be reduced and influence nuclear reactor
Normal operation, and nuclear pollution can be caused to environment.For these reasons, every country is all paid much attention to react nuclear power station
The leakage of heap primary Ioops pressure boundary is monitored.
For the monitoring of pressurized-water reactor nuclear power plant primary Ioops pressure boundary leakage, mainly pass through monitoring pressurized-water reactor nuclear power plant one
The radio nuclide source terms of high-temperature high pressure water in circuit are realized.The monitoring means used both at home and abroad at present mainly has：Containment
It is airborne in air in interior aerosol Total Beta Radioactivity measurement, containment131Inert gas in air in I radioactivity survey, containment
In radioactivity survey and containment in air13N (nitrogen 13) or18F (fluorine 18) radioactivity survey these four.
The measurement of aerosol Total Beta Radioactivity mainly monitors the Total Beta Radioactivity of aerosol in containment, aerosol in containment
Be mainly derived from the leakage and its gasification of reactor-loop pressure boundary coolant, by coolant fission product and corrosion
Activation products are formed；It is airborne in air in containment131The total β of aerosol is radiated in the radiometric measurement process of I and containment
Property measurement it is similar and measured in sampling, but it is airborne in air in containment131I radioactivity survey is made of active carbon
At " iodine filter cartridge ", replacement iodine filter cartridge manually operate；Noble gas activity measurement is logical in air in containment
It crosses monitoring inert gas Total Beta Radioactivity and carries out boundary leaking monitoring.
In containment in air13N or18F radioactivity survey, in air in containment13N radioactivity survey：Reactor core is split
Become proton in neutron and water and elastic scattering generation recoil proton occurs, is greater than the recoil proton of certain energy (E=5.555MeV)
In water16O occurs nuclear reaction and generates13N, i.e., 13N is β+Radionuclide, β+Half-life period is
9.96min。β+Positron annihilation effect occurs for particle and matter interaction, emits the light that two energy are 0.511Mev
Son, and two photons move round about.Pass through the gamma ray counting of 0.511Mev in measurement gas sampled, so that it may obtain
It samples in air13The radioactive activity of N converts, so that it may find out using the leakage transmission coefficient that dedicated calculation determines
(if air sampling here) or the water of primary Ioops pressure-bearing boundary (if the air sampling in containment) at pressure vessel upper top cover
Slip；For in air in containment18F radioactivity survey：18F is another activation products in one loop of nuclear power station water,
In reactor-loop water18F is generated by two nuclear reactions of subordinate：19F(n,2n)18F,18O(p,n)18F。18F is a kind of tool
There is β+The radgas of decay, half-life period 110min, it is easy to form gas in conjunction with micronic dust in air in air molten
Glue, only a small part18F exists also have β in gaseous form+Radionuclide.Due to18F is to be contained in reactor-loop
Another radionuclide in water largely exists in the form of aerosol micronic dust in containment, and18F is in primary Ioops water
In radioactive activity can accurately calculate, by measurement containment in18The available accuracy ratio of the micronic dust specific activity of F
The slip of higher primary Ioops pressure boundary.
In the implementation of the present invention, inventor has found：Due to aerosol,131I measurement and inert gas are core combustion
Expect the fission products of cladding leakage, their source item is anti-dependent on the damaged degree of cladding nuclear fuels and the core of nuclear fuel
Degree is answered, the exposure in high temperature and pressure radioactive water for a long time of the zircaloy fission product as fuel can, it may occur that certain
Corrosion failure, stress rupture of degree etc., to the defect of sand holes (i.e. small holes) or hair check property, cladding nuclear fuels occur
It is damaged estimate without standard measure, therefore by aerosol,131The measurement method of I measurement and inert gas be merely able to monitor whether
There is fission product leakage, but can not quantitatively calculate the leakage rate size of fission product, thus is only capable of observational measurement；In containment
In air13N or18F radioactivity survey there is source item can accurately calculate, phase since radio nuclide source terms are neutron activation products
For aerosol,131Three kinds of fission product (i.e. PIG) measurements of I measurement and inert gas, not only it is known that whether there is leakage feelings
Condition occurs, while leakage rate size can be accurately calculated according to source item, it can is used for quantitative measurment, but utilizes13N or18F
Radioactivity survey, although the slip information of quantitative in error range ± 20%, can be capable of, due to primary Ioops pressure
Bounds are wide, and existing detection technique can only get nuclear power station doubt road pressure boundary and leak, and the amount leaked is
How much, but other more information can not be obtained again, and the indefinite progress for being unfavorable for repairing work of information, serious possible danger
And personnel safety, nuclear pollution is caused to environment.
Summary of the invention
In view of the above-mentioned problems, the purpose of the present invention is to provide a kind of presurized water reactor primary Ioops boundary leaking monitoring method, being
System and monitor are conducive to improve repair personnel's repairing speed, reduce the dose of radiation that repair personnel is subject to during repairing.
In a first aspect, the embodiment of the invention provides a kind of presurized water reactor primary Ioops boundary leaking monitoring method, including it is following
Step：
At sample point, gas sampled is obtained by sampling pipe；
It calculates in the gas sampled13N and18The sampling concentration ratio of F；
According to13N and18F leakage point initial concentration ratio and13N and18Sampling concentration ratio of the F in sample point, meter
It calculates13N and18Diffusion time of the F from leakage point to sample point；
The diffusion time is compared with preset time threshold, to obtain the leakage of presurized water reactor primary Ioops boundary leaking
Dot position information.
It is described at sample point in the first implementation of first aspect, gas sampled is obtained by sampling pipe,
Specially：
In sample point, sample gas is pumped to outside containment by sampling pipe.
Further include in second of implementation of first aspect according to the first implementation of first aspect：
The sample gas is passed through13N detection device is detected, so that described13N detection device filters the sampling
The gamma-rays of 0.511Mev in gas, to measure and export the gamma-ray meter digit rate of the 0.511Mev；
The sample gas is passed through18F detection device is detected, so that described18F detection device filters the sampling
Aerosol in gas, to measure and export the aerosol counting rate.
According to second of implementation of first aspect, in the third implementation of first aspect, the calculating institute
It states in gas sampled13N and18The sampling concentration ratio of F, specially：
According to the gamma-ray meter digit rate of the 0.511Mev of output, calculate in the gas sampled13The beta activity of N is living
Degree；
According to the aerosol counting rate of output, calculate in the gas sampled18The beta activity activity of F；Wherein, if β
Radioactive activity is A,13The beta activity activity of N and18The calculating process of the beta activity activity of F is：A=(n-nb)/ε, in formula, ε
For detection efficient, nbFor background counting rate, n is counting rate when measuring sample, works as calculating13When the beta activity activity of N, n is institute
The gamma-ray meter digit rate for stating 0.511Mev, works as calculating18When the beta activity activity of F, n is the aerosol counting rate；
According to described13The beta activity activity of N and described18The beta activity activity of F, calculates in the gas sampled13N and18The sampling concentration ratio of F；Wherein, if13The beta activity activity of N is AtN,18The beta activity activity of F is AtNIf the sampling
Concentration ratio is C2, then
According to the third implementation of first aspect, in the 4th kind of implementation of first aspect, the basis13N
With18F leakage point initial concentration ratio and13N and18F is calculated in the sampling concentration ratio of sample point13N and18F is from leakage point
To the diffusion time of sample point, specially：
It obtains13N and18Initial concentration ratio of the F in leakage point；Wherein, if13The initial beta activity activity of N is A0N,18F
Initial beta activity activity be A0FIf the initial concentration ratio is C1, then
According to13N and18F leakage point initial concentration ratio and13N and18Sampling concentration ratio of the F in sample point, meter
It calculates13N and18Diffusion time of the F from leakage point to sample point；Wherein, core decaying rule A (t)=A0*e-λt, decay coefficientT1/2For half-life period,13The half-life period of N is 9.97min,18The half-life period of F is 110min, is located at t moment,13N and18F
It is in the sampling concentration ratio of sample point：ThenIn formula, λNFor13The decay of N
Constant, λFFor18The decay coefficient of F.
It is described pre- in the 5th kind of implementation of first aspect according to any of the above implementation of first aspect
If the acquisition of time threshold includes the following steps：
Containment is established with the Collaborative Simulation Environment (workbench) in ANSYS (large-scale general finite element analysis software)
Threedimensional model；
In fluent software, it is k- ε model that DIFFUSION IN TURBULENCE model is chosen on the basis of the containment threedimensional model,
And conditions setting, to generate presurized water reactor primary Ioops boundary leaking simulation model；Wherein, the boundary condition includes leakage face
Boundary condition, ventilating surface boundary condition；
On the presurized water reactor primary Ioops boundary leaking simulation model, simulation is calculated in nuclear leakage gas13N and18F is from each
Time needed for a leakage point is diffused into sampled point, with obtain each leakage point to sampled point corresponding each preset time threshold
Value.
Second aspect, the embodiment of the invention provides a kind of presurized water reactor primary Ioops boundary leakings to monitor system, including sampling
Unit and measurement processing unit；
The sampling unit is connect with the measurement processing unit, for being taken at sample point by sampling pipe
Sample gas；
The measurement processing unit, for calculating in the gas sampled13N and18The sampling concentration ratio of F；
The measurement processing unit, is also used to basis13N and18F leakage point initial concentration ratio and13N and18F is taking
The sampling concentration ratio of sampling point calculates13N and18Diffusion time of the F from leakage point to sample point；
The measurement processing unit is also used to for being compared with preset time threshold the diffusion time, to obtain pressure
The leakage dot position information of water-water reactor primary Ioops boundary leaking.
It further include probe unit in the first implementation of second aspect；
The probe unit is separately connected the sampling unit and the measurement processing unit, is used for the sampling gas
Body passes through13N detection device is detected, so that described13N detection device filters the γ of the 0.511Mev in the gas sampled
Ray, to measure and export the gamma-ray meter digit rate of the 0.511Mev；
And the sample gas is passed through18F detection device is detected, so that described18Described in the filtering of F detection device
Aerosol in gas sampled, to measure and export the aerosol counting rate.
It further include display in second of implementation of second aspect according to the first implementation of second aspect
Unit and electric control unit；
The display unit is connect with the measurement processing unit, the pressure for being obtained according to the measurement processing unit
The leakage dot position information of water-water reactor primary Ioops boundary leaking accordingly shows leakage point；
The electric control unit is used to be the measurement respectively with the measurement processing unit and the display unit
Processing unit and the display unit provide voltage output.
The third aspect, the embodiment of the invention provides a kind of monitors, including pressure described in any one of second aspect
Water-water reactor primary Ioops boundary leaking monitors system.
The embodiment of the invention provides a kind of presurized water reactor primary Ioops boundary leaking monitoring method, system and monitor, one
A embodiment has the advantages that：
First at sample point, gas sampled is obtained by sampling pipe, is then calculated in the gas sampled13N and18F
Sampling concentration ratio, further according to13N and18F leakage point initial concentration ratio and13N and18Sampling concentration of the F in sample point
Ratio calculates13N and18Diffusion time of the F from leakage point to sample point, finally by the diffusion time and preset time threshold into
Row compares, and to obtain the leakage dot position information of presurized water reactor primary Ioops boundary leaking, passes through13N and18The combined measurement of F obtains
The leakage point information of PWR of Nuclear Power Station primary Ioops boundary leaking solves existing one loop of nuclear power station pressure boundary leakage monitoring instrument
Device cannot provide the problem of leakage point information, provide leakage dot position information for repair personnel, provide convenience for repair personnel, have
Conducive to first-aid repair efficiency is improved, the dose of radiation that repair personnel is subject to during repairing, while the emergency repair time shortened are reduced
Reduce nuclear leakage, is conducive to guarantee environment safety.
Detailed description of the invention
In order to illustrate more clearly of technical solution of the present invention, attached drawing needed in embodiment will be made below
Simply introduce, it should be apparent that, the accompanying drawings in the following description is only some embodiments of the present invention, general for this field
For logical technical staff, without creative efforts, it is also possible to obtain other drawings based on these drawings.
Fig. 1 is the flow diagram for the presurized water reactor primary Ioops boundary leaking monitoring method that first embodiment of the invention provides.
Fig. 2 is the schematic diagram of leakage point setting and sampling that first embodiment of the invention provides.
Fig. 3 is the structural schematic diagram for the presurized water reactor primary Ioops boundary leaking monitoring system that second embodiment of the invention provides.
Specific embodiment
Following will be combined with the drawings in the embodiments of the present invention, and technical solution in the embodiment of the present invention carries out clear, complete
Site preparation description, it is clear that described embodiments are only a part of the embodiments of the present invention, instead of all the embodiments.It is based on
Embodiment in the present invention, it is obtained by those of ordinary skill in the art without making creative efforts every other
Embodiment shall fall within the protection scope of the present invention.
Referring to Fig. 1, first embodiment of the invention provides a kind of presurized water reactor primary Ioops boundary leaking monitoring method, it is described
Presurized water reactor primary Ioops boundary leaking monitoring method is integrated in presurized water reactor primary Ioops boundary leaking monitoring system, and including following step
Suddenly：
S11 obtains gas sampled by sampling pipe at sample point.
In embodiments of the present invention, sampling unit passes through sampling pipe in sample point first sample gas is pumped to safety
Outside shell, after sample point gets sample gas, the sample gas is transferred to probe unit, in the probe unit,
The sample gas is passed through13N detection device is detected, so that described13N detection device filters in the gas sampled
The gamma-rays of 0.511Mev, to measure and export the gamma-ray meter digit rate of the 0.511Mev；The sample gas is passed through again18F detection device is detected, so that described18F detection device filters the aerosol in the gas sampled, to measure and export
The aerosol counting rate, the probe unit are defeated by the gamma-ray meter digit rate of the 0.511Mev and the aerosol counting rate
Out into measurement processing unit, operated so as to subsequent.
S12 is calculated in the gas sampled13N and18The sampling concentration ratio of F.
In embodiments of the present invention, in the measurement processing unit, first according to the γ of the 0.511Mev of output
Ray counting rate, calculates the beta activity activity of 13N in the gas sampled, while according to the aerosol counting rate of output,
The beta activity activity for calculating 18F in the gas sampled, when carrying out nucleic activity measurement, key technology is to sample
Efficiency calibration, efficiency calibration method conventional at present is active efficiency curve method, that is, uses the nucleic standard source of known activity
Efficiency calibration is carried out to detector, detector is obtained to full-energy peak efficiency (EI) curve of this sample, passes through measurement and standard source
The sample that shape, material component are consistent with density obtains the radioactive activity of sample Radionuclide in turn, if beta activity activity is A,
The calculating process of the beta activity activity of the beta activity activity and 18F of 13N is：A=(n-nb)/ε, in formula, ε is detection efficient, nb
For background counting rate, n is counting rate when measuring sample, and when calculating the beta activity activity of 13N, n is the 0.511Mev's
Gamma-ray meter digit rate, when calculating the beta activity activity of 18F, n is the aerosol counting rate, is put further according to the β of the 13N
The beta activity activity of penetrating property activity and the 18F calculates the sampling concentration ratio of 13N and 18F in the gas sampled, if 13N
Beta activity activity be AtN, the beta activity activity of 18F is AtNIf the sampling concentration ratio is C2, then13N
And 18F is the activation products in one loop of nuclear power station water, all has β+decay characteristic, the two half-life period is different, respectively
9.97min, 110min can be used as the tracer of one loop of nuclear power station pressure boundary leakage monitoring, due to the difference of half-life period
It is different, thus after arrival sample point, 13N with 18F concentration ratio, which compares leakage point concentration ratio, to be changed.
S13, according to13N and18F leakage point initial concentration ratio and13N and18F sample point sampling concentration ratio,
It calculates13N and18Diffusion time of the F from leakage point to sample point.
In embodiments of the present invention, it in the measurement processing unit, obtains13N and18Initial concentration ratio of the F in leakage point
Example,13N and18There is F source item can accurately calculate, therefore13N and18Initial concentration ratio existing for two kinds of forms of F is in leakage point
Fixed, if13The initial beta activity activity of N is A0N,18The initial beta activity activity of F is A0FIf the initial concentration ratio
For C1, thenContainment primary Ioops pressure boundary is divided into several easy leakage regions, when different zones reach sample point
Between it is variant, it will have different concentration ratios, then basis13N and18F leakage point initial concentration ratio and13N and18F exists
The sampling concentration ratio of sample point calculates13N and18Diffusion time of the F from leakage point to sample point, core decaying rule A (t)=A0*
e-λt, decay coefficientT1/2For half-life period,13The half-life period of N is 9.97min,18The half-life period of F is 110min, is located at t
Moment,13N and18F is in the sampling concentration ratio of sample point：ThenIn formula, λN
For13The decay coefficient of N, λFFor18The decay coefficient of F.
The diffusion time is compared S14 with preset time threshold, to obtain presurized water reactor primary Ioops boundary leaking
Leak dot position information.
In embodiments of the present invention, the acquisition of the preset time threshold includes the following steps：It is (large-scale with ANSYS first
General finite element analysis software) in Collaborative Simulation Environment (workbench) establish containment threedimensional model, ANSYS company head
Mature CAE product is provided since the phase for user, determines the CAE product of oneself to break to form component now, company not only mentions
For integration, mature software, and the component (API) of software is provided, user can incite somebody to action according to this enterprise product processes of research & development
These technologies broken reconfigure, and form the analysis demand that can either sufficiently meet itself, and sufficiently incorporate research and development of products stream
The emulation system of journey, Workbench are then exclusively for the dedicated platform for reconfiguring these components and designing, it provides one
The basic framework of load and Administration API, in this frame, each component (API) passes through Jscript, VBscript and html script
Linguistic organization, and use interface (GUI) for being suitble to oneself is worked out, in addition, third party CAE technology and user produce with independent intellectual
The technology of power can also be compiled into API as the technology of ANSYS and dissolve in this program.Then in fluent software,
DIFFUSION IN TURBULENCE model is chosen on the basis of the containment threedimensional model as k- ε model, and conditions setting, to generate pressure water
Heap primary Ioops boundary leaking simulation model；Wherein, the boundary condition includes the perimeter strip of the boundary condition in leakage face, ventilating surface
Part, standard k-ε model is applied widely, has economically and reasonably precision, and model hypothesis flowing is complete turbulent flow, and molecule is viscous
Property influence can ignore, this standard model be only suitable for complete turbulent flow flow process simulation, finally in the presurized water reactor one
On the boundary leaking simulation model of circuit, simulation is calculated in nuclear leakage gas13N and18F is diffused into sampled point institute from each leakage point
Need time, with obtain each leakage point to sampled point corresponding each preset time threshold.
In embodiments of the present invention, it should be noted that air containment is about in domestic common nuclear power plant containment shell
70000m3, nuclear power plant containment shell circulation cold air unit flow is 80000m3/ h, even if cold wind unit is operated using rated power,
The easy leakage point gas in lower section is also required to be transmitted to the top at least one hour, presurized water reactor primary Ioops boundary leaking simulation process with
Easy leakage point is divided into for 3 to 5 regions and is illustrated, it should be noted that the present invention divides easy leakage point
Region quantity does not do any restrictions, sample point is placed on most easy leakage point, other leakage point gas diffusions to sample point time
Difference may need a hour according to longest is estimated, most short to be also required to more than ten minutes, according to simulated implementation as a result, pressure water
Heap primary Ioops boundary leaking needs 20 minutes to 60 minutes or so time from leakage point to sample point.
In embodiments of the present invention, it in the measurement processing unit, by the diffusion time being calculated and presets
Time threshold is compared, and the preset time threshold characterizes each leakage point to the time of the sampled point, passes through the expansion
Dissipate time and preset time threshold comparison, the available diffusion time within the scope of which preset time threshold, thus
The leakage dot position information of available presurized water reactor primary Ioops boundary leaking.
In embodiments of the present invention, referring to Fig. 2,5 leakage point regions are arranged during simulation and realization, this is utilized
The presurized water reactor primary Ioops boundary leaking monitoring method of application solves the problems, such as that monitor can not provide leakage point information.Because13N,18F is the activation products in one loop of nuclear power station water, all has β+Decay characteristic, the two half-life period is different, respectively
9.97min, 110min can be used as the tracer of one loop of nuclear power station pressure boundary leakage monitoring, simultaneously13N,18F has
Source item can be calculated accurately, i.e.,13N and18Initial concentration ratio existing for two kinds of forms of F in leakage point be it is fixed, due to from letting out
Leak source needs the time of 20min to 60min or so to sample point, due to the difference of half-life period, thus after arrival sample point,13N
With18F concentration ratio can change compared to leakage point concentration ratio, and containment primary Ioops pressure boundary is divided into 5 Ge Yi leakage point areas
Domain, it is variant that different leakage points reach the sample point time, it will has different concentration ratios, is calculated according to different concentration ratios
Corresponding diffusion time out, as described in Figure 2, sample point is placed on and is easiest to leak by No. 1-5 place for several easy leakages
The position of region 1, No. 2-5 each leakage point zone gas is different because the factors such as distance reach No. 1 position time, when presurized water reactor one
When circuit boundary leaks, the gas of each leakage point is calculated by the presurized water reactor primary Ioops boundary leaking monitoring method of the application
Body reaches leakage point 1 diffusion time；On the presurized water reactor primary Ioops boundary leaking simulation model, simulation calculate gas from
No. 2-5 each leakage point be diffused into sample point 1 corresponding to each preset time threshold；By the diffusion time with it is described pre-
If time threshold is compared, leakage dot position information can be obtained, in embodiments of the present invention, passes through theoretical modeling and experiment
Verifying combines, i.e., using China Atomic Energy Science Research Institute's swimming pool light water reactor as research object, theoretical modeling is specified
In moment space13N/18F concentration distribution cloud atlas and designated place13N/18F concentration changes with time relationship, with experimental measurements into
Row compares, re-optimization theoretical modeling, to obtain can be used for the theoretical modeling mould that radiative source term is distributed in nuclear power plant containment shell
Type, i.e., the described presurized water reactor primary Ioops boundary leaking simulation model.13N and18F sample point concentration ratio, in actual measurement mistake
Cheng Zhong can measure unknown concentration using relative manner as long as carrying out efficiency calibration first with known activity source；In theory
In simulation process, it can be simulated using Fluid Mechanics Computation (CFD) method, carry out mould with cfdrc FLUENT
Quasi- gas Release and dispersion rule, finally obtains concentration distribution result in containment.
In conclusion first embodiment of the invention provides a kind of presurized water reactor primary Ioops boundary leaking monitoring method, first
At sample point, gas sampled is obtained by sampling pipe, is then calculated in the gas sampled13N and18The sampling concentration ratio of F
Example, further according to13N and18F leakage point initial concentration ratio and13N and18F is calculated in the sampling concentration ratio of sample point13N
With18Diffusion time of the F from leakage point to sample point finally the diffusion time is compared with preset time threshold, to obtain
The leakage dot position information of pressure water-water reactor primary Ioops boundary leaking, passes through13N and18The combined measurement of F obtains PWR of Nuclear Power Station
The leakage point information of primary Ioops boundary leaking solves existing one loop of nuclear power station pressure boundary leakage monitoring instrument and cannot provide to let out
The problem of leak source information, provides leakage dot position information for repair personnel, provides convenience for repair personnel, is conducive to improve repairing
Efficiency reduces the dose of radiation that repair personnel is subject to during repairing, while the emergency repair time shortened decreases nuclear leakage,
Be conducive to guarantee environment safety.
Referring to Fig. 2, second embodiment of the invention provides a kind of presurized water reactor primary Ioops boundary leaking monitoring system, including
Sampling unit 11 and measurement processing unit 12.
The sampling unit 11 is connect with the measurement processing unit 12, for being obtained at sample point by sampling pipe
Take gas sampled.
The measurement processing unit 12, for calculating in the gas sampled13N and18The sampling concentration ratio of F.
The measurement processing unit 12, is also used to basis13N and18F leakage point initial concentration ratio and13N and18F exists
The sampling concentration ratio of sample point calculates13N and18Diffusion time of the F from leakage point to sample point.
The measurement processing unit 12 is also used to for being compared with preset time threshold the diffusion time, to obtain
The leakage dot position information of presurized water reactor primary Ioops boundary leaking.
It further include probe unit 13 in the first implementation of second embodiment；
The probe unit 13 is separately connected the sampling unit 11 and the measurement processing unit 12, and being used for will be described
Sample gas passes through13N detection device is detected, so that described13N detection device filters in the gas sampled
The gamma-rays of 0.511Mev, to measure and export the gamma-ray meter digit rate of the 0.511Mev；And the sample gas is led to
It crosses18F detection device is detected, so that described18F detection device filters the aerosol in the gas sampled, with measurement and it is defeated
The aerosol counting rate out.
The first implementation according to the second embodiment further includes in second of implementation of second embodiment
Display unit 14 and electric control unit 15.
The display unit 14 is connect with the measurement processing unit 12, for being obtained according to the measurement processing unit
The leakage dot position information of presurized water reactor primary Ioops boundary leaking accordingly show leakage point.
The electric control unit 15 is used for respectively with the measurement processing unit 12 and the display unit 14 as institute
It states measurement processing unit and the display unit provides voltage output.
Second of implementation according to the second embodiment, it is described to take in the third implementation of second embodiment
Sample unit 11 is specifically used for pumping to sample gas outside containment by sampling pipe in sample point.
The measurement processing unit 12, the γ specifically for receiving the 0.511Mev that the probe unit 13 exports are penetrated
Line counting rate and the aerosol counting rate calculate the sampling according to the gamma-ray meter digit rate of the 0.511Mev of output
In gas13The beta activity activity of N；According to the aerosol counting rate of output, calculate in the gas sampled18The β of F is radiated
Property activity；Wherein, if beta activity activity is A,13The beta activity activity of N and18The calculating process of the beta activity activity of F is：A
=(n-nb)/ε, in formula, ε is detection efficient, nbFor background counting rate, n is counting rate when measuring sample, works as calculating13The β of N
When radioactive activity, n is the gamma-ray meter digit rate of the 0.511Mev, works as calculating18When the beta activity activity of F, n is the gas
Colloidal sol counting rate；According to described13The beta activity activity of N and described18The beta activity activity of F, calculates in the gas sampled13N
With18The sampling concentration ratio of F；Wherein, if13The beta activity activity of N is AtN,18The beta activity activity of F is AtNIf described take
Sample concentration ratio is C2, then
The measurement processing unit 12, is specifically also used to obtain13N and18Initial concentration ratio of the F in leakage point；Wherein,
If13The initial beta activity activity of N is A0N,18The initial beta activity activity of F is A0FIf the initial concentration ratio is C1, thenAccording to13N and18F leakage point initial concentration ratio and13N and18Sampling concentration ratio of the F in sample point, meter
It calculates13N and18Diffusion time of the F from leakage point to sample point；Wherein, core decaying rule A (t)=A0*e-λt, decay coefficientFor half-life period,13The half-life period of N is 9.97min,18The half-life period of F is 110min, is located at t moment,13N and18F
It is in the sampling concentration ratio of sample point：ThenIn formula, λNFor13The decay of N
Constant, λFFor18The decay coefficient of F.
Third embodiment of the invention provides a kind of monitor, including presurized water reactor described in any one of second embodiment
Primary Ioops boundary leaking monitors system.
In embodiments of the present invention, the monitor includes presurized water reactor primary Ioops described in any one of second embodiment
Boundary leaking monitors system, and the presurized water reactor primary Ioops boundary leaking monitoring method is that can provide the one of leakage point informational function
The development providing method process of circuit pressure boundary leaking monitoring instrument, it is indicated that the future thrust of leakage monitoring instrument,
The monitor repairs speed, the radiation agent that reduction repair personnel is subject to during repairing to repair personnel is improved in nuclear power station
Amount is very beneficial.
It should be noted that the apparatus embodiments described above are merely exemplary, wherein described be used as separation unit
The unit of explanation may or may not be physically separated, and component shown as a unit can be or can also be with
It is not physical unit, it can it is in one place, or may be distributed over multiple network units.It can be according to actual
It needs that some or all of the modules therein is selected to achieve the purpose of the solution of this embodiment.In addition, device provided by the invention
In embodiment attached drawing, the connection relationship between module indicate between them have communication connection, specifically can be implemented as one or
A plurality of communication bus or signal wire.Those of ordinary skill in the art are without creative efforts, it can understand
And implement.
The above is a preferred embodiment of the present invention, it is noted that for those skilled in the art
For, various improvements and modifications may be made without departing from the principle of the present invention, these improvements and modifications are also considered as
Protection scope of the present invention.
Claims (10)
1. a kind of presurized water reactor primary Ioops boundary leaking monitoring method, which is characterized in that include the following steps：
At sample point, gas sampled is obtained by sampling pipe；
It calculates in the gas sampled13N and18The sampling concentration ratio of F；
According to13N and18F leakage point initial concentration ratio and13N and18F is calculated in the sampling concentration ratio of sample point13N
With18Diffusion time of the F from leakage point to sample point；
The diffusion time is compared with preset time threshold, to obtain the leakage point of presurized water reactor primary Ioops boundary leaking
Confidence breath.
2. presurized water reactor primary Ioops boundary leaking monitoring method according to claim 1, which is characterized in that described in sample point
Place obtains gas sampled by sampling pipe, specially：
In sample point, sample gas is pumped to outside containment by sampling pipe.
3. presurized water reactor primary Ioops boundary leaking monitoring method according to claim 2, which is characterized in that further include：
The sample gas is passed through13N detection device is detected, so that described13N detection device filters in the gas sampled
0.511Mev gamma-rays, to measure and export the gamma-ray meter digit rate of the 0.511Mev；
The sample gas is passed through18F detection device is detected, so that described18F detection device filters in the gas sampled
Aerosol, to measure and export the aerosol counting rate.
4. presurized water reactor primary Ioops boundary leaking monitoring method according to claim 3, which is characterized in that described in the calculating
In gas sampled13N and18The sampling concentration ratio of F, specially：
According to the gamma-ray meter digit rate of the 0.511Mev of output, calculate in the gas sampled13The beta activity activity of N；
According to the aerosol counting rate of output, calculate in the gas sampled18The beta activity activity of F；Wherein, if β is radiated
Property activity be A,13The beta activity activity of N and18The calculating process of the beta activity activity of F is：A=(n-nb)/ε, in formula, ε is to visit
Survey efficiency, nbFor background counting rate, n is counting rate when measuring sample, works as calculating13When the beta activity activity of N, n is described
The gamma-ray meter digit rate of 0.511Mev, works as calculating18When the beta activity activity of F, n is the aerosol counting rate；
According to described13The beta activity activity of N and described18The beta activity activity of F, calculates in the gas sampled13N and18F's
Sample concentration ratio；Wherein, if13The beta activity activity of N is AtN,18The beta activity activity of F is AtNIf the sampling concentration ratio
Example is C2, then
5. presurized water reactor primary Ioops boundary leaking monitoring method according to claim 4, which is characterized in that the basis13N
With18F leakage point initial concentration ratio and13N and18F is calculated in the sampling concentration ratio of sample point13N and18F is from leakage point
To the diffusion time of sample point, specially：
It obtains13N and18Initial concentration ratio of the F in leakage point；Wherein, if13The initial beta activity activity of N is A0N,18F's is initial
Beta activity activity is A0FIf the initial concentration ratio is C1, then
According to13N and18F leakage point initial concentration ratio and13N and18F is calculated in the sampling concentration ratio of sample point13N
With18Diffusion time of the F from leakage point to sample point；Wherein, core decaying rule A (t)=A0*e-λt, decay coefficient
For half-life period,13The half-life period of N is 9.97min,18The half-life period of F is 110min, is located at t moment,13N and18F takes sample point
Sample concentration ratio is：ThenIn formula, λNFor13The decay coefficient of N, λFFor18F's
Decay coefficient.
6. according to claim 1 to presurized water reactor primary Ioops boundary leaking monitoring method described in 5 any one, which is characterized in that
The acquisition of the preset time threshold includes the following steps：
Containment three-dimensional is established with the Collaborative Simulation Environment (workbench) in ANSYS (large-scale general finite element analysis software)
Model；
In fluent software, choosing DIFFUSION IN TURBULENCE model on the basis of the containment threedimensional model is k- ε model, and is set
Boundary condition is determined, to generate presurized water reactor primary Ioops boundary leaking simulation model；Wherein, the boundary condition includes the side in leakage face
The boundary condition of boundary's condition, ventilating surface；
On the presurized water reactor primary Ioops boundary leaking simulation model, simulation is calculated in nuclear leakage gas13N and18F is from each leakage
Point be diffused into sampled point needed for the time, with obtain each leakage point to sampled point corresponding each preset time threshold.
7. a kind of presurized water reactor primary Ioops boundary leaking monitors system, which is characterized in that including sampling unit and measurement processing unit；
The sampling unit is connect with the measurement processing unit, for obtaining sampling gas by sampling pipe at sample point
Body；
The measurement processing unit, for calculating in the gas sampled13N and18The sampling concentration ratio of F；
The measurement processing unit, is also used to basis13N and18F leakage point initial concentration ratio and13N and18F is in sample point
Sampling concentration ratio, calculate13N and18Diffusion time of the F from leakage point to sample point；
The measurement processing unit is also used to for being compared with preset time threshold the diffusion time, to obtain presurized water reactor
The leakage dot position information of primary Ioops boundary leaking.
8. presurized water reactor primary Ioops boundary leaking according to claim 7 monitors system, which is characterized in that further include that detection is single
Member；
The probe unit is separately connected the sampling unit and the measurement processing unit, for leading to the sample gas
It crosses13N detection device is detected, so that described13N detection device filters the gamma-rays of the 0.511Mev in the gas sampled,
To measure and export the gamma-ray meter digit rate of the 0.511Mev；
And the sample gas is passed through18F detection device is detected, so that described18F detection device filters the sampling gas
Aerosol in body, to measure and export the aerosol counting rate.
9. presurized water reactor primary Ioops boundary leaking according to claim 8 monitors system, which is characterized in that further include that display is single
Member and electric control unit；
The display unit is connect with the measurement processing unit, the presurized water reactor for being obtained according to the measurement processing unit
The leakage dot position information of primary Ioops boundary leaking accordingly shows leakage point；
The electric control unit is used to be the measurement processing respectively with the measurement processing unit and the display unit
Unit and the display unit provide voltage output.
10. a kind of monitor, which is characterized in that including the presurized water reactor primary Ioops boundary as described in claim 7 to 9 any one
Leakage monitoring system.
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