CN109935374A - A kind of containment atmospheric radiation monitoring device - Google Patents
A kind of containment atmospheric radiation monitoring device Download PDFInfo
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- CN109935374A CN109935374A CN201910150897.9A CN201910150897A CN109935374A CN 109935374 A CN109935374 A CN 109935374A CN 201910150897 A CN201910150897 A CN 201910150897A CN 109935374 A CN109935374 A CN 109935374A
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- 230000005855 radiation Effects 0.000 title claims abstract description 52
- 238000012806 monitoring device Methods 0.000 title claims abstract description 11
- 239000011261 inert gas Substances 0.000 claims abstract description 42
- 238000005070 sampling Methods 0.000 claims abstract description 37
- 238000012545 processing Methods 0.000 claims abstract description 30
- 238000011065 in-situ storage Methods 0.000 claims abstract description 22
- 239000007789 gas Substances 0.000 claims abstract description 12
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 claims abstract description 7
- 239000000523 sample Substances 0.000 claims description 40
- 210000004907 gland Anatomy 0.000 claims description 23
- 238000012544 monitoring process Methods 0.000 claims description 17
- 230000005540 biological transmission Effects 0.000 claims description 10
- 230000007246 mechanism Effects 0.000 claims description 9
- 238000003825 pressing Methods 0.000 claims description 9
- 238000005259 measurement Methods 0.000 claims description 8
- 238000009413 insulation Methods 0.000 claims description 7
- 229910000831 Steel Inorganic materials 0.000 claims description 6
- 230000033001 locomotion Effects 0.000 claims description 6
- 239000010959 steel Substances 0.000 claims description 6
- 238000007789 sealing Methods 0.000 claims description 4
- 238000004891 communication Methods 0.000 claims description 3
- 238000012986 modification Methods 0.000 claims 3
- 230000004048 modification Effects 0.000 claims 3
- 230000005611 electricity Effects 0.000 claims 1
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- 239000002245 particle Substances 0.000 description 29
- 238000001514 detection method Methods 0.000 description 21
- 238000000034 method Methods 0.000 description 20
- 230000000694 effects Effects 0.000 description 19
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 15
- 238000006243 chemical reaction Methods 0.000 description 7
- 239000000498 cooling water Substances 0.000 description 7
- 238000010586 diagram Methods 0.000 description 7
- 239000000443 aerosol Substances 0.000 description 6
- 238000001228 spectrum Methods 0.000 description 6
- 238000004364 calculation method Methods 0.000 description 4
- ZSLUVFAKFWKJRC-IGMARMGPSA-N 232Th Chemical compound [232Th] ZSLUVFAKFWKJRC-IGMARMGPSA-N 0.000 description 3
- 229910052776 Thorium Inorganic materials 0.000 description 3
- 238000010521 absorption reaction Methods 0.000 description 3
- 238000000151 deposition Methods 0.000 description 3
- 230000005251 gamma ray Effects 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 230000002285 radioactive effect Effects 0.000 description 3
- 230000004044 response Effects 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 2
- 239000002826 coolant Substances 0.000 description 2
- 230000008021 deposition Effects 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 230000005484 gravity Effects 0.000 description 2
- 239000011810 insulating material Substances 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 229910052704 radon Inorganic materials 0.000 description 2
- SYUHGPGVQRZVTB-UHFFFAOYSA-N radon atom Chemical compound [Rn] SYUHGPGVQRZVTB-UHFFFAOYSA-N 0.000 description 2
- 230000009257 reactivity Effects 0.000 description 2
- 238000006424 Flood reaction Methods 0.000 description 1
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- 230000009471 action Effects 0.000 description 1
- 230000003321 amplification Effects 0.000 description 1
- JJWKPURADFRFRB-UHFFFAOYSA-N carbonyl sulfide Chemical compound O=C=S JJWKPURADFRFRB-UHFFFAOYSA-N 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
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- 238000004004 elastic neutron scattering Methods 0.000 description 1
- 230000005442 electron-positron pair Effects 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
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- 239000010419 fine particle Substances 0.000 description 1
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- 239000000446 fuel Substances 0.000 description 1
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- 125000004435 hydrogen atom Chemical group [H]* 0.000 description 1
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- DNNSSWSSYDEUBZ-OUBTZVSYSA-N krypton-85 Chemical compound [85Kr] DNNSSWSSYDEUBZ-OUBTZVSYSA-N 0.000 description 1
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- 239000000126 substance Substances 0.000 description 1
- 230000032258 transport Effects 0.000 description 1
- 239000002912 waste gas Substances 0.000 description 1
Classifications
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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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- Measurement Of Radiation (AREA)
Abstract
The present invention provides a kind of containment atmospheric radiation monitoring device, including pedestal, setting portion on the base18Then F detector and inert gas radiation detector, sampling pump are delivered to respectively by safety valve by extracting gas sampled inside containment18F detector and inert gas radiation detector, described18It is provided at F detector18The preposition processing module of F, with18The preposition processing module connection of F18F treatment in situ module, setting and inert gas treatment in situ module, described at the inert gas radiation detector18The preposition processing module of F,18F treatment in situ module and inert gas treatment in situ module are separately positioned on bracket, and the bracket setting is on the base.
Description
Technical field
The present invention relates to a kind of nuclear power plant's waste gas monitoring technical fields, and in particular to a kind of containment atmospheric radiation monitoring dress
It sets
Background technique
The nuclear power unit of PWR Nuclear Power Plant is usually made of two closed circulation loops, claims primary Ioops and two
Circuit.Primary Ioops include that equipment, the pressure such as reactor (being sealed in pressure vessel), main cooling water pump, voltage-stablizer are maintained at 120
~160 atmospheric pressure;Secondary circuit includes that equipment, the pressure such as steam generator, condenser, main cooling water pump are maintained at 70 atmosphere
Pressure.Primary Ioops are connected to the steam generator in reactor core and secondary circuit.
In order to ensure the radioactive substance in reactor does not enter environment, avoid causing radiation pollution to the mankind and environment,
Steam generator in the armamentarium and secondary circuit of the primary Ioops of PWR Nuclear Power Plant is mounted in containment.
In containment, pressure vessel, voltage-stablizer, main cooling water pump, the cooling water pipeline etc. of the sealing reactor of primary Ioops
Equipment itself and the flange being attached thereto, valve, pad, the steam generator of secondary circuit and its method being connected with primary Ioops
Orchid, valve, pad junction form the pressure boundary of pressurized water reactor coolant system.
Due to a variety of causes such as manufacture, installation, abrasion, corrosion, high temperature and pressure cooling water in primary Ioops may break through pressure
Force boundary constraint, leaks into containment.This leakage will generate two serious consequences: first is that reactor coolant water amount is insufficient,
Cause reactor operation safety accident;Second is that the radioactive substance contained in primary Ioops water enters environment, cause to environment and people
The harm of class.Thereby it is ensured that the integrality of pressurized water reactor nuclear power unit primary Ioops pressure boundary, transports the safety of nuclear power plant
Row is most important.
Currently, common RCPB leakage radioactivity monitoring method has the monitoring of containment radioaerosol, inert gas
Activity concentration monitoring, although when the monitoring detection efficient height of existing, inert gas activity concentration, response
Between it is short, but can only observational measurement radionuclide activity concentration;For lower levels of leakage, often can not require when
Interior measurement slip value, application are very limited.
Summary of the invention
In view of this, there is provided a kind of containment atmospheric radiation monitoring devices for the main object of the present invention.
The technical solution adopted by the present invention are as follows:
A kind of containment atmospheric radiation monitoring device, which is characterized in that including
Pedestal, setting portion on the base18F detector and inert gas radiation detector,
Then sampling pump is delivered to respectively by safety valve by extracting gas sampled inside containment18F detector and
Inert gas radiation detector, described18It is provided at F detector18The preposition processing module of F, with18The preposition processing module connection of F
's18F treatment in situ module, setting and inert gas treatment in situ module, described at the inert gas radiation detector18Before F
Set processing module,18F treatment in situ module and inert gas treatment in situ module are separately positioned on bracket, and the branch is set up
It sets on the base.
It is described18F detector includes containment, is arranged in the probe tube on containment and counter sample pipe, setting in probe tube and
Sampling connecting valve and counter sample connection valve on counter sample pipe, and counter sample connection valve front end is set18F probe assembly and sampling
Pump, it is described18F probe assembly include the first shield, the main detector inside the first shield is set, meet detector and
Filter device, the main detector and meets detector and is oppositely arranged, and middle section is connect with filter device respectively;
The filter device includes filter housings, be provided in the filter head housings body inlet plenum, exhaust chamber, curl-paper box,
Cam, paper-pressing mechanism and chart drive motor, the chart drive motor drive the filter paper in filter paper box from side curl-paper box 131 to another
Side filter paper box, filter paper pass through between inlet plenum and exhaust chamber, compress when transmitting filter paper through paper-pressing mechanism.
The chart drive motor movement tenses filter paper, and band moving cam rotates, and cam presses microswitch, cuts off or opens
Paper motor power.The paper-pressing mechanism includes briquetting, the spring that briquetting lower part is arranged in and platen component.
The inert gas radiation detector includes shield, and the inner hollow setting of the shield is arranged along its inner wall
Have steel bushing, steel bushing inner wall be embedded in heat insulation layer, the upper and lower ends inside heat insulation layer be respectively arranged with main ionisation chamber locating slot and
Difference ionization chamber locating slot is respectively arranged with main ionisation chamber and difference at the main ionisation chamber locating slot and difference ionization chamber locating slot
To divide ionisation chamber, and is provided with connector sleeve between main ionisation chamber and difference ionization chamber, the upper end of the shield is provided with gland, with
And external preposition processing module is arranged in by cable connection for main ionisation chamber and difference ionization chamber;The gland includes mutually right
The left gland and right gland connect is provided with Butt Section between left gland and right gland, form sealing structure, the left gland and the right side
Gland is fixed by screw or bolt with shield.
The shield selects 4 Π lead screen bodies, and 4 Π lead screen body thicknesses are at least 40mm.
The difference ionization chamber includes a measuring chamber and compensated chamber.
The preposition processing module includes variable gain amplifier, I/F converter unit and ARM controlling unit, it is described can
Adjust gain amplifier by connecting respectively by cable with measuring chamber and compensated chamber, the variable gain amplifier is become by I/F
Unit connection ARM controlling unit is changed, ARM controlling unit is connected to inert gas treatment in situ module by RS485 interface;
The inert gas treatment in situ module include ARM primary processor and the display screen being connect with ARM primary processor,
Input keyboard, network interface and multiple ports I/O,
The display screen shows measurement data by the format of setting;
The keyboard inputs corresponding information;
The data that the RS485 port transmission or receiving front-end processing unit are sent;
The network port realizes the communication and data exchange with outer computer;
The port I/O receives environment or measured temperature, pressure and flow signal, output alarm or switch control letter
Number.
Present invention employs18F detection device,18F monitoring is a kind of emerging containment atmospheric radiation monitoring method, is one
Kind have many advantages, such as can to quantify, the advanced method that high sensitivity, response time are fast.It can be sent out faster, earlier using the method
The leakage situation of existing reactor-loop pressure boundary prevents accident to take timely measure, and is reactor safety fortune
Capable important guarantee.
Detailed description of the invention
Fig. 1 is the structural diagram of the present invention;
Fig. 2 is in the present invention18The structural schematic diagram of F detector;
Fig. 3 is the structural schematic diagram of filter device in the present invention;
Fig. 4 is the structural schematic diagram of inert gas radiation detector in the present invention;
Fig. 5 is the electric diagram of inert gas radiation detector in the present invention;
Fig. 6 is that containment atmospheric radiation monitor equipment forms frame principle in the present invention;
Fig. 7 is containment atmospheric radiation monitor work flow diagram in the present invention;
Fig. 8 is that γ-γ meets method detection in the present invention18F nucleic schematic diagram;
Fig. 9 is in the present invention18F transmission flow and detection system figure;
Figure 10 is that γ-γ meets method detection in the present invention18F and rejecting 511keV background interference principle;
Figure 11 is to meet method detection in the present invention18The circuit function module figure of F;
Figure 12 is radiation processing unit functional frame composition on the spot in the present invention;
Specific embodiment
Below in conjunction with attached drawing and specific embodiment, the present invention will be described in detail, herein illustrative examples of the invention
And explanation is used to explain the present invention, but not as a limitation of the invention.
Referring to figs. 1 to 12, a kind of containment atmospheric radiation monitoring device, including
3 top of pedestal is arranged in pedestal 318F detector 1 and inert gas radiation detector 2,
Then sampling pump 4 is delivered to respectively by safety valve by extracting gas sampled inside containment18F detector 1 with
And inert gas radiation detector 2, described18It is provided at F detector 118The preposition processing module 9 of F, with18The preposition processing mould of F
What block 9 connected18F treatment in situ module 8, setting and inert gas treatment in situ module at the inert gas radiation detector 2
7, it is described18The preposition processing module 9 of F,18F treatment in situ module 8 and inert gas treatment in situ module 7 are separately positioned on bracket
On 5, the bracket 5 is arranged on pedestal 3.
It is described18F detector 1 includes containment 19, and probe tube 15 and counter sample pipe 14 on containment 19 is arranged in, and setting exists
Sampling connecting valve 16 and counter sample connection valve 18 on probe tube 15 and counter sample pipe 14, and be arranged in 18 front end of counter sample connection valve
's18F probe assembly and sampling pump 17, it is described18F probe assembly includes the first shield 10, is arranged in the first shield 10
The main detector 11 in portion meets detector 12 and filter device 13, the main detector 11 and meets that detector 12 is opposite to be set
It sets, middle section is connect with filter device 13 respectively;
The filter device 13 includes filter housings, be provided in the filter head housings body inlet plenum 133, exhaust chamber 134,
Curl-paper box 131, cam 132, paper-pressing mechanism and chart drive motor 136, the chart drive motor 136 drive the filter paper in filter paper box from
Side curl-paper box 131 arrives other side filter paper box, and filter paper 135 when transmitting filter paper by passing through between inlet plenum 133 and exhaust chamber 134
Paper-pressing mechanism compresses.
The movement of chart drive motor 136 tenses filter paper 131, and band moving cam 132 rotates, and cam 132 presses microswitch
130, cut off or open 136 power supply of chart drive motor.The paper-pressing mechanism 137 includes briquetting 139,139 lower part of briquetting is arranged in
Spring 138 and platen component 137.
The inert gas radiation detector 2 includes secondary shielding body 201, and the inner hollow of the secondary shielding body 201 is set
It sets, its inner wall is provided with steel bushing 202, be embedded in heat insulation layer 203 in 202 inner wall of steel bushing, the upper and lower ends inside heat insulation layer 203
It is respectively arranged with main ionisation chamber locating slot 206 and difference ionization chamber locating slot 208, the main ionisation chamber locating slot 206 and difference
Main ionisation chamber 205 and difference ionization chamber 204, and main ionisation chamber 205 and difference ionization are respectively arranged at ionisation chamber locating slot 208
Connector sleeve 207 is provided between room 204, the upper end of the secondary shielding body 201 is provided with gland 209 and main ionisation chamber 205
External preposition processing module 212 is set by cable connection with difference ionization chamber 204;The gland 209 includes mutually right
The left gland and right gland connect is provided with Butt Section between left gland and right gland, form sealing structure, the left gland and the right side
Gland is fixed by screw or bolt 210 with shield.
The secondary shielding body 201 selects 4 Π lead screen bodies, and 4 Π lead screen body thicknesses are at least 40mm.
The difference ionization chamber 204 includes a measuring chamber and compensated chamber.
The preposition processing module 212 includes variable gain amplifier, I/F converter unit and ARM controlling unit, described
For variable gain amplifier by being connect respectively by cable with measuring chamber and compensated chamber, the variable gain amplifier passes through I/F
Converter unit connects ARM controlling unit, and ARM controlling unit is connected to inert gas treatment in situ module by RS485 interface;
Referring to Fig.1 2, the inert gas treatment in situ module 7 includes ARM primary processor and connects with ARM primary processor
Display screen, input keyboard, network interface and the multiple ports I/O connect,
The display screen shows measurement data by the format of setting;
The keyboard inputs corresponding information;
The data that the RS485 port transmission or receiving front-end processing unit are sent;
The network port realizes the communication and data exchange with outer computer;
The port I/O receives environment or measured temperature, pressure and flow signal, output alarm or switch control letter
Number.
Referring to Fig. 6, containment atmospheric radiation monitor is off-line type monitoring system, continuous to measure in containment atmosphere18F gas
The activity concentration of colloidal sol and inert gas, comprising: 118F detector, 1 inert gas detector, 2 spokes on the spot
Penetrate signal between processing unit (LRP), sampling pump, electric box, sampling loop, radiation detector and LRP and service cable with
And place the bracket of above equipment.
18F detector detects in containment atmosphere18F nucleic.It is obtained and is arranged in containment by two sampling pipes
Atmospheric sample at the circulating fan entrance area of interior east and west sides.
The diameter of Liang Gen branch probe tube is different, compensates for the length different to its, to make from containment
The sample flow of interior east and west sides can basically reach balance.Two branched pipes are before reaching radiation monitor, in containment
Inside merge into a root canal road.
The sampling of circulating fan inlet can be to avoid in containment for selection18F aerosol deposition circulating fan blade,
In condenser or pipeline.
Inert gas detector is for monitoring inert gas in containment85Kr (krypton -85) and133Total work of Xe (XenonInjection)
Concentration is spent, is the important supplementary means of RCPB leakage radioactivity monitoring.
Containment atmospheric radiation monitor includes two radiation processing units on the spot: one is completed to detecting18F nucleic
Acquisition, data processing and the display of signal;Another completes to detecting85Kr and133The signal of the total activity concentration of Xe
Acquisition, data processing and display;Each radiation processing unit can be communicated with remote computer on the spot, receive external control letter
Number, send measured radiation data, to speak, light alarm and indication signal.
In order to calculate the activity concentration under standard state, monitor further includes temperature and pressure monitoring device.
Electric control box major function is to introduce external impetus power supply to power to radiation processing unit on the spot and aspiration pump, with
The automatic control that the components such as aspiration pump can be achieved after radiation processing unit, the connection of sampling loop control assembly on the spot, in man-machine friendship
Mutual interface can show that power supply state, setting running timer, record aspiration pump runing time, operation interface are furnished with switching switch,
The operating status of pumping can be switched between automatic/hand/closing.
Referring to Fig. 7, sampling pump pump effect under, the atmospheric sample being derived from containment initially enters aerosol filtration
Room is completed by corresponding detector and on the spot radiation processing unit to depositing on filter material18The monitoring of F nucleic activity concentration;So
Afterwards enter inert gas sampling room, then by corresponding detector and on the spot radiation processing unit completion to inert gas85Kr and133The monitoring of the total activity concentration of Xe;It is back in containment finally by backpass ductwork.
Reference Fig. 8,18F nucleic radiation detection principle are as follows:
Elastic scattering, the matter of the high-energy of generation occur for the hydrogen atom in fast neutron and primary Ioops water in pressurized water reactor
Son reacts with water oxygen atom, and generating has radioactive nucleic18F:
18F passes through transmitting positive electron (β+Particle) it decay to18O (oxygen -18), the β of decay emission+Particle and ambient substance
In electron outside nucleus annihilation reaction occurs, generate the γ photon that both direction is opposite, energy is all 511keV.
By measuring the intensity of the γ photon of the 511keV, can calculate18The specific radioactivity of F, so as to find out pressure water
Reactor-loop pressure boundary18The slip of F.
This programme meets the intensity of the γ photon of method measurement 511keV using γ-γ,
Under the action of aspiration pump, contain18The gas of F nucleic enters filter chamber.It is filtered through filter paper,18F nucleic gas is molten
Glue is deposited on filter paper.
Face deposition18The main detector (upper position) of F nucleic aerosol detects18The 511keV gamma that F nucleic generates
Ray;Meanwhile meeting detector (lower position, opposite with main detector) detection18Opposite direction caused by F nucleic
511keV gamma rays.
After amplification, main detector signal feeding meets digital multiple tracks and is acquired, and meets detector signal by discriminating
Not, it shapes, postpone etc. and meet digital multiple tracks as meeting gate signal feeding after links.
Under the control of gate signal, meets digital multiple tracks and only record and analyze in sample18The 511keV's that F nucleic generates
Gamma-ray signal.
Referring to Fig. 9, in PWR Nuclear Power Plant primary Ioops18The decay radiation of F nucleic is from generating to being measured to, warp
Gone through primary Ioops pressure boundary (RCPB), heat insulation layer, containment free space, sampling pipe, filter paper, many devices of detector and
Equipment,
By right18F is available from the analysis generated to the detected process of its radiation18The transmission system of F monitoring system
Number K:
In formula:
Y- containment free volume;
In C- primary Ioops water18F specific radioactivity;
f-18The proportionality coefficient of F particle;
λ-18F decay coefficient;
λc-18F loses equivalent constant;
F- atmosphere sample flow;
In P- sampling pipe18F particle transmission coefficient;
ε-filter paper collection efficiency;
η-detection efficient;
Each specific meaning of parameter is as follows:
(1) the free volume V of containment
The free volume V of containment refers to the space that leakage sample can be reached freely.
(2) in primary Ioops cooling water18F specific activity c
After circulation, in primary Ioops cooling water18The concentration and specific radioactivity of F be it is uniform, and react core function
Rate is proportional.18F specific radioactivity indicates with c, unit Bq/cm3Or Bq/L.
The one-dimensional cylinder model in space, the first neutron energy spectrum of calculating fuel fission generation are used according to core structure.
Recoil proton power spectrum in H (n, n) P reaction is calculated according to neutron energy spectrum and elastic neutron scattering section.
It is calculated according to proton spectrum18O (p, n)18The reactivity of F reaction.
Primary Ioops waterborne radioactivity nucleic is calculated according to the cycle characteristics of primary Ioops water18The concentration and specific radioactivity of F.
Other in primary Ioops water generate18The calculating of F:
19F (n, 2n),18F (n, 2n) reaction channel
The reactivity R of the reaction channel may be calculated as
In formula: ΦiFor i-th group of neutron average flux, 1/cm2·s
σiFor i-th group of neutron average response section, cm2
NFFor in water19The cuclear density of F
11B (p, n)11The C reaction threshold value is 3.1MeV
11C is a kind of with β+The nucleic of decay, half-life period 20.4min.In primary Ioops water11The natural abundance of B is 2%,
Weight percent of the B in primary Ioops water is 1174ppm.
(3) in containment18F fine particle fraction coefficient f
18F is before entering containment atmosphere, some in the gap between primary Ioops pressure boundary and heat-insulating material
It is formed18F aerosol particles.The particle will be absorbed a part across heat-insulating material process.
Into in containment atmosphere18F aerosol particles with18The ratio of the total leakage rate of F is known as18F aerosol particles ratio
Coefficient is indicated with f.
According to the material and structure of the heat insulation layer of primary Ioops pressure boundary, calculated using emulation mode.
(4) in containment18The decay coefficient λ and absorption constant λ of F particlec
Into in containment atmosphere18F particle, under containment cooling channel effect, through physical actions such as diffusion, convection current
And it is uniformly distributed in containment.In this process, in containment atmosphere18On the one hand F concentration increases with leakage, on the other hand
It is reduced due to the absorption of each equipment in decay and containment.Decay coefficient and absorption constant use λ and λ respectivelycIt indicates, λc?
Referred to as lose constant.
(5) sample flow F in sampling pipe
The atmospheric sample amount flowed through in sampling pipe in unit time is known as sample flow, is indicated with F, unit L/min.
The time of propagation in atmosphere will be much smaller than in sampling pipe18The half-life period of F, so that in this period18Shadow of the decaying of F to measurement
Sound can be ignored.
(6)18Transmission coefficient P of the F particle in sampling pipe
The effects of in sampling pipe due to gravity and frictional force, a part18F particle can be deposited on sampling pipe tube wall
On.It reaches on filter membrane18It is extracted in F particle number and containment18The ratio between F particle number is known as in sampling pipe18F particle
Transmission coefficient P.
18Motion state of the F particle in sampling pipe will receive the influence of the following factor: the DIFFUSION IN TURBULENCE of particle,
Lift, Brownian movement, towrope resistance, gravity sedimentation, effect of inertia are sheared, the effect of these factors will make18F particle a part is heavy
Product is on sampling tube wall.
CFD software for calculation is selected to be calculated.First according to gas phase flow field in sampling pipe and18The characteristic of F particle phase, choosing
With suitable Gas and particles mathematical model, Movement Locus Equation and micronic dust rate equation are established, and right18F particle is sampling
Stress condition in pipe carries out analysis choice, its motion profile of theoretical calculation.Then, based on finite difference calculus to particle phase control
Equation carries out discrete method processing.Sampling pipe is divided into horizontal segment, vertical section, quarter bend pipeline section three types by third step.
Horizontal pipe section, vertical section and quarter bend pipeline section are calculated respectively, respectively obtain the transmission system of three sections of pipeline sections
The function formula of number P:
P=F (d, v, Φ, l) (6.4)
In formula: d is18F particle diameter, μm;
V is18F particle initial velocity, mm/s;
Φ is sampling pipe internal diameter, mm;
L is sampling pipe length, mm.
These above-mentioned parameters remove train value respectively:
D:1 μm, 1.5 μm, 2.0 μm, 2.5 μm, 3.0 μm;
V: it is determined by sampling caliber and sampling flow.
Φ: 14mm
L: for straight and vertical section 5m, 10m, 15m, 20m, 25m, 30m, 40m, 50m
Step 4: according to the specific geometric dimension and shape of the sampling pipe designed in engineering and the numerical value generation of sample flow
Enter in above-mentioned formula (6.4), can find out in practical sampling pipe18F particle transmission coefficient.
(7) filter paper collection efficiency ε
Gas sampled is collected into through filter paper on filter paper18F particle number and entrance filter paper18The ratio between F particle number is known as
Filter paper collection efficiency ε.
Due to what is be not collected18F particle can be sampled in pumped back containment, be repeated extraction, so ε ≈ 1.
(8) detection efficient η
One on filter paper18The output 0.511MeV gamma-ray burst number that F particle generates in detector is known as detection efficient,
It is indicated with η.
Detection efficient mainly by the geometrical factor of detection device,18Fβ+Efficiency and 0.511 MeV gamma-rays are buried in oblivion in decay
Intrinsic conversion efficiency factor in detector determines.Detection efficient is calculated with Monte Carlo method.
For the mode of Fixed Time Interval paper feed, on filter paper18F radioactive activity on the one hand being passed through with accumulation
The increase of the amount of gas and increase, on the other hand as the time decays.So on filter paper18The radioactive activity A of FfIt (t) can table
It is shown as:
It is detected according to containment atmospheric radiation monitor18The counting rate n of F nucleic 511keV annihilation photon, in conjunction with prison
The transmission coefficient K of examining system can calculate pressurized water reactor primary Ioops pressure boundary (RCPB)18The slip L of F:
L=n/K (6.6)
Wherein:
N- pulsimeter digit rate, unit cps;
L- primary Ioops pressure boundary slip, unit l/h;
6.2.2 minimum detectable Activity Calculation
The in the industry cycle commercial HPGe software for analyzing spectrum GammaVision-32 of widely used ORTEC[7]In, to out 16
Kind calculation formula, this programme use ORTEC for the method in the business software ScintiVision-32 of flashing energy spectrum analysis exploitation
It calculates.
Wherein:
MPA is minimum peak area;
σBFor background variance;
Wherein:
CiFor i-th counting;
L is the minimum road location in peak area;
H is peak area most high address;
Minimum detectable activity are as follows:
Wherein:
ε is efficiency at peak energy amount;
T is that spectrum obtains live time;
γdFor yield;
Referring to Fig.1 0, pair effect, high-energy ray due to caused by cosmic ray background, ambient enviroment energetic gamma rays
Compton effect,scattering, cause the interference to the peak γ that energy is 511keV, thus it is micro for being contained only in sample18F
Occasion, method measured directly, which cannot identify, to be come from18The gamma-rays of F decay.
Using two γ staggered relatively sensitive NaI (Tl) detectors, (main detector, one meets spy to this programme
Survey device), it is right18F decay generate two simultaneously, contrary, energy be all 511keV γ photon carry out γ-γ symbol
Close detection.
This method can effectively reject interference nucleic and the interference of the background radiation peak bring 511keV, reach only measurement sample
In18The gamma-ray purpose of F decay.
Since in natural air, radon, thorium daughter disintegration are almost without the β that can observe+Decay, so having same time
Annihilation radiation of the coincidence counting of relationship only on filter sample.Using method is met, can substantially reduce Environmental Radon,
The interference of thorium daughter.
It is to dodge that the electron-positron pair that μ decay itself and μ induce in shielding material, which buries in oblivion generated 511keV photon,
The important sources at the peaks backgrounds 511keV such as bright crystal, surrounding air, shield, another source at the peak background 511keV are high
The annihilation photon that energy γ background generates.After meeting method, detection system can effectively deduct the 511keV background.
Contain a large amount of thorium family daughter in sample208Tl, the gamma-rays of the higher 510.7keV of emissive porwer, is shown in Table
6.1, probability reaches 22.6%.208The energy of Tl transmitting is the gamma-rays of 2614.511keV, 583.187keV, and general γ is penetrated
Line detection system is readily observed, but be difficult to distinguish its transmitting 510.7keV gamma-rays with18F decay generates
511keV floods γ photon.But because208Tl when emitting 510.7keV gamma-rays, when different the direction of the launch it is opposite, energy
Identical another gamma-rays is measured, so after use meets method,18F detection system can effectively deduct 510.7keV ray
Contribution.
Table 6.1208The main gamma-rays of Tl transmitting
Using meeting method,18F detection system equally can also effectively reject inert gas85The energy that Kr is generated is 514keV
Gamma-rays interference.Therefore,18F detection system can effectively reject interference nucleic and the peak background radiation bring 511keV, only remember
Record is in sample18The annihilation radiation photon of F greatly reduces minimum detectable activity lower limit, improves detection performance.
Technical solution disclosed in the embodiment of the present invention is described in detail above, specific implementation used herein
Example is expounded the principle and embodiment of the embodiment of the present invention, and the explanation of above embodiments is only applicable to help to understand
The principle of the embodiment of the present invention;At the same time, for those skilled in the art is being embodied according to an embodiment of the present invention
There will be changes in mode and application range, in conclusion the content of the present specification should not be construed as to limit of the invention
System.
Claims (7)
1. a kind of containment atmospheric radiation monitoring device, which is characterized in that including
Pedestal, setting portion on the base18F detector and inert gas radiation detector,
Then sampling pump is delivered to respectively by safety valve by extracting gas sampled inside containment18F detector and inertia
Gas radiation detector, described18It is provided at F detector18The preposition processing module of F, with18The preposition processing module connection of F18F
Treatment in situ module, setting and inert gas treatment in situ module, described at the inert gas radiation detector18The preposition place F
Reason module,18F treatment in situ module and inert gas treatment in situ module are separately positioned on bracket, and the bracket setting exists
On pedestal.
2. containment atmospheric radiation monitoring device according to claim 1, which is characterized in that described18F detector includes peace
The probe tube on containment and counter sample pipe is arranged in full shell, and probe tube and sampling connecting valve and counter sample on counter sample pipe is arranged in
Connection valve, and counter sample connection valve front end is set18F probe assembly and sampling pump, it is described18F probe assembly includes first
Shield is arranged in the main detector inside the first shield, meets detector and filter device, the main detector and symbol
It closes detector to be oppositely arranged, middle section is connect with filter device respectively;
The filter device includes filter housings, be provided in the filter head housings body inlet plenum, exhaust chamber, curl-paper box, cam,
Paper-pressing mechanism and chart drive motor, the chart drive motor drive the filter paper in filter paper box to filter from side curl-paper box 131 to the other side
Carton, filter paper pass through between inlet plenum and exhaust chamber, compress when transmitting filter paper through paper-pressing mechanism.
3. containment atmospheric radiation monitoring device according to claim 2, which is characterized in that the chart drive motor movement will
Filter paper tenses, and band moving cam rotates, and cam presses microswitch, cuts off or open chart drive motor power supply.The paper-pressing mechanism packet
Include briquetting, the spring that briquetting lower part is set and platen component.
4. containment atmospheric radiation monitoring device according to claim 1, which is characterized in that the inert gas radiation inspection
Surveying device includes shield, and the inner hollow setting of the shield is provided with steel bushing along its inner wall, is embedded in and is insulated in steel bushing inner wall
Layer, the upper and lower ends inside heat insulation layer are respectively arranged with main ionisation chamber locating slot and difference ionization chamber locating slot, the main electricity
From being respectively arranged with main ionisation chamber and difference ionization chamber, and main ionisation chamber and difference at room locating slot and difference ionization chamber locating slot
Connector sleeve is provided between ionisation chamber, the upper end of the shield is provided with gland and main ionisation chamber and difference ionization chamber is logical
It crosses cable connection and external preposition processing module is set;The gland includes the left gland and right gland being mutually butted, left pressure
Be provided with Butt Section between lid and right gland, formed sealing structure, the left gland and right gland by screw or bolt with
Shield is fixed.
5. inert gas monitoring detector after high temperature modification accident according to claim 4, which is characterized in that the shield
4 Π lead screen bodies are selected, 4 Π lead screen body thicknesses are at least 40mm.
6. inert gas monitoring detector after high temperature modification accident according to claim 4, which is characterized in that the differential electrical
It include a measuring chamber and compensated chamber from room.
7. inert gas monitoring detector after high temperature modification accident according to claim 4, which is characterized in that the preposition place
Reason module includes variable gain amplifier, I/F converter unit and ARM controlling unit, and the variable gain amplifier is by dividing
Not Tong Guo cable connect with measuring chamber and compensated chamber, it is single that the variable gain amplifier by I/F converter unit connects ARM control
Member, ARM controlling unit are connected to inert gas treatment in situ module by RS485 interface;
The inert gas treatment in situ module includes ARM primary processor and the display screen connecting with ARM primary processor, input
Keyboard, network interface and multiple ports I/O,
The display screen shows measurement data by the format of setting;
The keyboard inputs corresponding information;
The data that the RS485 port transmission or receiving front-end processing unit are sent;
The network port realizes the communication and data exchange with outer computer;
The port I/O receives environment or measured temperature, pressure and flow signal, output alarm or switch control signal.
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Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111610548A (en) * | 2020-05-23 | 2020-09-01 | 陕西卫峰核电子有限公司 | I-129 radiation monitoring system and method |
CN111610546A (en) * | 2020-05-23 | 2020-09-01 | 陕西卫峰核电子有限公司 | I-129 and Kr-85 detection signal discrimination processing method |
CN112162309A (en) * | 2020-08-13 | 2021-01-01 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Cabinet type air-borne radioactive integrated monitoring device |
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Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2693551A1 (en) * | 1992-07-10 | 1994-01-14 | Electricite De France | Device indicating the flow rate of a leak in a primary circuit of a nuclear reactor. |
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 |
CN109100773A (en) * | 2018-10-29 | 2018-12-28 | 陕西卫峰核电子有限公司 | A kind of containment atmospheric radiation monitoring device |
CN109254316A (en) * | 2018-10-16 | 2019-01-22 | 陕西卫峰核电子有限公司 | A kind of nuclear power station aerosol continuous radiation monitoring device |
-
2019
- 2019-02-28 CN CN201910150897.9A patent/CN109935374A/en active Pending
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2693551A1 (en) * | 1992-07-10 | 1994-01-14 | Electricite De France | Device indicating the flow rate of a leak in a primary circuit of a nuclear reactor. |
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 |
CN109254316A (en) * | 2018-10-16 | 2019-01-22 | 陕西卫峰核电子有限公司 | A kind of nuclear power station aerosol continuous radiation monitoring device |
CN109100773A (en) * | 2018-10-29 | 2018-12-28 | 陕西卫峰核电子有限公司 | A kind of containment atmospheric radiation monitoring device |
Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN111610548A (en) * | 2020-05-23 | 2020-09-01 | 陕西卫峰核电子有限公司 | I-129 radiation monitoring system and method |
CN111610546A (en) * | 2020-05-23 | 2020-09-01 | 陕西卫峰核电子有限公司 | I-129 and Kr-85 detection signal discrimination processing method |
CN111610548B (en) * | 2020-05-23 | 2021-11-12 | 陕西卫峰核电子有限公司 | I-129 radiation monitoring system and method |
CN112162309A (en) * | 2020-08-13 | 2021-01-01 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Cabinet type air-borne radioactive integrated monitoring device |
CN112764084A (en) * | 2020-12-08 | 2021-05-07 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Beta + radioactive aerosol detection device |
CN112764084B (en) * | 2020-12-08 | 2022-06-28 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Beta + radioactive aerosol detection device |
CN112731508A (en) * | 2020-12-22 | 2021-04-30 | 武汉第二船舶设计研究所(中国船舶重工集团公司第七一九研究所) | Device and method for monitoring gas activity of nuclear power plant reactor after plant accident |
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