CN109935374A - A kind of containment atmospheric radiation monitoring device - Google Patents

A kind of containment atmospheric radiation monitoring device Download PDF

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Publication number
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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China
Prior art keywords
detector
inert gas
containment
chamber
module
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Inventor
曲广卫
徐进财
连琦
李天吟
王俊超
周红
靳磊
王珂
常贤龙
刘朋波
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SHAANXI WEIFENG NUCLEAR INSTRUMENT Inc
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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SHAANXI WEIFENG NUCLEAR INSTRUMENT Inc
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
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Priority to CN201910150897.9A priority Critical patent/CN109935374A/en
Publication of CN109935374A publication Critical patent/CN109935374A/en
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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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

A kind of containment atmospheric radiation monitoring device
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,18+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.
CN201910150897.9A 2019-02-28 2019-02-28 A kind of containment atmospheric radiation monitoring device Pending CN109935374A (en)

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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
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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
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Application publication date: 20190625