CN109712727A - A kind of main steam line Radiation monitoring method and device - Google Patents
A kind of main steam line Radiation monitoring method and device Download PDFInfo
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- 230000005855 radiation Effects 0.000 title claims abstract description 135
- 238000012544 monitoring process Methods 0.000 title claims abstract description 25
- 238000000034 method Methods 0.000 title claims abstract description 24
- 239000011261 inert gas Substances 0.000 claims abstract description 58
- 230000000694 effects Effects 0.000 claims abstract description 29
- 230000005540 biological transmission Effects 0.000 claims description 44
- 238000012545 processing Methods 0.000 claims description 40
- 238000012546 transfer Methods 0.000 claims description 37
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 31
- 238000001514 detection method Methods 0.000 claims description 24
- 238000005259 measurement Methods 0.000 claims description 18
- 238000000926 separation method Methods 0.000 claims description 15
- 238000009413 insulation Methods 0.000 claims description 11
- 230000005251 gamma ray Effects 0.000 claims description 9
- 230000035945 sensitivity Effects 0.000 claims description 8
- 238000006243 chemical reaction Methods 0.000 claims description 7
- 230000002285 radioactive effect Effects 0.000 claims description 7
- 238000004364 calculation method Methods 0.000 claims description 5
- 230000007613 environmental effect Effects 0.000 claims description 5
- 230000033001 locomotion Effects 0.000 claims description 4
- 230000005514 two-phase flow Effects 0.000 claims description 4
- 239000002826 coolant Substances 0.000 claims description 3
- 238000001035 drying Methods 0.000 claims description 3
- 238000010438 heat treatment Methods 0.000 claims description 3
- 238000003672 processing method Methods 0.000 claims 1
- 239000013078 crystal Substances 0.000 description 26
- 210000004907 gland Anatomy 0.000 description 8
- 238000001228 spectrum Methods 0.000 description 7
- VYPSYNLAJGMNEJ-UHFFFAOYSA-N Silicium dioxide Chemical compound O=[Si]=O VYPSYNLAJGMNEJ-UHFFFAOYSA-N 0.000 description 6
- 239000000498 cooling water Substances 0.000 description 6
- 229910001220 stainless steel Inorganic materials 0.000 description 6
- 239000010935 stainless steel Substances 0.000 description 6
- 229910000831 Steel Inorganic materials 0.000 description 5
- 238000010586 diagram Methods 0.000 description 5
- 239000010959 steel Substances 0.000 description 5
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 4
- 239000007789 gas Substances 0.000 description 4
- 229910002012 Aerosil® Inorganic materials 0.000 description 3
- 238000013461 design Methods 0.000 description 3
- 230000003993 interaction Effects 0.000 description 3
- 230000000149 penetrating effect Effects 0.000 description 3
- 238000004321 preservation Methods 0.000 description 3
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 2
- 230000005461 Bremsstrahlung Effects 0.000 description 2
- 239000000443 aerosol Substances 0.000 description 2
- 230000003321 amplification Effects 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 2
- 229910052681 coesite Inorganic materials 0.000 description 2
- 238000004891 communication Methods 0.000 description 2
- 229910052906 cristobalite Inorganic materials 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 238000003199 nucleic acid amplification method Methods 0.000 description 2
- 239000000377 silicon dioxide Substances 0.000 description 2
- 239000011780 sodium chloride Substances 0.000 description 2
- 229910052682 stishovite Inorganic materials 0.000 description 2
- 229910052905 tridymite Inorganic materials 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 229910052786 argon Inorganic materials 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000004888 barrier function Effects 0.000 description 1
- 230000005255 beta decay Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
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- 238000005260 corrosion Methods 0.000 description 1
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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
Abstract
The present invention provides a kind of main steam line Radiation monitoring method and device, method includes being arranged in main steam line16N radiation monitor and inert gas radiation detector, it is described16N radiation monitor passes through monitoring16N nucleic judges that steam generator leaks situation；In the inert gas radiation detector monitoring main steam line85Kr and133The total activity concentration of Xe；With16The connection of N radiation monitor16N radiation treatment module on the spot, the inert gas being connect with inert gas radiation detector radiation treatment module on the spot.With16N radiation monitor and the computer control unit of inert gas radiation detector connection, it is described16N radiation monitor and inert gas radiation detector receive computer control unit and control signal, send measured radiation data, to speak, light alarm and indication signal.
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 main steam line Radiation monitoring
Method and device.
Background technique
The nuclear power unit of PWR Nuclear Power Plant is usually made of two closed circulation loops, claim primary Ioops and
Secondary circuit.Primary Ioops include the equipment such as nuclear reactor (being sealed in pressure vessel), main cooling water pump, voltage-stablizer, and pressure is kept
In 120~160 atmospheric pressure；Secondary circuit includes that equipment, the pressure such as steam generator, condenser, main cooling water pump are maintained at 70
A atmospheric pressure.Primary Ioops are connected to the steam generator in reactor core and secondary circuit.
After the thermal energy for absorbing primary Ioops cooling water, secondary circuit cooling water is heated to boiling (about 260 DEG C of temperature) and forms water
Steam.The water vapor filtering is sent to steam turbine after falling the liquid water mixed, and turbogenerator operating is pushed to generate electricity.From
The secondary circuit cooling water of steam turbine outflow is back to steam generator after condenser is condensed into liquid water.
There are tens of thousands of heat-transfer pipes inside steam generator.In order to improve heat transfer efficiency, the tube wall of every heat-transfer pipe is made
It is very thin, only 1.09mm.Due to moving the cooling water of high temperature, high pressure in heat-transfer pipe, thus heat-transfer pipe is subject to mechanical damage
Wound and corrosion harmfulness, to generate leakage.
Summary of the invention
In view of this, there is provided a kind of main steam line Radiation monitoring method and devices for the main object of the present invention.
The technical solution adopted by the present invention are as follows:
A kind of main steam line Radiation monitoring method, including
Primary lateral secondary side 113l/d~757l/d in main steam line is set16N radiation monitor and inertia
Gas radiation detector,
It is described16N radiation monitor passes through monitoring16N nucleic judges that steam generator leaks situation；
In the inert gas radiation detector monitoring main steam line85Kr and133The total activity concentration of Xe；
With16The connection of N radiation monitor16N radiation treatment module on the spot, should16Radiation treatment module is used for spy N on the spot
It measures16Acquisition, data processing and the display of N nucleic signal；
The inert gas being connect with inert gas radiation detector radiation treatment module on the spot, inert gas spoke on the spot
Processing module is penetrated for detecting85Kr and133Acquisition, data processing and the display of the signal of the total activity concentration of Xe；
With16N radiation monitor and the computer control unit of inert gas radiation detector connection, it is described16N radiation prison
It surveys device and inert gas radiation detector receives computer control unit and controls signal, send measured radiation data, provide
Sound, light alarm and indication signal.
Further,16N is obtained after radiation treatment module data is handled on the spot16The slip of N, specific processing side
Method is as follows:
Heat-transfer pipe breakage in main steam generators16The slip of N and the detector measurement by the main steam header road16The gamma-ray meter digit rate that N decay generates has following relationship:
In formula:
Q is heat-transfer pipe slip (L/h),
N is measured place16The γ radiometer digit rate (s of N-1),
C is that heat-transfer pipe slip calculates transmission coefficient (s-1·L-1H),
Transmission coefficient C and detector geometrical factor K1, detector efficiency factor K2And when heat-transfer pipe unit slip16N is visited
At measuring point in main steam line16The gamma activity activity of N is closed, it may be assumed that
C=K1·K2·Av (6.3)
In formula:
AvWhen for heat-transfer pipe unit slip16At N sensing point in main steam line16The gamma activity activity of N,
AvIt is shown below:
Av=(Aρ/Q)·(ρv/ρp)·e-λt
(6.4)
In formula:
AρFor leakage position primary side16N radioactive activity (Bqcm-3), change with core power and leakage point position,
Q is steam flow (Lh in main steam pipe-1),
ρvFor main vapour density (kgm-3),
ρpFor coolant averag density (kgm-3),
λ is16N radiological decay constant (s-1),
T is16Transmission time (s) of the N from heat-transfer pipe leakage place to sensing point,
According to the structure size of reactor, steam generator and main steam line, physical parameter and16The Radiation monitoring of N
Point parameter, can calculate16The transmission time of N, detector geometrical factor K1, detector efficiency factor K2；Then, according to above-mentioned
It is various to calculate transmission coefficient c；Finally, it is broken to calculate heat-transfer pipe in main steam generators according to Transmission system c and counting rate n
At damage16The slip of N.
Further,16The detection method of transmission time t of the N from heat-transfer pipe leakage place to sensing point is as follows:
16The detection method of transmission time of the N from leakage point to measurement point is based on the assumption that model:
(1) Small leak amount is assumed: since leakage rate is small, the steam that water leakage becomes will not be to steam generator first and second
Heat transfer, the flow process generation of side significantly affect, i.e., steam generator is still in steady operational status；
(2) consistency is assumed: the water of primary side leaks into movement and the secondary side flow process for the steam that secondary side becomes
Unanimously；
(3) one-dimensional hypothesis: tube bundle region in steam generator of working media in secondary side, steam-water separation area, dry section
Be all One-Dimensional flows in main steam line；
(4) it isolates runner to assume: massless, momentum, energy variation between cold and hot two channel of steam generator secondary side；
By above-mentioned hypothesized model it is found that16N is heated two phase flow in tube bundle region, is insulation two-phase in steam-water separation area
Stream is single-phase steam flowing in dry section and main steam line, can be calculated with thermohydraulics program, calculation formula is as follows:
In formula: z1It is slip z to coordinate,
z2It is bend pipe area vertex z to coordinate,
wn1(z) for secondary side medium z to velocity component,
In formula: z2Z is exported to coordinate for steam-water separation area,
z1With the z in (6.5) formula2,
wn2(z) for steam-water separation area medium z to velocity component,
In formula: ρvFor vapour density,
VdFor dry section spatial volume,
Q is steam mass flow,
In formula: L is at steam generator outlet to the length between main steam line detector,
S is the section of main steam line,
ρv, Q and (6.7) formula it is same,
In above formula,
t1For in the time of tube bank heating zone transmission, i.e. admission port to the transmission time for giving water manifold, t1Because leaking point
Set it is different and different, usual Numerical heat transfer pipe hot end, this 3 positions of cold end and bend pipe t11、t12And t13, t1For they
Average value；t2For the transmission time in the transmission time in steam-water separation area, i.e., to water manifold to steam header；t3For in drying box
Transmission time, i.e. the transmission time that is exported to steam ring case of steam header；t4For steam ring case exit to main steam pipe
Transmission time at where detector.
Further, the inert gas radiation detector is provided with main ionisation chamber and difference ionization chamber, main ionisation chamber and
Difference ionization chamber working voltage polarity on the contrary, generated current direction also on the contrary, so as to offset to two ionisation chambers all
Contributive environmental exact details γ radiation,
It is counted caused by the output electric current of ionisation chamber are as follows:
N=IKf (7.1)
In formula: n is the counting rate measured, unit s-1,
Output electric current of the I for ionisation chamber, unit pA,
KfFor power frequency conversion coefficient, unit s-1/ pA,
It, can be lazy by formally calculating the radioactivity in main steam line after calibration obtains the sensitivity of ionisation chamber
The activity concentration of property gas:
In formula: S is ionisation chamber sensitivity, unit s-1/Bq。
The present invention also provides a kind of main steam line radiation monitoring equipment, including steam generator, setting is sent out in steam
U-tube inside raw device, is arranged in the main steam line on steam generator, the steam generator with containment carry out every
From, which is characterized in that it is provided on main steam line16N radiation monitor and inert gas radiation detector, with16N spoke
Penetrate monitor connection16N radiation treatment module on the spot, the inert gas connecting with inert gas radiation detector is with regard to eradiation
Processing module, with16N radiation monitor and the computer control unit of inert gas radiation detector connection, it is described16N radiation
Monitor and inert gas radiation detector receive computer control unit and control signal, send measured radiation data, give
It speaks, light is alarmed and indication signal；
And power supply box, it is described16N radiation monitor, inert gas radiation detector, computer control unit,16N is just
Eradiation processing module and inert gas radiation treatment module for power supply on the spot.
Further, described16N radiation monitor, inert gas radiation detector are arranged on bracket.
Steam generator heat-transfer pipe leakage monitor is arranged in PWR Nuclear Power Plant in the present invention, to nuclear power plant the
Two radioactivity protection barriers are monitored on-line, cause radioactive material contamination nuclear power plant two to return after avoiding heat-transfer pipe from leaking
Pipeline equipment or even accidental discharge, meaning are extremely important.
Detailed description of the invention
Fig. 1 is the principle of the present invention frame diagram；
Fig. 2 is structure structure chart of the invention；
Fig. 3 is the structural schematic diagram of filter assemblies in the present invention；
Fig. 4 is the circuit diagram of nuclear power station aerosol continuous radiation monitoring device in the present invention；
Fig. 5 is the schematic diagram of aerosol detection device in the present invention；
Fig. 6 is inert gas radiation detector in the present invention；
Fig. 7 is the circuit diagram of inert gas radiation detector in the present invention.
Specific embodiment
Below in conjunction with attached drawing and specific embodiment, the present invention will be described in detail, schematic implementation of the invention herein
Example and explanation are used to explain the present invention, but not as a limitation of the invention.
A kind of main steam line Radiation monitoring method, including
Primary lateral secondary side 113l/d~757l/d in main steam line is set16N radiation monitor and inertia
Gas radiation detector,
It is described16N radiation monitor passes through monitoring16N nucleic judges that steam generator leaks situation；
In the inert gas radiation detector monitoring main steam line85Kr and133The total activity concentration of Xe；
With16The connection of N radiation monitor16N radiation treatment module on the spot, should16Radiation treatment module is used for spy N on the spot
It measures16Acquisition, data processing and the display of N nucleic signal；
The inert gas being connect with inert gas radiation detector radiation treatment module on the spot, inert gas spoke on the spot
Processing module is penetrated for detecting85Kr and133Acquisition, data processing and the display of the signal of the total activity concentration of Xe；
With16N radiation monitor and the computer control unit of inert gas radiation detector connection, it is described16N radiation prison
It surveys device and inert gas radiation detector receives computer control unit and controls signal, send measured radiation data, provide
Sound, light alarm and indication signal.
Further,16N is obtained after radiation treatment module data is handled on the spot16The slip of N, specific processing side
Method is as follows:
Heat-transfer pipe breakage in main steam generators16The slip of N and the detector measurement by the main steam header road16The gamma-ray meter digit rate that N decay generates has following relationship:
In formula:
Q is heat-transfer pipe slip (L/h),
N is measured place16The γ radiometer digit rate (s of N-1),
C is that heat-transfer pipe slip calculates transmission coefficient (s-1·L-1H),
Transmission coefficient C and detector geometrical factor K1, detector efficiency factor K2And when heat-transfer pipe unit slip16N is visited
At measuring point in main steam line16The gamma activity activity of N is closed, it may be assumed that
C=K1·K2·Av (6.3)
In formula:
AvWhen for heat-transfer pipe unit slip16At N sensing point in main steam line16The gamma activity activity of N,
AvIt is shown below:
Av=(Aρ/Q)·(ρv/ρp)·e-λt
(6.4)
In formula:
AρFor leakage position primary side16N radioactive activity (Bqcm-3), change with core power and leakage point position,
Q is steam flow (Lh in main steam pipe-1),
ρvFor main vapour density (kgm-3),
ρpFor coolant averag density (kgm-3),
λ is16N radiological decay constant (s-1),
T is16Transmission time (s) of the N from heat-transfer pipe leakage place to sensing point,
According to the structure size of reactor, steam generator and main steam line, physical parameter and16The Radiation monitoring of N
Point parameter, can calculate16The transmission time of N, detector geometrical factor K1, detector efficiency factor K2；Then, according to above-mentioned
It is various to calculate transmission coefficient c；Finally, it is broken to calculate heat-transfer pipe in main steam generators according to Transmission system c and counting rate n
At damage16The slip of N.
Further,16The detection method of transmission time t of the N from heat-transfer pipe leakage place to sensing point is as follows:
16The detection method of transmission time of the N from leakage point to measurement point is based on the assumption that model:
(1) Small leak amount is assumed: since leakage rate is small, the steam that water leakage becomes will not be to steam generator first and second
Heat transfer, the flow process generation of side significantly affect, i.e., steam generator is still in steady operational status；
(2) consistency is assumed: the water of primary side leaks into movement and the secondary side flow process for the steam that secondary side becomes
Unanimously；
(3) one-dimensional hypothesis: tube bundle region in steam generator of working media in secondary side, steam-water separation area, dry section
Be all One-Dimensional flows in main steam line；
(4) it isolates runner to assume: massless, momentum, energy variation between cold and hot two channel of steam generator secondary side；
By above-mentioned hypothesized model it is found that16N is heated two phase flow in tube bundle region, is insulation two-phase in steam-water separation area
Stream is single-phase steam flowing in dry section and main steam line, can be calculated with thermohydraulics program, calculation formula is as follows:
In formula: z1It is slip z to coordinate,
z2It is bend pipe area vertex z to coordinate,
wn1(z) for secondary side medium z to velocity component,
In formula: z2Z is exported to coordinate for steam-water separation area,
z1With the z in (6.5) formula2,
wn2(z) for steam-water separation area medium z to velocity component,
In formula: ρvFor vapour density,
VdFor dry section spatial volume,
Q is steam mass flow,
In formula: L is at steam generator outlet to the length between main steam line detector,
S is the section of main steam line,
ρv, Q and (6.7) formula it is same,
In above formula,
t1For in the time of tube bank heating zone transmission, i.e. admission port to the transmission time for giving water manifold, t1Because leaking point
Set it is different and different, usual Numerical heat transfer pipe hot end, this 3 positions of cold end and bend pipe t11、t12And t13, t1For they
Average value；t2For the transmission time in the transmission time in steam-water separation area, i.e., to water manifold to steam header；t3For in drying box
Transmission time, i.e. the transmission time that is exported to steam ring case of steam header；t4For steam ring case exit to main steam pipe
Transmission time at where detector.
Further, the inert gas radiation detector is provided with main ionisation chamber and difference ionization chamber, main ionisation chamber and
Difference ionization chamber working voltage polarity on the contrary, generated current direction also on the contrary, so as to offset to two ionisation chambers all
Contributive environmental exact details γ radiation,
It is counted caused by the output electric current of ionisation chamber are as follows:
N=IKf (7.1)
In formula: n is the counting rate measured, unit s-1,
Output electric current of the I for ionisation chamber, unit pA,
KfFor power frequency conversion coefficient, unit s-1/ pA,
It, can be lazy by formally calculating the radioactivity in main steam line after calibration obtains the sensitivity of ionisation chamber
The activity concentration of property gas:
In formula: S is ionisation chamber sensitivity, unit s-1/Bq。
16The detection efficient of N detection system is mainly by the geometrical factor K of detection device1、16The γ of association is penetrated when the β decay of N
Intrinsic conversion efficiency K of the line in detector2Etc. factors determine.
16N emits the 7.12MeV high energy gamma photon of 69% 6.13MeV and 5% from generating quilt in main steam line
Gamma detector, which records, mainly have passed through two historical stages: first stage is in main steam line16N γ photon source energy
The no process for penetrating main steam line；Second stage be penetrate the γ photon of main steam line can incident detector system, simultaneously
It penetrates after detector involucrum layer interacts with detector crystal and causes the process counted.
According to the structure of main steam line and detector, Fig. 6 is seen, in the main steam line that detector is detected16N declines
It is low-down for selling of one's property raw gamma-ray peak source efficiency:
Main steam line has relatively thick steel pipe layer, so in main steam line16The γ photon source that N decay generates
Only some can penetrate main steam line.
High energy gamma photon only a small part after penetrating main pipeline can incident detector system, and incident detection
The γ photon of device will also penetrate each involucrum layer of detector, just can enter detector crystal after certain decaying.
The γ photon of incident detector crystal only some can in crystal sedimentary energy, i.e., incident γ photon is visited
Surveying device crystal has certain intrinsic conversion efficiency.
16The single energy γ photon of two kinds of 6.13MeV and 7.12MeV of N decay emission is wanted Zi generating to incident detector crystal
It could be arrived after each involucrum layer of air layer, detector between each shielded layer of main steam line, main steam line and detector
Up to detector crystal.In this process, 6.13MeV and two kinds of 7.12MeV single energy γ photons may be situated between with each shielded layer
The interaction such as photoelectric effect, Compton scattering and pair effect has occurred in matter, produces secondary photon and secondary electron,
And secondary electron can also generate next-generation secondary photon etc. again in the interaction with surrounding medium, this makes final reality
The γ photon of border incidence detector crystal is no longer both single energy γ photons of 6.13MeV and 7.12MeV.Therefore, detector
In this section of power spectrum of the 4.5MeV~7MeV surveyed, ingredient is sufficiently complex, specifically includes:
Full energy peak, single escape peak and the double escape peak of 6.13MeV γ photon, this is major part.
The single escape peak and double escape peak of a certain amount of 7.12MeV γ photon.
Two kinds of list energy γ photons of 6.13MeV and 7.12MeV are in detector crystal due to the scattering of Compton scattering generation
A part superposition of the long section continuous electronic energy spectrum of one left after photon escape.
16The γ photon of N passes through each involucrum layer of detection system and Compton scattering occurs.The energy before entering detector crystal
Amount is more than that the compton scattered photons of 4.5MeV finally may cause to count in this section of power spectrum of 4.MeV5~7MeV.
16N γ photon passes through each involucrum layer of detection system and generates photoelectron, Compton scattering electronics and positron-electron equity
Secondary electron, the energy that secondary electron may be generated with medium interaction are more than the bremsstrahlung photon of 4.5MeV, fly and fall into oblivion
It goes out the secondary photons such as photon, finally may cause to count in this section of power spectrum of 4.5MeV~7MeV.
Due to the fluctuation of detector output voltage amplitude pulse, so that the γ photon of incident detector crystal is in crystal
Actual deposition energy be also possible to draw in this section of power spectrum of 4.5MeV~7MeV of output except 4MeV.5~7MeV range
It rises and counts.
From above-mentioned analysis it is found that Near field K1And K2Depend mainly on the following aspects:
16The γ photon that N decay generates penetrates the penetrance that photon energy after main steam line is still greater than 4.5MeV, i.e., singly
Penetrated in the time of position the photon of the energy of main steam line greater than 4.5MeV with16The ratio between the source N radioactive activity.Referred herein
Photon includes 6.13MeV the and 7.12MeV high energy for being directed through main steam line16N γ photon and other energy are greater than
4.5MeV scattered photon and bremsstrahlung photon etc., i.e. this penetrance also include16The buildup factor of the mono- energy γ photon of N.
Penetrate high-energy photon of the energy greater than 4.5MeV after main steam line can incident detector system impingement rate,
High-energy photon of the energy greater than 4.5MeV forms the cylindrical surface source and detector system being centainly distributed after penetrating main steam line
Between geometrical factor.The size of geometrical factor and main steam line and detector and relative position between them are direct
It is related.
High-energy photon of the incident detector outer envelope energy greater than 4.5MeV penetrates energy after each overclad layer of detector crystal
Into the penetrance of detector crystal, i.e., to consider detector outer envelope to the attenuation effect of source photon.
Detector crystal sedimentary energy in the intrinsic conversion efficiency in the section 4.5MeV~7MeV, i.e., sedimentary energy 4.5MeV~
The counting rate in the section 7MeV and in the unit time practical incidence detector crystal the ratio between number of photons.With detector crystal material
Itself is related, also related with the position of γ photon source and detector crystal.
The volume and steam flow of main steam line.Because for same in pipeline16N radioactive activity, main steam pipe
The volume in road is different,16N radioactivity volume specific activity is just different, then Near field is also just different.Again because of main steam
In pipeline16N is entrained by the steam in pipeline, so steam flow or flow velocity determine16N radioactive source is in main steam
Distribution in pipeline.
In view of16The particularity of N detection device and above-mentioned analysis, for Near field K1And K2, prototype problem
Measuring is extremely difficult, can only be obtained at present by theoretical calculation.
Main steam line16The detection of N detection system16The 6.13MeV and two kinds of 7.12MeV gamma-ray counting rate N of N decay
Relational expression between slip L is again writeable are as follows:
In formula, K be at a distance from leakage point to detector, high steam flow velocity, gamma-ray emission probability, λ etc. it is related
The factor, detection efficient η be determine slip L basic concept.It is dependent on the size of detector and its with a distance from source
And the shielding material around detector, also rely on size and its geometry in source etc..η can use theoretical calculation and experiment
The body source of upper known strength and point source measurement obtain the gamma-ray long tube body of 6.13MeV due to being difficult in experiment measurement
Source, so we replace body source with point source to carry out detection efficiency calibration.
Coordinate system is defined first.Z-axis is the axis of steel pipe, and y-axis vertical level, x-axis is on the axis of detector.?
Cylindrical coordinate r is with a distance from the z of steel pipe axis, and φ is the azimuth of r.
Stable16In the state of the slip of N, gamma-ray counting rate,
N=ε (r0,φ0,z0)λeγ∫∫∫I(r,φ,z)R(r,φ,z)rdrdφdz (6.10)
Wherein eγIt is the gamma-ray emission probability of 6.13MeV-, I (r, φ, z) and R (r, φ, z) are respectively16The density of N
With relative efficiency spatial distribution,It is volume element.
It is located at reference point r0=0, φ0=0, z0Place a standard source, activity A, electronic instrument record in=0 position
The γ population arrived is n0, then the Absolute detection efficiency of reference source are as follows:
A standard source, activity A are placed at any point (r, φ, z), record population is n, then
Then in long tube any point radioactive source relative detection efficiency spatial distribution are as follows:
(r, φ, z)=ε (r, φ, z)/ε (r0, φ0, z0) (6.13)
If I (r, φ, z) is unrelated with r and φ, then:
I (z)=I0exp[-λ(L0+z)/v] (6.14)
Wherein I0It is at leak point16The density of N, L0It is distance of the leak point to detector, υ is the stream of high steam
Speed.
Then there is following three formula:
L=I0vS (6.15)
η=ε (r0, φ0, z0)∑(ξ) (6.16)
K=v-1·eλ·z0·λ·exp(-λL0/v) (6.17)
Wherein, S is the cross-sectional area of pipe diameter, Z0=1cm, ∑ (ξ) are the cumulative integrals at convergence point:
R (z) is integral of the R (r, φ, z) to r and φ, it is symmetrical, z relative to z=0cm0It is to eliminate
(6.10) formula integral dimension and introduce, if u >=10m/s, z=± 2.5m, z≤0.0243≤1, e λ-zAnd ezIt can Taylor
Expansion, and take the first order of z, then:
So relative detection efficiency factor η is
η=ε0(r0, φ0, z0)∑(ξ) (6.20)。
The present invention also provides a kind of main steam line radiation monitoring equipment, including steam generator, setting is sent out in steam
U-tube 2 inside raw device 3, is arranged in the main steam line 4 on steam generator 3, the containment 1 of steam generator 3
It is isolated, is provided on main steam line 416N radiation monitor 6 and inert gas radiation detector 5, with16N radiation
What monitor 6 connected16N radiation treatment module 8 on the spot, the inert gas connecting with inert gas radiation detector 5 is with regard to eradiation
Processing module 9, with16The computer control unit 10 that N radiation monitor 6 and inert gas radiation detector 5 connect, it is described16N
Radiation monitor 6 and inert gas radiation detector 5 receive computer control unit and control 10 signals, send measured spoke
Penetrate data, to speak, light alarm and indication signal；
And power supply box 11, it is described16N radiation monitor 6, inert gas radiation detector 5, computer control unit 10
、16N on the spot power on the spot for radiation treatment module 8 and inert gas by radiation treatment module 9.
Further, described16N radiation monitor 6, inert gas radiation detector 5 are arranged on bracket 7.
Referring to Fig. 3, the present invention also provides a kind of high temperature16N radiation monitor, including
Shield 601, setting are shielding intracorporal shielding chamber, and the insulation heat preservation layer on shielding chamber inner wall is arranged in
603, it is internally provided with detector crystal 602 in insulation heat preservation layer 603, the front end of the detector crystal 602 is provided with preposition place
Plate 605 is managed, and in the side of detector crystal 602 at least provided with the steady general source 604 of one group of sodium chloride.
The detector crystal 602 is sealed in stainless steel casing, the other side sealed insulation insulating layer of stainless steel casing
603.In the present invention, detector crystal 602 uses NaI crystal, density 3.667g/cm3；Crystal overclad layer is that A3 is stainless
Steel, density 7.8kg/cm3, top surface thickness 0.3cm, cylindrical side thickness 0.6cm；The insulation heat preservation layer 603 is rock wool or SiO2
One of aeroge, in the present invention, it is preferred to be aerosil, aerosil is leading of being currently known
The minimum solid of hot coefficient can be used as super insulating material, have stainless steel casing outside heat guard, one end welded seal is another
End is sealed with O-ring.Entire probe waterproof, heat-insulated, anti-strong motion.Thermal insulation layer SiO2The density 0.06g/cm of aeroge3, top
Face and cylindrical side thickness are 6cm；Outer shell is A3 stainless steel, density 7.8kg/cm3, top surface thickness 0.5cm, cylindrical side
Thick 0.3cm.
The shielding chamber is lead screen room thickness 50mm in 4 π lead screen rooms.
Referring to Fig. 4, the preposition processing board 604 includes pre-amplifier unit, digital multi-channel, ARM processing board, height
Press releasing unit and16Radiation treatment module 8, the pre-amplifier unit connect phototransistor, the photoelectric crystal to N on the spot
Pipe is arranged in the steady Pu Yuanchu of sodium chloride, and the digital multi-channel is separately connected pre-amplifier unit and ARM processing board, described
ARM processing board is connect with high pressure releasing unit, and high pressure releasing unit is connect with phototransistor, described16N radiation treatment on the spot
Module 8 is communicated by RS485 interface with ARM processing board.
NaI (Tl) detector output signal is directly entered 2048 number multiple tracks after the preposition amplification of certain gain
It is acquired.
ARM processing board to digital multi-channel acquisition to gamma spectrum analyzed and handled, and adjust main spy if necessary
The power supply high voltage of device is surveyed, spectrum stabilization is carried out.
Digital multiple tracks and the design of ARM processing board form a front-end processing unit, are arranged on different circuit boards
Detector output end.
Front-end processing unit by RS485 interface with16Radiation treatment module 8 is communicated N on the spot, and measured data is passed
It is defeated to be processed and displayed to radiation treatment module (LRP) on the spot.
It is described referring to Fig. 516Radiation treatment module 8 includes ARM primary processor and connect with ARM primary processor N on the spot
Display screen, 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.
16Radiation treatment module 8 (LRP) is communicated by RS485 interface with front-end processing unit N on the spot, is received and is located
The data that front-end processing unit is sent are managed, according to setting format in display measurement data, and automatically switch dimension；According to preparatory
The threshold value of setting shows or issues corresponding state instruction or sound and light alarm signal；By the requirement of program, pass through panel and keypad
Input corresponding information.
Radiation treatment module provides following measurement data, state instruction or sound and light alarm signal on the spot:
Measured value (1 tunnel analog quantity)
High level alarms (switching value)
High level alarms (switching value)
Failure and (or) Failure Alarm (switching value)
Inspection source starting or monitor are testing (switching value)
In addition, on the spot radiation treatment module can also provide surveyed radiation data a variety of average values (for example, 1min,
10min, 1h and day etc.).
When showing leak rate data, in power P >=20%FP, measurement data is shown by format, and automatic switchover amount
Guiding principle；In power P < 20%FP, total γ counting rate in measurement (0.2~2.2) MeV energy area, measurement data presses step-by-step counting format
Display.
Referring to Fig. 6 and Fig. 7, the present invention also provides a kind of inert gas radiation detectors, including
Shield 501, the inner hollow setting of the shield 501, is provided with steel bushing 502 along its inner wall, in steel bushing 502
Inner wall is embedded in heat insulation layer 503, the preferred aerosil of heat insulation layer 503, the upper and lower ends point inside heat insulation layer 503
It is not provided with main ionisation chamber locating slot 506 and difference ionization chamber locating slot 508, the main ionisation chamber locating slot 508 and differential electrical
From being respectively arranged with main ionisation chamber 505 and difference ionization chamber 504 at room locating slot 508, and main ionisation chamber 505 and difference ionization
Connector sleeve 507 is provided between room 504, the upper end of the shield 501 is provided with 505 He of gland 509 and main ionisation chamber
External preposition processing module 512 is arranged in by cable connection for difference ionization chamber 504.
The gland 509 includes the left gland and right gland being mutually butted, and docking is provided between left gland and right gland
Section 511 forms sealing structure.
The left gland and right gland are fixed by screw or bolt 510 and shield 501.
The difference ionization chamber 504 includes a measuring chamber and compensated chamber.
Detector provided by the invention is mounted at main steam line 5cm, and measurement range is 3.7 × 109Bq/m3~
3.7×1013Bq/m3, across 4 magnitudes.When radioactivity inert gas activity concentration is 3.7 × 10 in pipeline9Bq/m3When, detection
Dose equivalent at device estimates about 4.32 μ Sv/h, if considering further that the pipeline wall thickness after 50mm, actual dose rate is estimated in 0.2 μ
Sv/h is substantially at environmental exact details state.The sensitivity of ionisation chamber has to the detection level for reaching environment grade, is just able to satisfy
Field monitoring requirement.This programme difference ionization chamber 504 selects stainless steel to be made, and the size of measuring chamber and compensated chamber is about
φ 75mm × 144mm (0.5 liter), wall thickness 2.5mm fill in ionisation chamber to improve the sensitivity and detection efficient of ionisation chamber
There is the argon noble gas of 10 atmospheric pressure.
Outer γ backgrounds of detector erecting bed are 2.5 μ Gy/h, consider that external shield is reduced to environmental exact details level, electricity
Shield from room detector selects 4 Π lead screen bodies, and 4 Π lead screen body thicknesses are at least 40mm, and attenuation multiple is greater than 40
Times.
To avoid the adverse circumstances such as high temperature, high humidity from detecting required electronic circuit to the influence of detector electronic component
It does not design inside detector, but designs a preposition processing module 512, which is arranged another
Between measurement；Ionization chamber detector is connected by hard cable resistant to high temperature and preposition processing module 512.
The preposition processing module 512 includes variable gain amplifier, I/F converter unit and ARM controlling unit, institute
Variable gain amplifier is stated by connecting 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 radiation processing unit on the spot by RS485 interface.
The output signal of difference ionization chamber 504 is suitably amplified by hard cable transmission into variable gain amplifier, then
Into I/F conversion module, acquisition, the processing circuit of ARM controlling unit are entered back into.When difference ionization output electric current is larger,
ARM controls adjustable gain amplifying circuit and reduces amplification factor.
Variable gain amplifier, I/F converter, ARM processing circuit form a front end processing block, are arranged in and visit
It surveys between the different measurement of device.
By RS485 interface, radiation processing unit is communicated front-end processing unit on the spot with inert gas monitor, will
Measured data is transferred to radiation processing unit on the spot and is processed and displayed.
The radiation processing unit on the spot includes ARM primary processor and the display screen connecting with ARM primary processor, defeated
Enter keyboard, network interface and multiple ports I/O, the display screen shows measurement data by the format of setting；The keyboard is defeated
Enter corresponding information；The data that the RS485 port transmission or receiving front-end processing unit are sent；The network port is realized
With the communication and data exchange of outer computer；The port I/O receives environment or measured temperature, pressure and flow letter
Number, output alarm or switch control signal.
Technical solution disclosed in the embodiment of the present invention is described in detail above, specific reality used herein
It applies example to be expounded the principle and embodiment of the embodiment of the present invention, the explanation of above embodiments is only applicable to help
Understand the principle of the embodiment of the present invention；At the same time, for those skilled in the art, according to an embodiment of the present invention, specific
There will be changes in embodiment and application range, in conclusion the content of the present specification should not be construed as to this hair
Bright limitation.
Claims (6)
1. a kind of main steam line Radiation monitoring method, which is characterized in that including
Primary lateral secondary side 113l/d~757l/d in main steam line is set16N radiation monitor and inert gas
Radiation detector,
It is described16N radiation monitor passes through monitoring16N nucleic judges that steam generator leaks situation；
In the inert gas radiation detector monitoring main steam line85Kr and133The total activity concentration of Xe；
With16The connection of N radiation monitor16N radiation treatment module on the spot, should16Radiation treatment module is used for detecting N on the spot
's16Acquisition, data processing and the display of N nucleic signal；
The inert gas being connect with inert gas radiation detector radiation treatment module on the spot, inert gas radiation treatment on the spot
Module is used for detecting85Kr and133Acquisition, data processing and the display of the signal of the total activity concentration of Xe；
With16N radiation monitor and the computer control unit of inert gas radiation detector connection, it is described16N radiation monitor with
And inert gas radiation detector receives computer control unit and controls signal, sends measured radiation data, to speak, light report
Alert and indication signal.
2. the method according to claim 1, wherein16N is obtained after radiation treatment module data is handled on the spot16N's
Slip, specific processing method are as follows:
Heat-transfer pipe breakage in main steam generators16The slip of N and the detector measurement by the main steam header road16N decay
The gamma-ray meter digit rate of generation has following relationship:
In formula:
Q is heat-transfer pipe slip (L/h),
N is measured place16The γ radiometer digit rate (s of N-1),
C is that heat-transfer pipe slip calculates transmission coefficient (s-1·L-1H),
Transmission coefficient C and detector geometrical factor K1, detector efficiency factor K2And when heat-transfer pipe unit slip16At N sensing point
In main steam line16The gamma activity activity of N is closed, it may be assumed that
C=K1·K2·Av (6.3)
In formula:
AvWhen for heat-transfer pipe unit slip16At N sensing point in main steam line16The gamma activity activity of N,
AvIt is shown below:
Av=(Aρ/Q)·(ρv/ρp)·e-λt
(6.4)
In formula:
AρFor leakage position primary side16N radioactive activity (Bqcm-3), change with core power and leakage point position,
Q is steam flow (Lh in main steam pipe-1),
ρvFor main vapour density (kgm-3),
ρpFor coolant averag density (kgm-3),
λ is16N radiological decay constant (s-1),
T is16Transmission time (s) of the N from heat-transfer pipe leakage place to sensing point,
According to the structure size of reactor, steam generator and main steam line, physical parameter and16The Radiation monitoring point of N is joined
Number, can calculate16The transmission time of N, detector geometrical factor K1, detector efficiency factor K2；Then, according to above-mentioned various meter
Calculate transmission coefficient c；Finally, calculating heat-transfer pipe breakage in main steam generators according to Transmission system c and counting rate n16N
Slip.
3. according to the method described in claim 2, it is characterized in that,16Transmission time t of the N from heat-transfer pipe leakage place to sensing point
Detection method it is as follows:
16The detection method of transmission time of the N from leakage point to measurement point is based on the assumption that model:
(1) Small leak amount is assumed: since leakage rate is small, the steam that water leakage becomes will not be to first and second side of steam generator
Heat transfer, flow process generation significantly affect, i.e., steam generator is still in steady operational status；
(2) consistency is assumed: the movement that the water of primary side leaks into the steam that secondary side becomes is consistent with secondary side flow process；
(3) one-dimensional hypothesis: the working media in secondary side is in the tube bundle region of steam generator, steam-water separation area, dry section and master
It is all One-Dimensional flows in jet chimney；
(4) it isolates runner to assume: massless, momentum, energy variation between cold and hot two channel of steam generator secondary side；
By above-mentioned hypothesized model it is found that16N is heated two phase flow in tube bundle region, is insulation two phase flow in steam-water separation area, dry
It is single-phase steam flowing in dry area and main steam line, can be calculated with thermohydraulics program, calculation formula is as follows:
In formula: z1It is slip z to coordinate,
z2It is bend pipe area vertex z to coordinate,
wn1(z) for secondary side medium z to velocity component,
In formula: z2Z is exported to coordinate for steam-water separation area,
z1With the z in (6.5) formula2,
wn2(z) for steam-water separation area medium z to velocity component,
In formula: ρvFor vapour density,
VdFor dry section spatial volume,
Q is steam mass flow,
In formula: L is at steam generator outlet to the length between main steam line detector,
S is the section of main steam line,
ρv, Q and (6.7) formula it is same,
In above formula,
t1For in the time of tube bank heating zone transmission, i.e. admission port to the transmission time for giving water manifold, t1Because of leakage point position difference
And it is different, usual Numerical heat transfer pipe hot end, this 3 positions of cold end and bend pipe t11、t12And t13, t1For their average value；t2
For the transmission time in the transmission time in steam-water separation area, i.e., to water manifold to steam header；t3For in the transmission of drying box
Between, i.e. the transmission time that is exported to steam ring case of steam header；t4For where steam ring case exit to main steam pipe detector
The transmission time at place.
4. the method according to claim 1, wherein the inert gas radiation detector is provided with main ionisation chamber
And difference ionization chamber, main ionisation chamber and difference ionization chamber working voltage polarity on the contrary, generated current direction also on the contrary, to
It can offset to all contributive environmental exact details γ radiation of two ionisation chambers,
It is counted caused by the output electric current of ionisation chamber are as follows:
N=IKf (7.1)
In formula: n is the counting rate measured, unit s-1,
Output electric current of the I for ionisation chamber, unit pA,
KfFor power frequency conversion coefficient, unit s-1/ pA,
It, can be by formally calculating the radioactivity inert gas in main steam line after calibration obtains the sensitivity of ionisation chamber
Activity concentration:
In formula: S is ionisation chamber sensitivity, unit s-1/Bq。
5. a kind of main steam line radiation monitoring equipment, including steam generator, are arranged in the U-tube inside steam generator,
Main steam line on steam generator is set, and the steam generator is isolated with containment, which is characterized in that in master
It is provided on jet chimney16N radiation monitor and inert gas radiation detector, with16The connection of N radiation monitor16N is just
Eradiation processing module, the inert gas being connect with inert gas radiation detector radiation treatment module on the spot, with16N radiation prison
The computer control unit of device and the connection of inert gas radiation detector is surveyed, it is described16N radiation monitor and inert gas radiation
Detector receives computer control unit and controls signal, sends measured radiation data, to speak, light alarm and indication signal；
And power supply box, it is described16N radiation monitor, inert gas radiation detector, computer control unit,16N is with regard to eradiation
Processing module and inert gas radiation treatment module for power supply on the spot.
6. main steam line radiation monitoring equipment according to claim 5, which is characterized in that described16N radiation monitor,
Inert gas radiation detector is arranged on bracket.
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