CN108572382B - Method for measuring and calculating H' (0.07) in beta-gamma mixed radiation field - Google Patents

Method for measuring and calculating H' (0.07) in beta-gamma mixed radiation field Download PDF

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CN108572382B
CN108572382B CN201710137540.8A CN201710137540A CN108572382B CN 108572382 B CN108572382 B CN 108572382B CN 201710137540 A CN201710137540 A CN 201710137540A CN 108572382 B CN108572382 B CN 108572382B
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gamma
beta
monitor
radiation field
value
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CN108572382A (en
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韦应靖
方登富
陈立
崔伟
牛蒙青
冯梅
孟艳俊
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China Institute for Radiation Protection
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China Institute for Radiation Protection
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    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/02—Dosimeters
    • 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 invention belongs to the technical field of radiation monitoring, and relates to a beta-gamma mixed radiation field
Figure DDA0001241836440000011
The method of (1). The measuring and calculating method comprises the following steps: 1) by passing
Figure DDA0001241836440000012
Measurement of monitor
Figure DDA0001241836440000013
Numerical values, corrected to obtain
Figure DDA0001241836440000014
Numerical values according to correction
Figure DDA0001241836440000015
Numerically determining the directed dose equivalent rate of gamma ray contribution
Figure DDA0001241836440000016
2) By beta-spectral measurement, determination
Figure DDA0001241836440000017
Calibration factor N of monitor in beta radiation fieldβA value; 3) determination by gamma spectrometry
Figure DDA0001241836440000018
Calibration factor N of monitor in gamma radiation fieldγA value; 4) according to
Figure DDA0001241836440000019
Direct measurement of monitor, combined
Figure DDA00012418364400000110
NβAnd NγValue, the directed dose equivalent rate of the beta ray contribution is calculated
Figure DDA00012418364400000111
5)
Figure DDA00012418364400000112
And
Figure DDA00012418364400000113
adding to obtain the measured position
Figure DDA00012418364400000114
The value is obtained. The method solves the problem of the beta-gamma mixed radiation field
Figure DDA00012418364400000115
The difficulty of accurate measurement is improved
Figure DDA00012418364400000116
The accuracy of measurement and can provide powerful data support for radiation evaluation and radiation protection actions.

Description

Method for measuring and calculating H' (0.07) in beta-gamma mixed radiation field
Technical Field
The invention belongs to the technical field of radiation monitoring, and relates to a beta-gamma mixed radiation field
Figure BDA0001241836420000019
(0.07) the measurement and calculation method.
Background
With the development of nuclear energy and the wide application of nuclear technology, the weak penetrating radiation has wide harmThe method is widely applied to various fields such as nuclear industry, radiology, nuclear technology application and the like. Although radiation is in many cases more easily shielded to reduce extraneous radiation to personnel, personnel working in radiation fields where weak penetrating radiation makes a larger share and is not easily shielded, such as fuel element manufacturing plants, after-treatment plants and parts of the work site of nuclear power plants, may still be exposed to a larger dose of radiation to their extremities, skin. In order to evaluate the weak penetrating radiation condition of workers in a site with nuclear radiation, the directional dose equivalent rate of the site needs to be accurately monitored in advance
Figure BDA0001241836420000011
Numerical values. The monitoring data provides basis for decision-making of radiation protection actions, and radiation protection professionals can make decisions according to monitored places
Figure BDA0001241836420000012
The numerical value is measured, reasonable and feasible protective measures are taken, the weak penetrating radiation dose borne by staff in a radiation place is reduced, and the risk of skin burn is reduced.
The international committee for radiation and measurement (ICRU) definition of the targeted dose equivalent rate is: the directional dose equivalent H' (d, Ω) at a point in the radiation field is the dose equivalent produced by the corresponding extended field at a depth d on a radius of the ICRU sphere in the specified direction Ω. The ICRU recommends d 0.07mm for weak penetrating radiation, denoted H' (0.07).
Currently, site directed dose equivalent rates are measured
Figure BDA0001241836420000013
The instrument has poor energy response characteristics, and cannot directly measure and accurately give the radiation in the beta-gamma mixed radiation field
Figure BDA0001241836420000014
Numerical values, thus for mixed beta-gamma radiation fields
Figure BDA0001241836420000015
Has been an accurate measurement in the field of radiation monitoringA difficult problem, which is also a weak link to be solved urgently in the radiation protection field.
Disclosure of Invention
The invention aims to provide a beta-gamma mixed radiation field
Figure BDA0001241836420000016
To solve the problem of beta-gamma mixed radiation field
Figure BDA0001241836420000017
Difficulty in accurate measurement, improvement
Figure BDA0001241836420000018
The accuracy of measurement and provide powerful data support for radiation evaluation and radiation protection actions.
To achieve this, in a basic embodiment, the invention provides a mixed beta-gamma radiation field
Figure BDA0001241836420000021
The measuring and calculating method of (2), said measuring and calculating method comprising the steps of:
1) by passing
Figure BDA0001241836420000022
Measurement of monitor
Figure BDA0001241836420000023
Numerical values, corrected to obtain
Figure BDA0001241836420000024
Numerical values according to correction
Figure BDA0001241836420000025
Numerically determining the directed dose equivalent rate of gamma ray contribution
Figure BDA0001241836420000026
2) Determination by beta-spectral measurement
Figure BDA0001241836420000027
Calibration factor N of monitor in beta radiation fieldβA value;
3) determination by gamma spectrometry
Figure BDA0001241836420000028
Calibration factor N of monitor in gamma radiation fieldγA value;
4) according to
Figure BDA0001241836420000029
Direct measurement of monitor, combined
Figure BDA00012418364200000210
NβAnd NγValue, calculating the directed dose equivalent rate of the beta ray contribution
Figure BDA00012418364200000211
5)
Figure BDA00012418364200000212
And
Figure BDA00012418364200000213
adding to obtain the measured position
Figure BDA00012418364200000214
The value is obtained.
In a preferred embodiment, the present invention provides a mixed beta-gamma radiation field
Figure BDA00012418364200000215
The method for measuring and calculating, wherein the method described in step 1)
Figure BDA00012418364200000216
The performance of the monitor meets the requirements of the metrological verification regulation JJJG 393-2003 on X and gamma radiation equivalent (rate) meters and monitors for radiation protection.
In a preferred embodimentIn the scheme, the invention provides a beta-gamma mixed radiation field
Figure BDA00012418364200000217
The method for measuring and calculating in (1), wherein the correction method in step 1) comprises: for an energy response of better than + -30% in the range of 40keV to 1.5MeV and for a dose rate linearity of better than + -10% in its effective range
Figure BDA00012418364200000218
Monitor according to standard radiation field
Figure BDA00012418364200000219
Results of the monitor's verification/calibration, using
Figure BDA00012418364200000220
By multiplying the value directly measured by the monitor by a calibration factor obtained by verification/calibration, a correction of the measuring point is obtained
Figure BDA00012418364200000221
Numerical values.
In a preferred embodiment, the present invention provides a mixed beta-gamma radiation field
Figure BDA00012418364200000222
The method for measuring and calculating in (1), wherein the correction method in step 1) comprises:
for an energy response in the range 40keV to 1.5MeV of more than + -30%
Figure BDA00012418364200000223
Monitor according to
Figure BDA00012418364200000224
The result of the monitor is determined/calibrated in the X, gamma standard radiation field, and the result can be obtained
Figure BDA00012418364200000225
Calibration factor for measuring X-ray and gamma-ray radiation fields with different energies by monitorA seed;
according to the field gamma measurement spectrum, the energy characteristics of the measured gamma ray can be known, and the energy point can be found in the standard radiation field calibration result
Figure BDA00012418364200000226
The calibration factor of the monitor measurements is,
Figure BDA00012418364200000227
the direct measurement value of the monitor being multiplied by the calibration factor to obtain a correction of the measurement point
Figure BDA00012418364200000228
Numerical values.
In a preferred embodiment, the present invention provides a mixed beta-gamma radiation field
Figure BDA00012418364200000229
Wherein the correction in step 1) is made when the energy of the gamma-rays emitted by the radionuclide in the beta-gamma mixed radiation field is above 40keV
Figure BDA00012418364200000230
The numerical value is
Figure BDA00012418364200000231
The value is obtained.
In a preferred embodiment, the present invention provides a mixed beta-gamma radiation field
Figure BDA00012418364200000232
The method for measuring and calculating, wherein N is described in the step 2)βThe determination method of the value is as follows:
measuring a beta radiation spectrum in a beta-gamma mixed radiation field by using a beta spectrometer, measuring a spectrum 1 when a probe is exposed, measuring a spectrum 2 at the same position when 5mm of aluminum is added in front of the probe, and respectively correcting the spectrum 1 and the spectrum 2 in dead time and subtracting to obtain a pure beta ray fluence spectrum of a measuring point;
then the pure beta ray fluence spectrumComparing the measured spectrum with that of a beta spectrometer in a pure beta radiation field, finding out a standard reference spectrum similar to that of a beta-gamma mixed radiation field, and taking a calibration factor, namely N, in the beta radiation field corresponding to the standard reference spectrumβThe value is obtained.
In a preferred embodiment, the invention provides a mixed beta-gamma radiation field
Figure BDA0001241836420000031
Wherein the pure beta radiation field is90Sr-90Y、85Kr and/or147The radiation field of Pm.
In a preferred embodiment, the present invention provides a mixed beta-gamma radiation field
Figure BDA0001241836420000032
The method for measuring and calculating, wherein N is described in the step 3)γThe determination method of the value is as follows:
measuring the gamma-ray energy spectrum of the beta-gamma mixed radiation field by using a gamma spectrometer, or measuring the gamma-ray energy spectrum after sampling the beta-gamma mixed radiation field on site, and combining the energy of the gamma-ray of the measured field
Figure BDA0001241836420000033
The monitor calibrates the result in the standard X, gamma radiation field, finds out the calibration factor of the energy point close to the site in the standard radiation field, and the calibration factor is
Figure BDA0001241836420000034
N of monitor at the actual measurement pointγThe value is obtained.
In a preferred embodiment, the present invention provides a mixed beta-gamma radiation field
Figure BDA0001241836420000035
The method of (1), wherein the measurement is carried out in the range of 40keV to 1.5MeV
Figure BDA0001241836420000036
The monitor has good response to gamma ray energyAt + -30%, if the gamma radiation energy of the measured field is of various types and the gamma ray energy is in the range of 40keV-1.5MeV, it can be selected
Figure BDA0001241836420000037
Monitor is arranged at137The calibration factor given by calibration in the Cs radiation field is used as N for calculationγThe value is obtained.
In a preferred embodiment, the invention provides a mixed beta-gamma radiation field
Figure BDA0001241836420000038
The method of measuring and calculating, wherein in step 4)
Figure BDA0001241836420000039
The calculation method of (2) is shown in the following formula (3):
Figure BDA00012418364200000310
wherein M is
Figure BDA00012418364200000311
The monitor measures the value directly.
The invention has the beneficial effect that the beta-gamma mixed radiation field of the invention is utilized
Figure BDA00012418364200000312
The method can be used for the directional dose equivalent rate measurement of nuclear facility sites, particularly the measurement of the directional dose equivalent rate of sites emitting gamma rays and having higher beta radiation, and solves the problem of the beta-gamma mixed radiation field
Figure BDA00012418364200000313
Difficulty in accurate measurement, improvement
Figure BDA00012418364200000314
The accuracy of measurement and can provide powerful data support for radiation evaluation and radiation protection actions.
Drawings
FIG. 1 is an exemplary beta-gamma hybrid radiation field of the present invention
Figure BDA0001241836420000041
Is a flow chart of the measurement and calculation method.
FIG. 2 is a graph of the conversion coefficients of photon fluence to ambient dose equivalents and directed dose equivalents as referred to in the detailed description.
Fig. 3 is a gamma spectrum of a cold end seal liner wipe sample of a nuclear power plant 1SG (steam generator) in an example of an application of the embodiment.
Fig. 4 is a pure beta-ray fluence spectrum of a seal liner wipe sample at the cold end of a nuclear power plant 1SG (steam generator) in an example of an application of an embodiment.
FIG. 5 is an exemplary embodiment of an exemplary application85Beta fluence spectrum of kr standard radiation field.
Detailed Description
The following further describes embodiments of the present invention with reference to the accompanying drawings.
Exemplary beta-gamma mixed radiation field of the invention
Figure BDA0001241836420000042
The method of measurement and calculation of (2) is shown in FIG. 1. Due to the same
Figure BDA0001241836420000043
The response of the monitor to beta rays and gamma rays is different, and the monitor cannot be directly used
Figure BDA0001241836420000044
The monitor can accurately measure the beta-gamma mixed field
Figure BDA0001241836420000045
Values, in the processing of measurement data, based on
Figure BDA0001241836420000046
The values directly measured by the monitor need to be calculated by gamma ray and beta ray pair respectively
Figure BDA0001241836420000047
The contribution of (a), namely:
Figure BDA0001241836420000048
the method comprises the following steps:
1) peripheral dose equivalent rate
Figure BDA0001241836420000049
Numerical measurement determination
With better energy response and dose rate linearity
Figure BDA00012418364200000410
The monitor is verified/calibrated in X and gamma standard radiation fields, and the performance of the monitor meets the requirements of JJJG 393-2003. For in-situ beta-gamma mixed radiation field
Figure BDA00012418364200000411
Numerical values, using after verification/calibration
Figure BDA00012418364200000412
The monitor measures the measurement, and the corrected measurement point can be calculated by multiplying the directly measured value by the calibration factor given in the certificate of verification/calibration according to the verification/calibration result in the standard radiation field
Figure BDA00012418364200000413
Numerical values. If it is not
Figure BDA00012418364200000414
If the energy response of the measuring instrument is slightly poor and the field gamma radiation energy is known, the energy response can be further corrected according to the result of the verification/calibration certificate.
2)
Figure BDA00012418364200000415
Numerical determination
For gamma rays with energies above 300keV, as shown in fig. 2, the international radiation unit is consistent with the conversion coefficients reported by the measurement commission as ICRU43, which reports fluence to ambient dose equivalents and fluence to directed dose equivalents H' (0.07); for gamma rays with energies below 300keV, the conversion coefficients differ slightly. However, the air kerma K according to the monoenergetic photon given in GB/T12162.3aTo the surrounding dose equivalent H*(10) And a conversion factor for the directed dose equivalent H' (0.07), as shown in Table 1, in the range of 30keV to 300keV, and a ratio of the two in the range of 0.9 to 1.1, indicating the same point in the radiation field around which the dose equivalent H is present*(10) And the agreed true value for the targeted dose equivalent H' (0.07) do not differ by more than 10%. The energy of gamma rays emitted by the radionuclide in the actual nuclear facility site is basically above 30 keV. Therefore, the directional dose equivalent rate of the gamma ray contribution is calculated
Figure BDA0001241836420000051
When, the following relationship can be considered to exist:
Figure BDA0001241836420000052
therefore, only the field measurement is needed and the correction is carried out through the calibration factor, and the measurement point is accurately obtained
Figure BDA0001241836420000053
The measured place can be obtained by value
Figure BDA0001241836420000054
The value is obtained.
TABLE 1 monoenergetic photons Ka-H*(10) And Ka-H' (0.07) conversion factor
Figure BDA0001241836420000055
3) Determination by beta-spectral measurements
Figure BDA0001241836420000056
Calibration factor N of monitorβ
And (3) measuring a field beta radiation spectrum by using a beta spectrometer, and if the field dosage rate is very high, wiping, sampling and measuring. During measurement, the spectrum 1 is measured when the probe is exposed, and because the beta spectrometer has certain response to the gamma rays, the beta rays and the gamma rays in the spectrum contribute together during fluence spectrum. Spectrum 2 was measured at the same location with 5mm aluminum (enough to absorb all beta rays) in front of the probe, spectrum 2 being the fluence spectrum of pure gamma rays. And (3) performing dead time correction and subtraction on the spectrum 1 and the spectrum 2 respectively to obtain the fluence spectrum of the pure beta ray of the measuring point. After the beta fluence spectrum is obtained, the beta fluence spectrum is compared with a beta spectrometer in a pure beta radiation field (generally, the beta fluence spectrum is measured in a pure beta radiation field)90Sr-90Y、85Kr、147Pm), and finding out a standard reference spectrum similar to the field measurement spectrum.
Figure BDA0001241836420000061
When the measurement result of the monitor is calculated, the calibration factor N of the monitor isβGet it right
Figure BDA0001241836420000062
And calibrating the result of the monitor in the beta radiation field corresponding to the standard reference spectrum.
4) Determination by gamma spectrometry
Figure BDA0001241836420000063
Calibration factor N of monitorγ
To pair
Figure BDA0001241836420000064
The monitor is calibrated in the standard X and gamma radiation fields to determine
Figure BDA0001241836420000065
The monitor is linear in energy response characteristic and dose rate to gamma radiation and gives a calibration factor. When the radiation field measurement is carried out, a gamma spectrometer can be used for measuring the field gamma energy spectrum, and a sampling measurement method can also be adopted for measuring the energy spectrumAfter the energy characteristics of the gamma rays in the field, combining
Figure BDA0001241836420000066
The monitor calibrates the result in the standard X and gamma radiation fields to determine
Figure BDA0001241836420000067
N used by the monitor at the actual measurement pointγThe value is obtained. If it is not
Figure BDA0001241836420000068
The monitor responds well to gamma ray energy (in the range of 40keV to 1.5MeV,
Figure BDA0001241836420000069
the response of the monitor to gamma ray energy is better than +/-30 percent), and the gamma ray energy on site has various types, and the monitor is generally used137The calibration factor given by calibration in the Cs radiation field is taken as NγThe value is obtained.
5)
Figure BDA00012418364200000610
Numerical determination
Directed dose equivalent rate for beta ray contribution in beta-gamma mixed field
Figure BDA00012418364200000611
Measurement results, need to be taken from
Figure BDA00012418364200000612
The contribution of gamma-ray is deducted from the direct measurement value of the monitor, the dosage rate of the residual beta-ray contribution is multiplied by the calibration factor in the beta radiation field, and then the measurement point can be obtained
Figure BDA00012418364200000613
The value is obtained. Specifically, the following formula is calculated:
Figure BDA00012418364200000614
wherein: m is
Figure BDA00012418364200000615
Direct measurement of the monitor; n is a radical of hydrogenγIs composed of
Figure BDA00012418364200000616
A calibration factor of the monitor in a gamma radiation field; n is a radical ofβIs composed of
Figure BDA00012418364200000617
The measurement instrument calibrates the factor in the beta radiation field.
In the formula (3)
Figure BDA00012418364200000618
M、
Figure BDA00012418364200000619
The units of the three are the same and are mu Sv/h or mSv/h. 6)
Figure BDA00012418364200000620
Numerical determination
According to the calculation results of the formula (2) and the formula (3), the sum of the formula (1) is used for calculating the beta-gamma mixed radiation field of the measuring point
Figure BDA00012418364200000621
The value is obtained.
In the above exemplary beta-gamma mixed radiation field of the present invention
Figure BDA00012418364200000622
The specific application of the measuring and calculating method is as follows:
sealing lining plate surface for 1SG (1# steam generator) cold end during overhaul of certain nuclear power station
Figure BDA00012418364200000623
The values are measured, and the specific measurement calculation process is as follows:
1) peripheral dose equivalent rate
Figure BDA0001241836420000071
Numerical measurement determination
1 RADIAGEM2000 type X and gamma dose rate instrument is selected, and the energy response of the instrument is better than +/-16% within the range of 40keV-1.5MeV through measurement; dose rates are linear better than + -10% over the range of 1 μ Sv/h-100 mSv/h. Use of the
Figure BDA0001241836420000072
The monitor measures the reading of the 1SG cold-end sealing lining plate as 268 MuSv/h, and a gamma spectrum of the 1SG cold-end sealing lining plate wiping sample measured by using a gamma spectrometer is shown in figure 3, and as can be seen from figure 3, the energy of gamma rays emitted by radioactive nuclides on the sealing lining plate is mainly more than 200 keV. Thus, the position
Figure BDA0001241836420000073
The measured value of the monitor can be directly used137Correction of the calibration factor for Cs by
Figure BDA0001241836420000074
Monitor is arranged at137As can be seen from the calibration results in the Cs standard radiation field, the calibration factor is 1.02 when the dose rate is near 268. mu. Sv/h. The 1SG cold end sealing the liner plate surface
Figure BDA0001241836420000075
The corrected value was 268 × 1.02 ═ 273 μ Sv/h.
2)
Figure BDA0001241836420000076
Numerical determination
According to the gamma spectrum measurement result of the wiping sample of the 1SG cold-end sealing lining plate, the energy of gamma rays emitted by the radioactive nuclide on the equipment is above 40 keV. Therefore, it can be calculated according to the formula (2)
Figure BDA0001241836420000077
Figure BDA0001241836420000078
3) Determination by beta-spectral measurements
Figure BDA0001241836420000079
Calibration factor N of monitorβ
The method is characterized in that a beta spectrometer is used for measuring a beta radiation spectrum of a 1SG cold-end sealing lining plate wiping sample, the spectrum 1 is measured when a probe is exposed, and the beta ray and the gamma ray contribute together during the fluence spectrum of the spectrum because the beta spectrometer also has certain response to the gamma ray. Spectrum 2 was measured at the same location with 5mm aluminum (enough to absorb all beta rays) in front of the probe, spectrum 2 being the fluence spectrum of pure gamma rays. The dead time correction is performed on the spectrum 1 and the spectrum 2 respectively, and the dead time correction is subtracted, so that the fluence spectrum of the pure beta ray at the measuring point can be obtained, and is shown in fig. 4. After the beta fluence spectrum is obtained, the beta fluence spectrum is compared with a beta spectrometer in a pure beta radiation field (generally, the beta fluence spectrum is measured in a pure beta radiation field)90Sr-90Y、85Kr、147Pm), finding out the on-site measured spectrum and85the energy distribution ranges of the Kr standard spectra (as shown in fig. 5) are similar. Then
Figure BDA00012418364200000710
When the measurement result of the monitor is calculated, the calibration factor N of the monitor isβIs selected
Figure BDA00012418364200000711
Monitor is arranged at85Calibration factor 1.02 in Kr standard radiation field.
4) Determination by gamma spectrometry
Figure BDA00012418364200000712
Calibration factor N of monitorγ
To pair
Figure BDA00012418364200000713
The monitor is calibrated in standard X and gamma radiation fields, and the energy response of the monitor is better than +/-30% within the range of 60keV-1.5 MeV; dose rates are better than + -5% linear over the range of 1. mu.Sv/h-100 mSv/h. Gamma spectra from 1SG cold end seal liner wipe (see fig. 3) on the seal linerThe gamma ray energy emitted by the radionuclide is mainly above 200 keV. Thus, the position
Figure BDA0001241836420000081
The measured value of the monitor can be directly used137Correction of the calibration factor for Cs by
Figure BDA0001241836420000082
Monitor is arranged at137The calibration result in the Cs standard radiation field shows that the calibration factor is 1.96 when the dosage rate is close to 268 MuSv/h. Calculating 1SG cold end seal liner surface
Figure BDA0001241836420000083
When value, N is selectedγThe value was 1.96.
5)
Figure BDA0001241836420000084
Numerical determination
For a beta-gamma mixed field emitted by a 1SG cold-end sealed lining plate,
Figure BDA0001241836420000085
the monitor directly measures M to be 2.98mSv/h, wherein the directional dose equivalent rate of the beta ray contribution
Figure BDA0001241836420000086
Can be calculated by the formula (3), i.e.
Figure BDA0001241836420000087
Figure BDA0001241836420000088
6)
Figure BDA0001241836420000089
Numerical determination
Calculated according to the above
Figure BDA00012418364200000810
By adding the two, the 1SG cold end sealing liner surface can be determined
Figure BDA00012418364200000811
The value 273+2897 ═ 3170 μ Sv/h.
7) Measurement uncertainty assessment
For field measurement and calculation
Figure BDA00012418364200000812
The numerical value is calculated by using a formula (1), and the uncertainty of the numerical value is mainly derived from the following parts:
(1) measuring
Figure BDA00012418364200000813
Time, the uncertainty introduced by the calibration factor N: from the calibration certificate, U-7% (k-2) is derived, so that the uncertainty introduced by the calibration factor into class B is U1＝3.5％；
(2) Measuring
Figure BDA00012418364200000814
Time, the uncertainty introduced by the calibration factor N: from the calibration certificate, U-7% (k-2) is derived, so that the uncertainty introduced by the calibration factor into class B is U2＝3.5％；
(3) Uncertainty introduced by field measurement data repeatability: according to the field monitoring data, the repeatability of the instrument monitoring data can be less than 1%. 6 readings are measured on site, so that the range of A-type uncertainty repeatedly introduced by field measurement data can be obtained
Figure BDA00012418364200000815
(4) Uncertainty introduced by the instrument linear response: according to
Figure BDA00012418364200000816
At 1. mu. Sv.h-1-100mSv·h-1Within the range, the relative intrinsic error of the instrument is within ± 5%. Assuming measured dataThe uncertainty introduced by instrument dose rate linearity is
Figure BDA00012418364200000817
(5)
Figure BDA00012418364200000818
Introduced uncertainty: in the calculation of
Figure BDA00012418364200000819
When using
Figure BDA00012418364200000820
The uncertainty of the measured value of (2) mainly comprises the following two parts: calibration factor N-introduced uncertainty: from the calibration certificate, U-5% (k-2) is derived, so that the uncertainty introduced by the calibration factor into class B is U52.5 percent; uncertainty introduced by field measurement data repeatability: due to the fact that repeatability of the measuring instrument is different under the conditions of different dosage rates, according to field monitoring data, repeatability of the monitoring data can reach 9% at most when the dosage rate is low. The actual field measurement is carried out for 6 times, so that the range of the A-type uncertainty introduced by the repeatability of the field measurement data is obtained
Figure BDA0001241836420000093
Figure BDA0001241836420000094
Synthetic uncertainty: the uncertainty components of the above six parts can be known in the field
Figure BDA0001241836420000091
Synthetic standard uncertainty of monitoring data
Figure BDA0001241836420000092
Its relative expansion uncertainty U is 15% (k 2).
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The foregoing examples or embodiments are merely illustrative of the present invention, which may be embodied in other specific forms or in other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims are also intended to be included within the scope of the invention.

Claims (5)

1. In a beta-gamma mixed radiation field
Figure FDA0003569999750000011
The measuring and calculating method is characterized by comprising the following steps:
1) by passing
Figure FDA0003569999750000012
Measurement of monitor
Figure FDA0003569999750000013
Numerical values, corrected to obtain
Figure FDA0003569999750000014
Numerical values according to correction
Figure FDA0003569999750000015
Numerically determining the directed dose equivalent rate of gamma ray contribution
Figure FDA0003569999750000016
2) Determination by beta-spectral measurement
Figure FDA0003569999750000017
Calibration factor N of monitor in beta radiation fieldβA value;
3) determination by gamma spectrometry
Figure FDA0003569999750000018
Calibration factor N of monitor in gamma radiation fieldγA value;
4) according to
Figure FDA0003569999750000019
Direct measurement of monitor, combined
Figure FDA00035699997500000110
NβAnd NγValue, calculating the directed dose equivalent rate of the beta ray contribution
Figure FDA00035699997500000111
5)
Figure FDA00035699997500000112
And
Figure FDA00035699997500000113
adding to obtain the measured position
Figure FDA00035699997500000114
The value of the one or more of the one,
wherein:
n described in step 2)βThe determination method of the value is as follows:
measuring a beta radiation spectrum in a beta-gamma mixed radiation field by using a beta spectrometer, measuring a spectrum 1 when a probe is exposed, measuring a spectrum 2 at the same position when 5mm of aluminum is added in front of the probe, and respectively correcting the spectrum 1 and the spectrum 2 in dead time and subtracting to obtain a pure beta ray fluence spectrum of a measuring point;
then comparing the pure beta ray fluence spectrum with the spectrum measured by a beta spectrometer in a pure beta radiation field,finding out a standard reference spectrum similar to the measured spectrum of the beta-gamma mixed radiation field, and taking a calibration factor in the beta radiation field corresponding to the standard reference spectrum, namely NβThe value of the sum of the values,
the pure beta radiation field is90Sr-90Y、85Kr and/or147The radiation field of the Pm,
n described in step 3)γThe determination method of the value is as follows:
measuring the gamma-ray energy spectrum of the beta-gamma mixed radiation field by using a gamma spectrometer, or measuring the gamma-ray energy spectrum after sampling the beta-gamma mixed radiation field on site, and combining the energy of the gamma-ray of the measured field
Figure FDA00035699997500000115
The monitor calibrates the result in the standard X, gamma radiation field, finds out the calibration factor of the energy point close to the site in the standard radiation field, and the calibration factor is
Figure FDA00035699997500000116
N of monitor at the actual measurement pointγThe value of the sum of the values,
in the range of 40keV to 1.5MeV when
Figure FDA00035699997500000117
The response of the monitor to gamma-ray energy is better than +/-30%, and if the gamma-ray energy of the detected place is of various types and the gamma-ray energy is in the range of 40keV-1.5MeV, the monitor can be selected
Figure FDA00035699997500000118
Monitor is arranged at137The calibration factor given by calibration in the Cs radiation field is used as N for calculationγThe value of the one or more of the one,
in step 4)
Figure FDA00035699997500000119
The calculation method of (2) is shown in the following formula (3):
Figure FDA0003569999750000021
wherein M is
Figure FDA0003569999750000022
The monitor measures the value directly.
2. The method of claim 1, wherein: described in step 1)
Figure FDA0003569999750000023
The performance of the monitor meets the requirements of a metrological verification regulation JJJG 393-2003.
3. The method for measuring and calculating according to claim 1, wherein the correction in step 1) is: for an energy response of better than + -30% in the range of 40keV to 1.5MeV and for a dose rate linearity of better than + -10% in its effective range
Figure FDA0003569999750000024
Monitor according to standard radiation field
Figure FDA0003569999750000025
Results of the monitor's verification/calibration, using
Figure FDA0003569999750000026
By multiplying the value directly measured by the monitor by a calibration factor obtained by verification/calibration, a correction of the measuring point is obtained
Figure FDA0003569999750000027
Numerical values.
4. The method for measuring and calculating according to claim 1, wherein the correction in step 1) is:
more than + -30% for energy response in the range of 40keV to 1.5MeVIs
Figure FDA0003569999750000028
Monitor according to
Figure FDA0003569999750000029
The result of the monitor is determined/calibrated in the X, gamma standard radiation field, and the result can be obtained
Figure FDA00035699997500000210
The monitor measures the calibration factors of X-ray and gamma-ray radiation fields with different energies;
according to the field gamma measurement spectrum, the energy characteristics of the measured gamma ray can be known, and the energy point can be found in the standard radiation field calibration result
Figure FDA00035699997500000211
The calibration factor of the monitor measurements is,
Figure FDA00035699997500000212
the direct measurement value of the monitor being multiplied by the calibration factor to obtain a correction of the measurement point
Figure FDA00035699997500000213
Numerical values.
5. The method of claim 1, wherein: corrected when the energy of gamma rays emitted by radionuclide in the beta-gamma mixed radiation field in the step 1) is above 40keV
Figure FDA00035699997500000214
The numerical value is
Figure FDA00035699997500000215
The value is obtained.
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