CN115620930A - Floating type nuclear power plant beta ray and gamma ray online monitoring method and system - Google Patents
Floating type nuclear power plant beta ray and gamma ray online monitoring method and system Download PDFInfo
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Abstract
The invention discloses a method and a system for on-line monitoring of beta rays and gamma rays of a floating nuclear power plant, which relate to the technical field of radiation monitoring, are used for monitoring ray signals by designing a reasonable range position on the basis of the range radiated by a ray source, designing an acquisition space on the basis of different ranges of beta ray signals and gamma ray signals, and deducting gamma ray interference signals in the process of acquiring the beta ray signals by utilizing the different ranges of the beta ray signals and the gamma ray signals, thereby effectively improving the monitoring precision; the online monitoring system of the scheme integrates the detection assembly in the measurement pipe fitting to be connected with the process pipeline to be measured, realizes effective acquisition of low-level beta and gamma ray signals possibly existing in inert gas or liquid of the pipeline based on a direct contact measurement method, reduces interference of gamma rays on beta ray measurement through a compensation measurement technology, and simultaneously realizes real-time measurement of gamma rays.
Description
Technical Field
The invention relates to the technical field of radiation monitoring, in particular to a method and a system for online monitoring of beta rays and gamma rays of a floating nuclear power plant
Background
In order to find whether a reactor system and equipment of a floating nuclear power plant are effectively and normally operated from the level of radiation, real-time and effective radioactivity monitoring is needed to be carried out on process fluid in a pipeline, but because the activity level of inert gas or liquid in part of pipelines is lower, the decay branch ratio is small and the characteristic ray energy is lower, the detection efficiency is lower during online tube-side measurement, and the requirement on the detection sensitivity of low-level beta and gamma rays is difficult to meet; in addition, the sampling pipeline in the off-line sampling monitoring method brings about the influence of complexity and uncertainty.
Disclosure of Invention
The technical problem to be solved by the invention is as follows: the traditional online tube-side monitoring method has low efficiency, is easily influenced by other interference signals and is difficult to meet the requirements on low-level beta and gamma ray detection sensitivity, and the offline sampling monitoring method brings about the influences of complexity and uncertainty; the scheme provides a method and a system for monitoring beta rays and gamma rays of a floating nuclear power plant on line.
The invention is realized by the following technical scheme:
the scheme provides a floating type nuclear power plant beta ray and gamma ray on-line monitoring method, which comprises the following steps:
the method comprises the following steps: simultaneously acquiring beta ray signals and gamma ray signals in a first space, a second space and a third space of a radiation field of a radiation source: wherein, beta ray signals and gamma ray signals are simultaneously collected in a first space, gamma ray signals are collected in a second space, and gamma ray signals are collected in a third space; the centers of the first space, the second space and the third space are sequentially distributed along a ray L, the ray L is a perpendicular line of a pipeline where the ray source is located, the first space is closest to the pipeline where the ray source is located, and the first space penetrates through the pipe wall of the pipeline where the ray source is located;
step two: deducting a gamma ray interference signal from a beta ray signal and a gamma ray signal acquired by a first space based on a gamma ray signal acquired by a second space to obtain the dose rate of the beta ray; a gamma-ray dose rate is calculated based on the gamma-ray signals acquired in the third space.
The working principle of the scheme is as follows: the traditional online tube-side monitoring method is that a collecting device for different ray signals is directly arranged beside a pipeline for direct collection, other interference signals around the pipeline in the collecting process can influence the monitoring precision, and the requirement of low-level beta and gamma ray detection sensitivity is difficult to meet; the scheme is based on the range radiated by a ray source, ray signals are monitored through the reasonable range position, the acquisition space is designed based on different ranges of beta ray signals and gamma ray signals, gamma ray interference signals are deducted by the different ranges of the beta ray signals and the gamma ray signals in the process of acquiring the beta ray signals, and the monitoring precision is effectively improved.
In the process that a ray source radiates and penetrates through a first space, a second space and a third space in sequence, a beta ray signal and a gamma ray signal are simultaneously acquired in the first space, due to the fact that the range of beta ray radiation is limited, the gamma ray signal is acquired in the second space to compensate the gamma ray signal acquired in the first space so as to obtain an accurate beta ray radiation signal, when the ray source radiates to the third space, only the gamma ray signal basically remains, and at the moment, the gamma ray signal can be accurately acquired in the third space.
The further optimization scheme is that the beta ray signal and the gamma ray signal are scintillation light signals.
The further optimization scheme is that the second step comprises the following substeps:
s21, performing photoelectric conversion on the scintillation light signals collected in the first space to obtain pulse signals A1, performing photoelectric conversion on the scintillation light signals collected in the second space to obtain pulse signals A2, and triggering the pulse signals A1 and A2 to output TTL pulse signals A1 and A2 with the same duration respectively;
s22, acquiring trigger time T of two groups of TTL pulse signals A1 And T A2 Taking TTL pulse signal A1 as gate signal to calculate T A1 And T A2 The difference Δ T of (d);
and S23, if the delta T is smaller than the threshold value T, subtracting the TTL pulse signal A2 from the TTL pulse signal A1, and then calculating the dosage rate of the beta ray, otherwise, directly calculating the dosage rate of the beta ray based on the TTL pulse signal A1.
The scheme also provides a floating type nuclear power plant beta ray and gamma ray online monitoring system which is used for realizing the scheme, and the floating type nuclear power plant beta ray and gamma ray online monitoring method comprises the following steps:
a detector assembly for simultaneously acquiring beta-ray signals and gamma-ray signals in a first space, a second space and a third space of a radiation field of a radiation source: wherein, beta ray signals and gamma ray signals are simultaneously collected in a first space, gamma ray signals are collected in a second space, and gamma ray signals are collected in a third space; the centers of the positions of the first space, the second space and the third space are sequentially arranged along a ray L, the ray L is a perpendicular line of a flowing pipeline of the ray source, the first space is closest to the pipeline where the ray source is located, and the first space penetrates through the pipe wall of the pipeline where the ray source is located;
the calculation module is used for deducting the gamma-ray interference signal from the beta-ray signal and the gamma-ray signal acquired by the first space based on the gamma-ray signal acquired by the second space to obtain the dosage rate of the beta-ray; calculating a gamma-ray dose rate based on the gamma-ray signals acquired in the third space;
the measuring pipe is the same as a flow pipeline which bears the detector assembly and serves as a ray source;
and the shielding assembly is wrapped on the periphery of the flow pipeline where the probe assembly is positioned and used for shielding the probe assembly.
The measuring pipe fitting and the shielding component form a low-background large-capacity measuring chamber, and the detection sensitivity of the low-level radioactive medium is improved.
The detector assembly is cylindrical, is arranged perpendicular to the measuring pipe fitting and penetrates through the pipe wall of the measuring pipe fitting to directly contact the ray source; the shielding assembly wraps outside the detector assembly, and meanwhile the detector assembly penetrates through the pipe wall, towards which the measuring pipe fitting points, to be provided with the shielding assembly.
The modular line monitoring system is compact in structure and integrated in combination design, is convenient to install and detach in the shielding assembly, and can realize mechanical positioning of the detector assembly through the connector structure inside the shielding assembly.
In a further optimized scheme, the detector assembly comprises: the detector comprises a first high beta/gamma plastic scintillator detector, a second high beta/gamma plastic scintillator detector, a high gamma plastic scintillator detector and an insulating material;
the space occupied by the first beta/gamma plastic scintillator detector, the second beta/gamma plastic scintillator detector and the gamma plastic scintillator detector respectively form a first space, a second space and a third space; the insulating material wraps the outer surface of the cylindrical structure, and the insulating material corresponding to the first beta/gamma plastic scintillator detector penetrates through the pipe wall of the measuring pipe fitting to directly contact the ray source.
The further optimization scheme is that the photoelectric conversion device further comprises a photoelectric conversion module, and the first high beta/gamma plastic scintillator detector, the second high beta/gamma plastic scintillator detector and the high gamma plastic scintillator detector are respectively connected with one photoelectric conversion module.
The further optimization scheme is that the thicknesses of the first high beta/gamma plastic scintillator detector and the second high beta/gamma plastic scintillator detector are consistent, and the thickness of the high gamma plastic scintillator detector is larger than that of the first high beta/gamma plastic scintillator detector.
The further optimization scheme is that the thickness of the high-gamma plastic scintillator detector is at least 50 times of that of the first high-beta/gamma plastic scintillator detector.
The further optimization scheme is that the shielding assembly 3 is prepared from lead alloy, and polyethylene material is filled between the detector assembly and the shielding assembly.
The shielding body assembly is prepared from lead alloy with a certain thickness, and the shielding assembly wrapped on the outer surface of the detector assembly is of a cylindrical structure, so that effective radiation shielding of the detector assembly can be realized, and the sufficient strength of the detector assembly is also ensured. Meanwhile, a high-temperature-resistant high-density polyethylene material is filled between the detector assembly and the shielding body assembly, and the upper part, the lower part and the side surface of the shielding assembly are insulated by adopting ceramic. The shield of the measuring pipe should completely wrap the expansion area of the measuring pipe, so as to form a low-background measuring environment and reduce the interference of external rays on a measuring object.
A first beta/gamma plastic scintillator detector (adopting a high beta/gamma thin plastic scintillator detector) at the front end of the detector assembly is sensitive to both beta rays and gamma rays, when the detector is used for measurement in a beta and gamma ray radiation field, the scintillator detector outputs the total number of scintillation photons after the beta rays and the gamma rays are acted with a scintillator, and a photoelectric conversion module (adopting an SiPM photoelectric assembly) is used for performing photoelectric conversion and amplification on scintillation light in real time. Due to the limited range of the beta ray, the second beta/gamma plastic scintillator detector (which adopts the same high beta/gamma thin plastic scintillator detector as the first beta/gamma plastic scintillator detector) will be sensitive only to the gamma ray, i.e. the number of the scintillation photons after the gamma ray and the scintillator are acted is output, and the gamma ray compensation of the first high beta/gamma thin plastic scintillator detector can be realized.
The high-gamma plastic scintillator detector can effectively attenuate gamma rays with larger energy due to larger thickness, and transmits generated scintillation light to the photoelectric conversion module, thereby realizing photoelectric conversion and amplification treatment of the high-energy gamma rays.
Compared with the prior art, the invention has the following advantages and beneficial effects:
the invention provides a floating nuclear power plant beta-ray and gamma-ray online monitoring method, which is characterized in that based on the radiation range of a ray source, ray signal monitoring is carried out by designing a reasonable range position, an acquisition space is designed based on different ranges of beta-ray signals and gamma-ray signals, and gamma-ray interference signals are deducted by using the different ranges of the beta-ray signals and the gamma-ray signals in the process of acquiring the beta-ray signals, so that the monitoring precision is effectively improved.
The invention provides a floating type nuclear power plant beta-ray and gamma-ray on-line monitoring system.A detection assembly is fused in a measurement pipe fitting and is connected with a process pipeline to be measured through the measurement pipe fitting, so that the effective acquisition of low-level beta and gamma-ray signals possibly existing in inert gas or liquid of the pipeline is realized on the basis of a direct contact measurement method, the interference of gamma-ray on beta-ray measurement is reduced through a compensation measurement technology, and meanwhile, the real-time measurement of gamma-ray is realized; on the other hand, the system replaces the traditional photomultiplier based on the photoelectric conversion module, improves the light collection efficiency, enhances the rigidity and the working stability of the device, reduces the weight and the size of the device, and can meet the installation space and the technical requirements of floating nuclear power plant equipment.
Drawings
In order to more clearly illustrate the technical solutions of the exemplary embodiments of the present invention, the drawings that are required to be used in the embodiments will be briefly described below, it should be understood that the following drawings only illustrate some embodiments of the present invention and therefore should not be considered as limiting the scope, and that for those skilled in the art, other related drawings can be obtained from these drawings without inventive effort. In the drawings:
FIG. 1 is a schematic flow chart of a method for online monitoring beta rays and gamma rays of a floating nuclear power plant;
FIG. 2 is a schematic structural diagram of a floating nuclear power plant beta-ray and gamma-ray online monitoring system;
FIG. 3 is a schematic cross-sectional view of a detector assembly construction;
fig. 4 is a schematic diagram of the online monitoring principle of beta rays and gamma rays of a floating nuclear power plant.
In the drawings:
the device comprises a detector assembly 1, a first high beta/gamma plastic scintillator detector 11, a second high beta/gamma plastic scintillator detector 12, a high gamma plastic scintillator detector 13, an insulating material 14, a photoelectric conversion module 15, a signal line centralized processing module 16, a measuring pipe 2, a shielding assembly 3, a connector 4 and a signal line 5.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
In order to find whether a reactor system and equipment of a floating nuclear power plant are effectively and normally operated from the level of radiation, real-time and effective radioactivity monitoring is needed to be carried out on process fluid in a pipeline, but because the activity level of inert gas or liquid in part of pipelines is lower, the decay branch ratio is small and the characteristic ray energy is lower, the detection efficiency is lower during online tube-side measurement, and the requirement on the detection sensitivity of low-level beta and gamma rays is difficult to meet; in addition, the sampling pipeline in the off-line sampling monitoring method brings about the influence of complexity and uncertainty. The present invention provides the following embodiments to solve the above problems:
example 1
The embodiment provides an online monitoring method for beta rays and gamma rays of a floating nuclear power plant, as shown in fig. 1, including the steps of:
the method comprises the following steps: simultaneously acquiring beta ray signals and gamma ray signals in a first space, a second space and a third space of a radiation field of a radiation source: wherein, beta ray signals and gamma ray signals are simultaneously collected in a first space, gamma ray signals are collected in a second space, and gamma ray signals are collected in a third space; the centers of the first space, the second space and the third space are sequentially distributed along a ray L, the ray L is a perpendicular line of a pipeline where the ray source is located, the first space is closest to the pipeline where the ray source is located, and the first space penetrates through the pipe wall of the pipeline where the ray source is located;
step two: deducting a gamma ray interference signal from a beta ray signal and a gamma ray signal acquired by a first space based on a gamma ray signal acquired by a second space to obtain the dose rate of the beta ray; a gamma-ray dose rate is calculated based on the gamma-ray signals acquired in the third space.
The beta ray signal and the gamma ray signal are scintillation light signals. The second step comprises the following substeps:
s21, performing photoelectric conversion on the scintillation light signals collected in the first space to obtain pulse signals A1, performing photoelectric conversion on the scintillation light signals collected in the second space to obtain pulse signals A2, and triggering the pulse signals A1 and A2 to output TTL pulse signals A1 and A2 with the same duration respectively;
s22, acquiring trigger time T of two groups of TTL pulse signals A1 And T A2 Using TTL pulse signal A1 as gate signal to calculate T A1 And T A2 The difference Δ T of (d);
and S23, if the delta T is smaller than the threshold value T, subtracting the TTL pulse signal A2 from the TTL pulse signal A1, and then calculating the dosage rate of the beta ray, otherwise, directly calculating the dosage rate of the beta ray based on the TTL pulse signal A1.
In the embodiment, two high beta/gamma thin plastic scintillators are placed in a first space and a second space, a high gamma thick plastic scintillator is placed in a third space to collect beta ray signals and gamma ray signals, after scintillation light output by the two high beta/gamma thin plastic scintillators passes through a SiPM photoelectric module conversion circuit, a fast pulse signal with a steep rising edge is generated, in order to extract effective pulse information, the fast pulse is transmitted into a fast comparator, square wave pulses with a threshold value of 100mV and a pulse width of 200ns are triggered and formed, and then the square wave pulses are further processed in a TTL pulse generator, so that +5V TTL pulses A1 and TTL pulses A2 are generated in the output, the pulse duration is 10 mus, and the triggering time of the two groups of pulses is recorded as TA1 and TA2.
Taking a TTL pulse signal A1 of a first beta/gamma thin plastic scintillator as a gate signal, calculating a difference value delta T between TA1 and TA2, and if the delta T is smaller than T =2 mus, determining that an anti-coincidence effect occurs, namely that gamma rays generate a scintillation light effect on both the first beta/gamma thin plastic scintillation crystal and a second beta/gamma thin plastic scintillation crystal, so that the signal needs to be considered to be deducted from a total output signal of a first detector, the interference of the gamma rays is reduced, and the dosage rate of the beta rays is obtained.
And aiming at scintillation light output by the high gamma thick plastic scintillator, the gamma ray dosage rate is calculated after photoelectric conversion, amplification forming and TTL forming processing.
Example 2
The embodiment provides an online monitoring system for beta rays and gamma rays of a floating nuclear power plant, which is used for implementing the online monitoring method for beta rays and gamma rays of a floating nuclear power plant in the previous embodiment, as shown in fig. 2, and includes:
a detector assembly 1 for simultaneously acquiring β -ray signals and γ -ray signals in a first space, a second space and a third space of a radiation field of a radiation source: the method comprises the following steps of acquiring a beta-ray signal and a gamma-ray signal simultaneously in a first space, acquiring a gamma-ray signal in a second space and acquiring a gamma-ray signal in a third space; the centers of the positions of the first space, the second space and the third space are sequentially arranged along a ray L, the ray L is a perpendicular line of a flowing pipeline of the ray source, the first space is closest to the pipeline where the ray source is located, and the first space penetrates through the pipe wall of the pipeline where the ray source is located;
the calculation module is used for deducting the gamma ray interference signal from the beta ray signal and the gamma ray signal acquired by the first space based on the gamma ray signal acquired by the second space to obtain the dosage rate of the beta ray; calculating a gamma-ray dose rate based on the gamma-ray signals acquired in the third space;
the measuring pipe 2 is used as a flow pipeline for carrying the detector assembly and serving as a ray source;
and the shielding assembly 3 is wrapped on the periphery of the flow pipeline where the probe assembly is positioned and used for shielding the probe assembly.
The detector assembly 1 is cylindrical, and the detector assembly 1 is perpendicular to the measuring pipe 2 and penetrates through the pipe wall of the measuring pipe 2 to directly contact the ray source; the shielding assembly 3 is wrapped outside the detector assembly 1, and meanwhile, the shielding assembly 3 is also arranged on the pipe wall of the detector assembly 1, which penetrates through the measuring pipe fitting 2 to point to.
As shown in fig. 3, the probe assembly 1 includes: a first high beta/gamma plastic scintillator detector 11, a second high beta/gamma plastic scintillator detector 12, a high gamma plastic scintillator detector 13 and an insulating material 14;
the first beta/gamma plastic scintillator detector 11, the second beta/gamma plastic scintillator detector 12 and the gamma plastic scintillator detector 13 are sequentially spliced and arranged into a cylindrical structure, and the first beta/gamma plastic scintillator detector 11, the second beta/gamma plastic scintillator detector 12 and the gamma plastic scintillator detector 13 occupy spaces respectively forming a first space, a second space and a third space; the insulating material 14 wraps the outer surface of the cylindrical structure, and the insulating material 14 corresponding to the first beta/gamma plastic scintillator detector 11 penetrates through the pipe wall of the measuring pipe to directly contact with the radiation source.
The photoelectric conversion module 15 is further included, and the first high beta/gamma plastic scintillator detector 11, the second high beta/gamma plastic scintillator detector 12 and the high gamma plastic scintillator detector 13 are respectively connected with one photoelectric conversion module 15. The signal lines 5 of the respective photoelectric conversion modules 15 are collected together by the signal line concentration processing module 16.
The thicknesses of the first high beta/gamma plastic scintillator detector 11 and the second high beta/gamma plastic scintillator detector 12 are consistent, and the thickness of the high gamma plastic scintillator detector 13 is larger than that of the first high beta/gamma plastic scintillator detector 11.
The thickness of the high gamma plastic scintillator detector 13 is at least 50 times the thickness of the first high beta/gamma plastic scintillator detector 11.
As shown in fig. 4, the processing procedure included in the computation module, i.e. the signal centralized processing unit, is as follows:
the first high beta/gamma plastic scintillator detector 11 outputs beta and gamma scintillation light which is processed by the photoelectric conversion module A1 and outputs a group of pulse signals, the second high beta/gamma plastic scintillator detector 12 outputs gamma scintillation light which is processed by the photoelectric conversion module A2 and outputs a group of pulse signals, the high gamma plastic scintillator detector 13 outputs gamma scintillation light which is processed by the photoelectric conversion module B and outputs a group of pulse signals, the three groups of pulse signals respectively output three groups of TTL pulse signals by the fast shaping circuit A, the fast shaping circuit B and the fast shaping circuit C, the first two groups are used for outputting beta ray dosage rate after gamma ray compensation calculation, and the last group is used for outputting gamma ray dosage rate.
The shielding assembly 3 is prepared from lead alloy, and polyethylene material is filled between the detector assembly 1 and the shielding assembly 3.
The floating nuclear power plant beta ray and gamma ray on-line monitoring system can realize effective collection of beta rays and gamma rays generated by inert gas and liquid decay in a process pipeline, the detector component of the system comprises two types of plastic detectors, and the high beta/gamma thin plastic scintillator detector can reduce the measurement interference of the gamma rays to the beta rays in an object to be measured through compensation, so that the beta rays in the inert gas can be accurately measured at high efficiency; the high gamma thick plastic scintillator detector deposits the energy loss of gamma rays in the detector completely, generates a great amount of photoelectric effect, realizes the effective monitoring of the gamma rays with middle and low energy, is used for the online gamma monitoring of liquid or inert gas in a process pipeline, and ensures the operation safety of a reactor.
Example 3
The embodiment provides a floating type nuclear power plant beta ray and gamma ray on-line monitoring device, a detector component of the device adopts a modular design and comprises 2
The high beta/gamma thin plastic scintillator detector (containing 2 SiPM photoelectric conversion modules) and 1
The high gamma thick plastic scintillator detector (containing 1 SiPM photoelectric conversion module) and a centralized signal processing unit. In addition, the measuring tube is an expanded stainless steel tube, the length of the tube is 500mm, the tube diameters of the two ends are 350mm, the tube diameter of the center is 450mm, the size or the mass of the detector component for the object to be detected is increased, and the detection efficiency is improved. Meanwhile, the thickness of the lead shielding layer of the device is 60mm, and radiation interference of the environmental background can be reduced. In addition, two ends of the device are connected with the process pipe through flanges, the structure is compact, and the installation and maintenance are convenient. Through tests, the device can realize effective detection of beta rays and gamma rays in inert gas in the process pipeline, can meet the requirement of real-time online analysis of the gamma rays in liquid in the process pipeline, and has the energy corresponding range of 80 keV-2.5 MeV and the beta ray measurement range of 10 6 Bq/m 3 ～3.7×10 15 Bq/m 3 ( 133 Xe), gamma ray measurement range of 3.7 × 10 2 Bq/m 3 ～3.7×10 12 Bq/m 3 ( 137 Cs). The size of the device is 500mm (L) multiplied by 450mm (W) multiplied by 450mm (H), the weight is 45kg, and the technical requirement of the floating nuclear power plant reactor radiation monitoring system for process monitoring can be met.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. A floating type nuclear power plant beta ray and gamma ray on-line monitoring method is characterized by comprising the following steps:
the method comprises the following steps: simultaneously acquiring beta ray signals and gamma ray signals in a first space, a second space and a third space of a radiation field of a radiation source: the method comprises the following steps of acquiring a beta-ray signal and a gamma-ray signal simultaneously in a first space, acquiring a gamma-ray signal in a second space and acquiring a gamma-ray signal in a third space; the centers of the positions of the first space, the second space and the third space are sequentially arranged along a ray L, the ray L is a perpendicular line of a pipeline where the ray source is located, the first space is closest to the pipeline where the ray source is located, and the first space penetrates through the pipe wall of the pipeline where the ray source is located;
step two: deducting a gamma ray interference signal from a beta ray signal and a gamma ray signal acquired by a first space based on a gamma ray signal acquired by a second space to obtain the dose rate of the beta ray; a gamma-ray dose rate is calculated based on the gamma-ray signals acquired in the third space.
2. The online beta-ray and gamma-ray monitoring method for a floating nuclear power plant according to claim 1, characterized in that the beta-ray signal and the gamma-ray signal are scintillation light signals.
3. The method for on-line monitoring beta rays and gamma rays of a floating nuclear power plant according to claim 2, characterized in that the second step comprises the following substeps:
s21, performing photoelectric conversion on the scintillation light signals collected in the first space to obtain pulse signals A1, performing photoelectric conversion on the scintillation light signals collected in the second space to obtain pulse signals A2, and triggering the pulse signals A1 and A2 to output TTL pulse signals A1 and A2 with the same duration respectively;
s22, acquiring trigger time T of two groups of TTL pulse signals A1 And T A2 Using TTL pulse signal A1 as gate signal to calculate T A1 And T A2 The difference Δ T of (d);
s23, if the delta T is smaller than the threshold value T, subtracting the TTL pulse signal A2 from the TTL pulse signal A1, and then calculating the dosage rate of the beta ray, otherwise, directly calculating the dosage rate of the beta ray based on the TTL pulse signal A1.
4. A beta ray and gamma ray on-line monitoring system of a floating nuclear power plant is used for realizing the beta ray and gamma ray on-line monitoring method of the floating nuclear power plant according to any one of claims 1 to 3, and comprises the following steps:
a detector assembly 1 for simultaneously acquiring β -ray signals and γ -ray signals in a first space, a second space and a third space of a radiation field of a radiation source: wherein, beta ray signals and gamma ray signals are simultaneously collected in a first space, gamma ray signals are collected in a second space, and gamma ray signals are collected in a third space; the centers of the positions of the first space, the second space and the third space are sequentially arranged along a ray L, the ray L is a perpendicular line of a flowing pipeline of the ray source, the first space is closest to the pipeline where the ray source is located, and the first space penetrates through the pipe wall of the pipeline where the ray source is located;
the calculation module is used for deducting the gamma-ray interference signal from the beta-ray signal and the gamma-ray signal acquired by the first space based on the gamma-ray signal acquired by the second space to obtain the dosage rate of the beta-ray; calculating a gamma ray dose rate based on the gamma ray signals acquired in the third space;
the measuring pipe 2 is the same as a flow pipeline which bears the detector assembly and is used as a ray source;
and the shielding assembly 3 is wrapped on the periphery of the flow pipeline where the probe assembly is positioned and used for shielding the probe assembly.
5. The system for on-line monitoring beta rays and gamma rays of a floating nuclear power plant according to claim 4, characterized in that the detector assembly 1 is cylindrical, the detector assembly 1 is installed perpendicular to the measuring pipe 2 and passes through the pipe wall of the measuring pipe 2 to directly contact the ray source; the shielding assembly 3 is wrapped outside the detector assembly 1, and meanwhile the detector assembly 1 penetrates through the pipe wall, towards which the measuring pipe fitting 2 points, to be provided with the shielding assembly 3.
6. A floating type nuclear power plant beta ray and gamma ray online monitoring system as claimed in claim 5, characterized in that the detector assembly 1 includes: a first high beta/gamma plastic scintillator detector 11, a second high beta/gamma plastic scintillator detector 12, a high gamma plastic scintillator detector 13 and an insulating material 14;
the first beta/gamma plastic scintillator detector 11, the second beta/gamma plastic scintillator detector 12 and the gamma plastic scintillator detector 13 are sequentially spliced and arranged into a cylindrical structure, and the first beta/gamma plastic scintillator detector 11, the second beta/gamma plastic scintillator detector 12 and the gamma plastic scintillator detector 13 occupy spaces respectively forming a first space, a second space and a third space; the insulating material 14 wraps the outer surface of the cylindrical structure, and the insulating material 14 corresponding to the first beta/gamma plastic scintillator detector 11 penetrates through the pipe wall of the measuring pipe to directly contact with the radiation source.
7. The system of claim 6, further comprising a photoelectric conversion module 15, wherein the first high β/γ plastic scintillator detector 11, the second high β/γ plastic scintillator detector 12, and the high γ plastic scintillator detector 13 are respectively connected to a photoelectric conversion module 15.
8. A floating type nuclear power plant beta ray and gamma ray on-line monitoring system as claimed in claim 7, characterized in that the thickness of the first high beta/gamma plastic scintillator detector 11 is the same as that of the second high beta/gamma plastic scintillator detector 12, and the thickness of the high gamma plastic scintillator detector 13 is larger than that of the first high beta/gamma plastic scintillator detector 11.
9. A floating nuclear power plant beta and gamma ray on-line monitoring system as claimed in claim 8, wherein the thickness of the high gamma plastic scintillator detector 13 is at least 50 times the thickness of the first high beta/gamma plastic scintillator detector 11.
10. The system for on-line monitoring beta rays and gamma rays of a floating type nuclear power plant as claimed in claim 5, wherein the shielding component 3 is made of lead alloy, and polyethylene material is filled between the detector component 1 and the shielding component 3.
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