CN107907901A - The measuring method and system of nuclear power station neutron, gamma spectra and dosage - Google Patents
The measuring method and system of nuclear power station neutron, gamma spectra and dosage Download PDFInfo
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- CN107907901A CN107907901A CN201711076547.XA CN201711076547A CN107907901A CN 107907901 A CN107907901 A CN 107907901A CN 201711076547 A CN201711076547 A CN 201711076547A CN 107907901 A CN107907901 A CN 107907901A
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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
- G01T1/023—Scintillation dose-rate meters
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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
- G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
- G01T1/362—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry with scintillation detectors
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
- G01T3/06—Measuring neutron radiation with scintillation detectors
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
- G01T3/06—Measuring neutron radiation with scintillation detectors
- G01T3/065—Spectrometry
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Abstract
The invention discloses the measuring method of a kind of nuclear power station neutron, gamma spectra and dosage, it comprises the following steps：1) by neutron and gamma ray input neutron detection system output signal A, gamma ray is inputted into gamma detection system output signal B；2) signal A and signal B are inputted into digital signal processing circuit progress calculation process jointly and obtains neutron, gamma spectra and dosage；Wherein, digital signal processing circuit is using field programmable gate array chip as acp chip.Relative to the prior art, the measuring method of nuclear power station neutron of the present invention, gamma spectra and dosage measures while realizing neutron, gamma spectra and dosage based on FPGA Technology.A kind of in addition, measuring system the invention also discloses nuclear power station neutron, gamma spectra and dosage.
Description
Technical field
The invention belongs to technical field of nuclear power, it is more particularly related to a kind of nuclear power station neutron, gamma spectra with
The measuring method and system of dosage, protection, environment suitable for the mixing field area people such as nuclear power plant nuclear island and Spent Fuel Pool
Radiation monitoring.
Background technology
Neutron energy spectrum is mainly used in the analysis of neutron flux, and neutron behavior, heap power to research reactor etc. have weight
The effect wanted；The measurement of gamma spectra is mainly used in the fields such as nuclide identification, industrial flaw detection, and gamma spectra is carried out in nuclear power plant
Measurement primarily to understand environment in radionuclide distribution and content.
At present, the technology of detection gamma ray is very ripe both at home and abroad, not only there is the personnel dosimeter that species is enriched,
There is portable isotope identifier in succession.But the technology for detecting neutron ray is immature, because quick to neutron ray
The detector of sense is also sensitive to gamma ray, therefore cannot accurately obtain neutron energy spectrum and dosage.
The prior art provides a kind of hand-held neutron-gamma radiation detector, uses6LiI (Eu) scintillation crystal conduct
Neutron detection element, using CsI crystal as gamma detection element, sensitive, measurable environment is responded to neutron and gamma radiation
Ambient radiation is horizontal, can also add up dose of radiation.Above-mentioned hand-held neutron-gamma radiation detector is not only simple in structure, volume
It is compact and light-weight, easy to carry, easy to use.
But above-mentioned hand-held neutron-gamma radiation detector still suffers from problems with：
1) counting of neutron, gamma only by the conjunction measuring of discriminator and counter, then calculates agent according to counting
Amount, but the power spectrum and dosage of neutron and gamma ray cannot be measured at the same time；
2) neutron and gamma dosage are calculated based on counting method, there are larger constant error；
3) although to the output signal of neutron and gamma-ray probe, given threshold is screened respectively, neutron probe is to gal
Horse radiation-sensitive, the signal of neutron probe output include neutron signal and gamma signal, lead to not screen neutron ray and gal
Horse ray, the data reliability of acquisition and accuracy be not high.
In view of this, it is necessory to provide a kind of high nuclear power station neutron of accuracy of measurement, gamma spectra and the survey of dosage
Measure method and system.
The content of the invention
It is an object of the invention to：The defects of overcoming the prior art, there is provided a kind of high nuclear power station neutron of accuracy of measurement,
The measuring method and system of gamma spectra and dosage.
For achieving the above object, the present invention provides the measuring method of a kind of nuclear power station neutron, gamma spectra and dosage,
It comprises the following steps：
1) by neutron and gamma ray input neutron detection system output signal A, gamma ray is inputted into gamma detection system
System output signal B；
2) signal A and signal B are inputted into digital signal processing circuit progress calculation process jointly and obtains neutron, gamma spectra
With dosage；
Wherein, digital signal processing circuit is using field programmable gate array (FPGA) chip as acp chip.
The a kind of of measuring method as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the neutron detection
System includes neutron detector and the first analog-digital converter, the letter exported after neutron and gamma ray the input neutron detector
Number it is the input signal of the first analog-digital converter, the first analog-digital converter output signal A.
The a kind of of measuring method as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the gamma detection
System includes gamma detector and the second analog-digital converter, and the signal exported after the gamma ray input gamma detector is the
The input signal of two analog-digital converters, the second analog-digital converter output signal B.
The a kind of of measuring method as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the digital signal
Process circuit obtains signal A acquisition process neutron and gamma mixed tensor deposition spectrum, and gamma energy is obtained to signal B acquisition process
Amount deposition spectrum.
The a kind of of measuring method as nuclear power station neutron of the present invention, gamma spectra and dosage improves, in the step 2)
Arithmetic processing method includes：Spectrum progress spectrum unscrambling is deposited to gamma energy and obtains gamma spectra；Gamma spectra is being moulded through gamma ray
Energy Response Matrix in material scintillator acts on obtaining gamma modeling sudden strain of a muscle energy deposition spectra；Neutron and gamma mixed tensor deposition spectrum button
Sudden strain of a muscle energy deposition spectra, which is moulded, except corresponding gamma obtains remaining proton spectra；Neutron energy spectrum is obtained to remaining proton spectra spectrum unscrambling；Finally lead to
Cross and neutron dose and gamma dosage is calculated.
The a kind of of measuring method as nuclear power station neutron of the present invention, gamma spectra and dosage improves, and may be programmed at the scene
Gamma dosage is calculated by G (E) function method on door Array Substrate, neutron agent is calculated by Kerma calculating method
Amount.
The a kind of of measuring method as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the digital signal
Output signal driving display module, communication module and the memory module running of process circuit.
In order to realize foregoing invention purpose, present invention also offers the survey of a kind of nuclear power station neutron, gamma spectra and dosage
Amount system, it includes：
Neutron detection system, including neutron detector and the first modulus for being connected with the signal output part of neutron detector turn
Parallel operation；
Gamma detection system, including gamma detector and the second modulus for being connected with the signal output part of gamma detector turn
Parallel operation；And
Digital signal processing circuit, using field programmable gate array chip as acp chip；
Wherein, the signal output part of first analog-digital converter and second analog-digital converter is respectively connected to numeral
The signal input part of signal processing circuit, the digital signal processing circuit turn first analog-digital converter and the second modulus
The output signal of parallel operation carries out calculation process.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the neutron detection
Device includes plastic scintillant probe, shielding shell, high voltage power supply, photomultiplier, charge sensitive amplifier.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the Plastic scintillation
Body probe is used for the energy for measuring neutron and gamma ray, and nuclear signal is converted to optical signal.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the gamma detection
Device includes NaI (Tl) scintillator probe, shielding shell, high voltage power supply, photomultiplier, charge sensitive amplifier.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, and the NaI (Tl) is dodged
Bright body probe is used for the energy for measuring gamma ray, and nuclear signal is converted to optical signal.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the digital signal
Output signal acquisition process of the process circuit to the first analog-digital converter obtains neutron and gamma mixed tensor deposition spectrum, to second
The output signal acquisition process of analog-digital converter obtains gamma energy deposition spectrum.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, the calculation process
Including：Spectrum progress spectrum unscrambling is deposited to gamma energy and obtains gamma spectra；Gamma spectra is through gamma ray in plastic scintillant
Energy Response Matrix acts on obtaining gamma modeling sudden strain of a muscle energy deposition spectra；Neutron and gamma mixed tensor deposition spectrum deduct corresponding gamma
Modeling dodges energy deposition spectra and obtains remaining proton spectra；Neutron energy spectrum is obtained to remaining proton spectra spectrum unscrambling；In being calculated
Sub- dosage and gamma dosage.
The a kind of of measuring system as nuclear power station neutron of the present invention, gamma spectra and dosage improves, and may be programmed at the scene
Gamma dosage is calculated using G (E) function method on gate array chip, neutron agent is calculated by Kerma calculating method
Amount.
Relative to the prior art, the measuring method and system of nuclear power station neutron of the present invention, gamma spectra and dosage have with
Lower beneficial effect：
1) by selecting NaI (Tl) scintillators and plastic scintillant to be used as detector, meet from measuring principle to gamma
Measured while ray and neutron ray, by depositing spectrum spectrum unscrambling to gamma energy, to neutron and gamma mixed tensor deposition spectrum
Neutron energy spectrum and gamma spectra is calculated in spectrum stripping, the method to remaining proton spectra spectrum unscrambling, by G (E) function methods and than releasing
Energy calculating method obtains neutron dose and gamma dosage, by building including detector, analog-digital converter (ADC), field-programmable
The measuring system of gate array (FPGA), realizes the function of measuring neutron, gamma spectra and dosage at the same time, suitable for mixing field
The measurement of son and gamma spectra and dosage；
2) measured while realizing neutron, gamma spectra and dosage based on FPGA technology, measuring system has small, knot
The advantages of structure is simple, easy to carry；
3) neutron dose is calculated based on spectroscopy, reduces constant error during measurement neutron dose；
4) by realizing that G (E) function method calculates gamma dosage on fpga chip, it is possible to reduce the sound of gamma dosage measurement
Between seasonable and relative error, the memory space of FPGA has been saved；
5) by depositing the neutron to be formed in neutron and gamma energy and being peeled off in gamma mixed tensor deposition spectrum by gamma
The electron spectrum that actinism produces, realizes the examination of neutron and gamma, improves the accuracy and accuracy of measuring method.
Brief description of the drawings
With reference to the accompanying drawings and detailed description, to the measurement side of nuclear power station neutron of the present invention, gamma spectra and dosage
Method and system and its advantageous effects are described in detail, wherein：
Fig. 1 is the schematic diagram of the measuring system of nuclear power station neutron of the present invention, gamma spectra and dosage.
Fig. 2 is the schematic diagram of the measuring method of nuclear power station neutron of the present invention, gamma spectra and dosage.
Embodiment
In order to become apparent from goal of the invention, technical solution and its advantageous effects of the present invention, below in conjunction with attached drawing
And embodiment, the present invention will be described in further detail.It should be appreciated that the specific reality described in this specification
Mode is applied just for the sake of explaining the present invention, is not intended to limit the present invention.
Refering to Figure 1, the measuring system of nuclear power station neutron of the present invention, gamma spectra and dosage includes：
Neutron detection system 10, including neutron detector 102 and be connected with the signal output part of neutron detector 102
One analog-digital converter 104；
Gamma detection system 20, including gamma detector 202 and be connected with the signal output part of gamma detector 202
Two analog-digital converters 204；And
Digital signal processing circuit 30, using field programmable gate array (FPGA) chip as acp chip；
Wherein, the signal output part of the first analog-digital converter 104 and the second analog-digital converter 204 is respectively connected to digital letter
The signal output part of number process circuit 30, digital signal processing circuit 30 is to the first analog-digital converter 104 and the second analog-to-digital conversion
The output signal of device 204 carries out calculation process.
102 preferred plastic scintillation detectors of neutron detector, plastic scintillation detectors include plastic scintillant probe, shielding
The devices such as shell, high voltage power supply, photomultiplier, charge sensitive amplifier, during plastic scintillant probe can measure
The energy of son and gamma ray, optical signal is converted into by nuclear signal, and light intensity characterizes the energy of ray, and photomultiplier is by optical signal
Electric signal is amplified and converted to, high voltage power supply is powered for photomultiplier, and charge sensitive amplifier is to photomultiplier
The electric signal of output is filtered, amplifies, and the output signal of charge sensitive amplifier is the first analog-digital converter
(ADC1) 104 input signal, the first analog-digital converter 104 output signal A, digital information processing system 30 gather signal A
Processing obtains neutron and gamma mixed tensor deposition spectrum.
The preferred EJ299-33A plastic scintillation detectors of plastic scintillation detectors, EJ299-33A plastic scintillation detectors are Φ
The cylinder of 50mm × 50mm, its density are about 1.08g/cm3, one layer of aluminium of scintillator outer layer covers, shell density is about 2.7g/
cm3, the positive face thickness of aluminum hull is 1mm, lateral thickness 2.5mm.The middle H atom number density of plastic scintillant is 5.13 × 1022/
cm3, C atoms number density is 4.86 × 1022/cm3。
Gamma detector 202 preferred NaI (Tl) scintillation detector, NaI (Tl) scintillation detector include NaI (Tl) scintillator
Device, NaI (Tl) scintillators such as probe, shielding shell, high voltage power supply, photomultiplier, charge sensitive amplifier are visited
Head is merely able to the energy of measurement gamma ray, nuclear signal is converted into optical signal, light intensity characterizes the energy of ray, photomultiplier
By optical signal amplification and electric signal is converted into, high voltage power supply is powered for photomultiplier, and charge sensitive amplifier is to light
The electric signal of electric multiplier tube output is filtered, amplifies, and the output signal of charge sensitive amplifier turns for the second modulus
The input signal of parallel operation (ADC2) 204, the second analog-digital converter 204 output signal B, digital information processing system 30 is to signal B
Acquisition process obtains gamma energy deposition spectrum.
By depositing spectrum spectrum unscrambling to gamma energy, composing spectrum stripping, to remaining proton spectra to neutron and gamma mixed tensor deposition
The method of spectrum unscrambling obtains neutron energy spectrum and gamma spectra, obtains gamma dosage by G (E) function method on fpga chip, passes through
Kerma calculating method obtains neutron dose.Output signal driving display module 302, communication module 304 and the storage mould of FPGA
The running of block 306.
Please refer to Fig.1 with shown in Fig. 2, the measuring method of nuclear power station neutron of the present invention, gamma spectra and dosage includes following
Step：
1) neutron and gamma ray input neutron detection system 10 are exported into signal A, gamma ray is inputted into gamma detection
System 20 exports signal B；
2) signal A and signal B are inputted into digital signal processing circuit 30 jointly carry out calculation process and obtain neutron, gamma energy
Spectrum and dosage；
Wherein, digital signal processing circuit 30 is using field programmable gate array (FPGA) chip as acp chip.
Neutron and gamma ray by the effect output electric signal of neutron detector 102, the amplitude characterization neutron of electric signal and
The energy of gamma ray, electric signal carry out conversion of the analog signal to digital signal, the first mould by the first analog-digital converter 104
The output signal of number converter 104 enters FPGA, and the processing logic of digital signal is established inside FPGA, realizes multiple tracks pulse first
The function of amplitude analyzer, multichannel pulse scope-analyzer refer to pulse signal being assigned to different roads according to its amplitude size
The relation of location, whole step-by-step countings and road location forms pulse amplitude spectrum, due to impulse amplitude and ray energy positive correlation, passes through energy
The one-to-one relationship of Liang Yu roads location can be demarcated, and obtain neutron and gamma mixed tensor deposition spectrum.
Gamma ray is by the effect output electric signal of gamma detector 202, the energy of the amplitude characterization gamma ray of electric signal
Amount, electric signal carry out conversion of the analog signal to digital signal, the second analog-digital converter 204 by the second analog-digital converter 204
Output signal enter FPGA, the processing logic of digital signal is established inside FPGA, realizes multichannel pulse scope-analyzer first
Function, multichannel pulse scope-analyzer refers to pulse signal being assigned to different road locations, whole arteries and veins according to its amplitude size
Punching counts and the relation of road location forms pulse amplitude spectrum, due to impulse amplitude and ray energy positive correlation, passes through energy and road location
One-to-one relationship can be demarcated, obtain gamma energy deposition spectrum.
Under same radiation field, the gamma energy into plastic scintillant and NaI (Tl) scintillator is consistent with intensity,
Two kinds of different detectors can be obtained by way of testing and measuring to the detection efficient of gamma ray, pass through Monte Carlo calculations
Method can obtain different-energy gamma ray every one of sedimentary energy in two kinds of detectors probability, thus can by mistake
Difference obtains the situation of gamma ray sedimentary energy in plastic scintillant in the range of allowing, then by plastics by way of spectrum stripping
Gamma discrimination in scintillator in neutron and gamma mixed tensor deposition spectrum falls.
Below in conjunction with shown in Fig. 2, the arithmetic processing method in step 2) is described in detail：
1) spectrum progress spectrum unscrambling is deposited to gamma energy and obtains gamma spectra；
Gamma energy deposits the counting N of Pu i-thg0iRepresent, NaI gamma energies the i-th row of response matrix jth row
Value RgNaIijRepresent, NaI gamma energy response matrixes are that the gamma ray for characterizing different-energy is visited in NaI (Tl) scintillator
Survey in device in the probable value of every one of sedimentary energy, can be obtained by Monte Carlo calculations or experimental method measurement, iteration kth time
The counting Φ in gamma spectra jth roadgj (k)Represent, jth road initial gamma power spectrum setting value Φgj (0)Represent, arbitrarily set one
Group Φgj (0)Value, forms initial gamma power spectrum, brings GRAVEL iterative algorithms into and calculated, and setting iterations n times are (according to grinding
Study carefully as shown by data, during iterations N=4000, spectrum unscrambling precision is very high, is further added by iterations precision improvement unobvious, and
The interative computation time is longer), one group of Φ being calculatedgj (N)It is then gamma spectra.Using GRAVEL algorithms to energy deposition spectra
Carry out the error of spectrum unscrambling is influenced be subject to iterations, and with the increase of interative computation number, spectrum unscrambling error is far below counting method
The constant error of neutron dose is measured, the error of GRAVEL algorithm spectrum unscramblings measures neutron dose within 10%, less than counting method
More than 50% constant error.
GRAVEL interative computation formula are as follows：
Wherein,
ρg0iFor Ng0iStandard deviation.
2) gamma spectra acts on obtaining gamma modeling sudden strain of a muscle energy through Energy Response Matrix of the gamma ray in plastic scintillant
Deposition spectrum；
The value R of gamma energy the i-th row of response matrix jth row is dodged in modelinggPijRepresent, gamma energy response matrix characterization is dodged in modeling
The gamma ray of different-energy in plastic scintillator detector in the probable value of every one of sedimentary energy, can be by Monte Carlo
Calculate or experimental method measurement obtains, the counting Φ in the gamma spectra jth road that interative computation n times obtaingj (N)Represent, gamma modeling
Dodge the counting N of energy deposition spectra i-thgPiRepresent, the counting that energy deposition spectra i-th is dodged in gamma modeling can be counted by formula (2)
Obtain：
NgPi=RgPij·Φgj (N)Formula (2)
Gamma modeling is calculated according to formula (2) and dodges energy deposition spectra per counting together.
3) neutron and gamma mixed tensor deposition spectrum deduct corresponding gamma modeling sudden strain of a muscle energy deposition spectra and obtain remaining proton spectra；
The counting N of neutron and gamma mixed tensor deposition spectrum i-thgniRepresent, the counting of remaining proton spectra i-th is used
Nn0iRepresent, then the counting of remaining proton spectra i-th can be calculated by formula (3)：
Nn0i=Ngni-NgPiFormula (3)
Remaining proton spectra are calculated per counting together according to formula (3).
4) neutron energy spectrum is obtained to remaining proton spectra spectrum unscrambling；
The value R of the i-th row of Neutron energy responce matrix jth rownijRepresent, Neutron energy responce matrix characterization different-energy
Neutron in plastic scintillator detector in the probable value of every one of sedimentary energy, can be obtained by Monte Carlo calculations, repeatedly
For the counting Φ in kth time neutron energy spectrum jth roadnj (k)Represent, jth road primary neutron power spectrum setting value Φnj (0)Represent, appoint
One group of Φ of meaning settingnj (0)Value, forms primary neutron power spectrum, substitutes into GRAVEL iterative algorithms and is calculated, sets iterations n times
(shown according to data, during iterations N=4000, spectrum unscrambling precision is very high, is further added by iterations precision improvement not
Substantially, and the interative computation time is longer), one group of Φ being calculatednj (N)It is then neutron energy spectrum.
GRAVEL interative computation formula are as follows：
Wherein,ρn0iFor Nn0iStandard deviation.
5) gamma dosage is calculated by G (E) function method on fpga chip according to gamma energy deposition spectrum；
G (E) function method is also known as full spectrometry, and the gamma energy deposition spectrum that it measures spectrometer adds one and energy per one
Relevant coefficient, i.e. dose weights value are measured, this value can be calculated by G (E) function, and G (E) function can pass through base
Obtained in the least square fitting of relative error quadratic sum minimum principle, it is one and detector size, the relevant letter of structure
Number, it is unrelated with radiation field.
G (E) functional form is：
By way of least square fitting, KMAX values are chosen, one group of A (K) value of G (E) coefficient is calculated, substitute into gal
The i-th energy value of horse energy deposition spectra EiThe i-th power spectrum dose conversion factor is calculated, i.e. G (E) functional value is G (Ei), gal
Horse absorbent value DgRepresent, gamma absorbent value can be calculated by formula (6)：
Wherein, IMAX is the most high address of gamma energy deposition spectrum.
6) neutron dose is calculated by Kerma calculating method according to neutron energy spectrum；
Under conditions of charged particle equilibrium is met, NEUTRON ABSORBED DOSE FROM and Kerma approximately equal, therefore can pass through
The method for solving Kerma calculates relation such as formula (7) table of NEUTRON ABSORBED DOSE FROM, NEUTRON ABSORBED DOSE FROM and Kerma
Show：
Expression energy is the mass energy transfer coefficient of the neutron of E in media as well,Represent the neutron that energy is E
Fluence, Kerma of the function representation neutron energy between E to E+dE in the sign of integration, neutron fluence value can be by neutron
Power spectrum is calculated, at a certain distance from neutron energy spectrum characterizes incident neutron before plastic scintillator detector on an equivalent plane
Energy distribution situation, the survey that this distance and plane geomery are used when key element and Neutron energy responce chess matrix analogue calculate
It is consistent to measure model.
For monoenergetic neutrons, its Kerma can be expressed as：Ki=fki·Φi, wherein fkiRepresent in i-th group of energy
The kerma factor of son, fkiRepresent the Kerma of unit neutron fluence, ΦiRepresent the fluence of the neutron of i-th group of energy.
Furthermore, it is possible to obtain the kerma factor of each group's neutron by way of linear interpolation, substitute into formula and calculate
Divide group's neutron dose.
It should be noted that neutron detector 102 is not limited to use plastic scintillator detector, gamma detector 202 is not
It is limited to use NaI (Tl) scintillator detector, every spy that can meet detector size, energy resolution and detection efficient requirement
The alternative plastic scintillator detector of device and NaI (Tl) scintillator detector are surveyed, wherein, detector size need to meet portability
Good requirement.
In addition, the electricity such as the first analog-digital converter 104, the second analog-digital converter 204 and field programmable gate array (FPGA)
Sub- component does not specify the model used, and selection meets that the broadband fully sampled to nuclear signal shape, the modulus of sample rate requirement turn
Parallel operation, selection meet that multi-channel analysis, spectrum unscrambling and other fpga chips for calculating process performance requirement are carried out to nuclear signal is
Can.The computational methods of neutron dose are not limited to Kerma calculating method, and neutron dose is calculated by neutron energy spectrum in other
Computational methods can also under conditions of the limitation of FPGA memory spaces is met.
According to above detailed description of the present invention, relative to the prior art, nuclear power station neutron of the present invention, gamma energy
Compose and had the advantages that with the measuring method of dosage：
1) by selecting NaI (Tl) scintillators and plastic scintillant to be used as detector, meet from measuring principle to gamma
Measured while ray and neutron ray, by depositing spectrum spectrum unscrambling to gamma energy, to neutron and gamma mixed tensor deposition spectrum
Neutron energy spectrum and gamma spectra is calculated in spectrum stripping, the method to remaining proton spectra spectrum unscrambling, by G (E) function methods and than releasing
Energy calculating method obtains neutron dose and gamma dosage, by building including detector, analog-digital converter (ADC), field-programmable
The measuring system of gate array (FPGA), realizes the function of measuring neutron, gamma spectra and dosage at the same time, suitable for mixing field
The measurement of son and gamma spectra and dosage；
2) measured while realizing neutron, gamma spectra and dosage based on FPGA technology, measuring system has small, knot
The advantages of structure is simple, easy to carry；
3) neutron dose is calculated based on spectroscopy, reduces constant error during measurement neutron dose；
4) by realizing that G (E) function method calculates gamma dosage on fpga chip, it is possible to reduce the sound of gamma dosage measurement
Between seasonable and relative error, the memory space of FPGA has been saved；
5) by depositing the neutron to be formed in neutron and gamma energy and being peeled off in gamma mixed tensor deposition spectrum by gamma
The electron spectrum that actinism produces, realizes the examination of neutron and gamma, improves the accuracy and accuracy of measuring method.
According to the disclosure and teachings of the above specification, those skilled in the art in the invention can also be to above-mentioned embodiment party
Formula carries out appropriate change and modification.Therefore, the invention is not limited in embodiment disclosed and described above, to this
Some modifications and changes of invention should also be as falling into the scope of the claims of the present invention.In addition, although this specification
In used some specific terms, but these terms are merely for convenience of description, do not limit the present invention in any way.
Claims (10)
1. the measuring method of a kind of nuclear power station neutron, gamma spectra and dosage, it is characterised in that comprise the following steps：
1) by neutron and gamma ray input neutron detection system output signal A, it is defeated that gamma ray is inputted into gamma detection system
Go out signal B；
2) signal A and signal B are inputted into digital signal processing circuit progress calculation process jointly and obtains neutron, gamma spectra and agent
Amount；
Wherein, digital signal processing circuit is using field programmable gate array chip as acp chip.
2. the measuring method of nuclear power station neutron according to claim 1, gamma spectra and dosage, it is characterised in that described
Neutron detection system includes neutron detector and the first analog-digital converter, after the neutron and gamma ray input neutron detector
The signal of output is the input signal of the first analog-digital converter, and the first analog-digital converter exports signal A.
3. the measuring method of nuclear power station neutron according to claim 1, gamma spectra and dosage, it is characterised in that described
Gamma detection system includes gamma detector and the second analog-digital converter, is exported after the gamma ray input gamma detector
Signal is the input signal of the second analog-digital converter, and the second analog-digital converter exports signal B.
4. the measuring method of nuclear power station neutron according to claim 1, gamma spectra and dosage, it is characterised in that described
Digital signal processing circuit obtains signal A acquisition process neutron and gamma mixed tensor deposition spectrum, and signal B acquisition process is obtained
Deposit and compose to gamma energy.
5. the measuring method of nuclear power station neutron according to claim 4, gamma spectra and dosage, it is characterised in that described
Arithmetic processing method includes in step 2)：Spectrum progress spectrum unscrambling is deposited to gamma energy and obtains gamma spectra；Gamma spectra is through gamma
Energy Response Matrix of the ray in plastic scintillant acts on obtaining gamma modeling sudden strain of a muscle energy deposition spectra；Neutron and gamma mixed tensor
Deposition spectrum deducts corresponding gamma modeling sudden strain of a muscle energy deposition spectra and obtains remaining proton spectra；Neutron energy is obtained to remaining proton spectra spectrum unscrambling
Spectrum；Finally by neutron dose and gamma dosage is calculated.
A kind of 6. measuring system of nuclear power station neutron, gamma spectra and dosage, it is characterised in that including：
Neutron detection system, including neutron detector and the first analog-to-digital conversion for being connected with the signal output part of neutron detector
Device；
Gamma detection system, including gamma detector and the second analog-to-digital conversion for being connected with the signal output part of gamma detector
Device；And
Digital signal processing circuit, using field programmable gate array chip as acp chip；
Wherein, the signal output part of first analog-digital converter and second analog-digital converter is respectively connected to digital signal
The signal input part of process circuit, the digital signal processing circuit is to first analog-digital converter and the second analog-digital converter
Output signal carry out calculation process.
7. the measuring system of nuclear power station neutron according to claim 6, gamma spectra and dosage, it is characterised in that described
Neutron detector includes the preposition amplification electricity of plastic scintillant probe, shielding shell, high voltage power supply, photomultiplier, charge-sensitive
Road.
8. the measuring system of nuclear power station neutron according to claim 6, gamma spectra and dosage, it is characterised in that described
Gamma detector includes NaI (Tl) scintillator probe, shielding shell, high voltage power supply, photomultiplier, the preposition amplification of charge-sensitive
Circuit.
9. the measuring system of nuclear power station neutron according to claim 6, gamma spectra and dosage, it is characterised in that described
Output signal acquisition process of the digital signal processing circuit to the first analog-digital converter obtains neutron and gamma mixed tensor deposition
Spectrum, the output signal acquisition process to the second analog-digital converter obtain gamma energy deposition spectrum.
10. the measuring system of nuclear power station neutron according to claim 9, gamma spectra and dosage, it is characterised in that described
Calculation process includes：Spectrum progress spectrum unscrambling is deposited to gamma energy and obtains gamma spectra；Gamma spectra is dodged through gamma ray in plastics
Energy Response Matrix in bright body acts on obtaining gamma modeling sudden strain of a muscle energy deposition spectra；Neutron and gamma mixed tensor deposition spectrum deduction pair
The gamma modeling answered dodges energy deposition spectra and obtains remaining proton spectra；Neutron energy spectrum is obtained to remaining proton spectra spectrum unscrambling；Finally by meter
Calculation obtains neutron dose and gamma dosage.
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