The technical field of the invention is spectrometry applied to the detection of ionizing radiation. This essentially involves X-ray or y-ray spectrometry.
Devices for detecting ionizing radiation, based on gaseous, semiconductor or scintillating detector materials, allow electrical pulses formed by interactions of the radiation in the detector material to be obtained. The amplitude of each pulse depends on the energy deposited by the radiation in the course of each interaction. These devices are usually coupled to spectrometric measuring circuits. The fields of application are broad, and comprise notably carrying out measurements on nuclear waste, equipment or installations, or radiological environmental monitoring.
Spectrometric measuring systems are nowadays widely used in industry. Software allows for parameterization of pulse processing, and automated measurement control and analysis.
However, some steps are difficult to automate, and still leave a large amount of room for manual adjustments. This involves for example energy calibration, or efficiency calibration, or certain measurement interpretations.
The invention described below facilitates the automation and repeatability of key steps relating to calibration or measurement analysis.
A first subject of the invention is a method for processing an X-ray or gamma-ray radiation spectrum formed by a spectrometric measuring device, the device comprising:
The reference activity may be 1 Bq.
According to one embodiment:
Sub-step c6 may comprise estimating a width of each peak of the input vector, each estimated width parameterizing the spectral dispersion matrix.
Sub-step c6 comprises estimating a position, among the channels, corresponding to the center of each peak of the input vector, each estimated position parameterizing the spectral dispersion matrix.
According to one possibility, the object contains calibration radionuclides the emission energies of which are known, the method comprising:
According to one embodiment:
Step c) may comprise taking into consideration an energy function, the energy function being such that:
Step c) may comprise taking into consideration a resolution function, the resolution function being such that:
The method may take into consideration a shape function, the shape function establishing an analytical relationship that models the shape of each peak of the detected spectrum.
A second subject of the invention is a device intended to acquire a spectrum of X-ray or gamma-ray photons emitted by an object, the object being likely to contain radionuclides, the device comprising:
A third subject of the invention is a medium, able to be connected to a computer, comprising instructions for implementing step c) of a method according to the first subject of the invention based on a spectrum resulting from a spectrometric detector. The medium may be integrated into a computer or connected to a computer by a wired or wireless link.
The invention will be better understood on reading the description of the exemplary embodiments that are presented, in the rest of the description, with reference to the figures listed below.
Ionizing radiation is understood to mean X-ray or gamma-ray photonic radiation formed of photons the energy of which is for example between 1 keV and 2 MeV.
In the example shown, the detector comprises a germanium (Ge) semiconductor material, but a semiconductor material commonly used to detect ionizing photons, for example Si, CdTe, CdZnTe, could also be involved. The photons forming the incident radiation form interactions in the detector material. The detector material is subjected to a bias voltage V. Each interaction generates charge carriers, which are collected by an electrode, generally an anode.
Other types of detectors, for example scintillators coupled to a photon/charge carrier converter, or a gas detector such as an ionization chamber, may be used, provided that they allow the collection of a quantity of charges Q under the effect of an energy E released by the ionizing radiation in the course of an interaction in the detector 10. Among the usual scintillator detectors, mention may be made of NaI(Tl) or LaBr3.
The detector 10 is connected to an electronic circuit 12 that is configured to generate a pulse the amplitude of which depends on, and is preferably proportional to, the quantity of charge collected during an interaction. The quantity of charge corresponds to the energy deposited by the radiation in the course of the interaction.
The electronic circuit 12 is connected to a spectrometry unit 13 that is arranged downstream of the electronic circuit and that makes it possible to collect all of the pulses formed during an acquisition period. Each pulse corresponds to an interaction of the incident radiation in the detection material. The spectrometry circuit then classifies the pulses as a function of their amplitude A so as to provide a histogram containing the number of pulses detected as a function of their amplitude. This histogram is an amplitude spectrum. It is usually obtained using a multichannel analyzer. Each amplitude is discretized by channel, each channel being assigned an amplitude band. The value of each channel of the spectrum corresponds to a number of pulses the amplitude of which is within the amplitude band assigned to the channel. Each amplitude band corresponds to an energy band, the correspondence being bijective. Each channel is thus assigned an energy band or an amplitude band.
The relationship between amplitude and energy may be established by irradiating the detector using a calibration source, emitting radiation the energy of which is known. This in particular involves radiation having at least one discontinuity, or energy peak, at a known energy value. This operation is usually denoted by the term energy calibration. For example, in gamma-ray spectrometry, the detector is exposed to a 152Eu calibration source, producing photons at known emission energies. It is also possible to use a 137Cs source, producing mostly photons the energy of which is 661.6 keV. It is also possible to use a 60Co source producing photons the energy of which is mostly 1173 keV and 1332 keV. The energy calibration makes it possible to establish an energy function ƒe that makes it possible to establish an analytical relationship between amplitude and energy. Taking into consideration the energy function ƒe makes it possible, by changing variable, to obtain an energy spectrum y from an amplitude spectrum yA.
The spectrum y corresponds to a histogram of the amplitudes of each detected pulse, discretized by energy or amplitude channels. Each channel is assigned an energy band, for example [401, 402] keV. The spectrum y may be expressed in the form of a vector (y1, . . . yi . . . , yn), where n corresponds to the total number of channels. Each channel is assigned a rank i, with 1≤i≤n.
Each channel of rank i is delimited by a lower amplitude Ai and an upper amplitude Ai+1, such that a detected pulse is assigned to the channel of rank i when its amplitude is between A, and Ai+1.
The lower amplitude Ai of each channel corresponds to a lower energy ei. The upper amplitude Ai+1 of each channel corresponds to an upper energy ei+1. The amplitude-energy correspondence is established by the energy function ƒe. Thus,
β is a set of parameters of the energy function ƒe, described below.
The variable
corresponds to a relative position of the channel in relation to the maximum number of channels of the spectrum. This is a normalized rank of each channel, between 0 (i=1) and 1 (i=n+1). Normalization makes it possible to establish an energy function ƒe independent of the number of channels n, the latter being able to be parameterized.
The energy function may be polynomial. For example, it may be a linear function, in which case β=(β0, β1) and
It may be a 2nd-degree polynomial function, in which case
The vector β is either assumed to be known, following an energy calibration operation on the detector, or estimated based on a spectrum of the radiation emitted by a calibration object the composition of which is known. Optionally, the device comprises a collimator 16 that is intended to restrict the field of observation of the detector. The collimator generally comprises a gamma ray photon-attenuating material, for example lead or a tungsten-containing alloy.
In the example shown, the detector 10 is connected to a cryostat 18 comprising liquid nitrogen in order to keep the Ge detector at an operating temperature.
The device comprises a processing unit 14 that is programmed to implement steps of algorithms described with reference to
A description will now be given of the various variables that are used in processing operations implemented by the processing unit 14 and that are described below.
The objective of a gamma-ray spectrometry measurement is to identify the radionuclides 2j present in the object 2 and, preferably, to estimate their respective activities.
The spectrum y that is shown contains multiple peaks, each peak corresponding to an emission energy Ek of a radionuclide present in the object 2. These peaks form the useful information of each spectrum, based on which it is possible to identify radionuclides and quantify their respective activities. The spectrum also contains a continuum c, corresponding to photon scattering in the detector or before said photons reach the detector. The continuum corresponds to that portion of the spectrum below and between each peak. In
The spectrum y may thus be decomposed as follows:
where y, m, c and b are vectors of dimension (1,n).
The information relating to the peaks is contained in the vector m, which forms the useful component of the spectrum y. The vector m contains all of the peaks of the spectrum y: it is a vector representative of the mixture of the peaks of the spectrum y. The vectors m and y have the same dimension.
A description will now be given of various embodiments, including processing of the measured spectrum y. One step in common to the various embodiments is that of extracting the useful component m from the spectrum y.
The continuum c may be estimated by implementing a baseline suppression algorithm, as described in the publication This K. et al “Contribution to continuum estimation in gamma spectrum by observation by local minima”. This thus gives:
y−ĉ=m+b (6)
where c is the estimate of the continuum.
As an alternative, the vector m may be established using dedicated software for individual extraction of spectrometry peaks, by baseline suppression or estimation. The vector m may result from a concatenation of each peak individually extracted from a measured spectrum.
It will be considered below that the object potentially consists of q radionuclides 2j, the respective activities of which are a1 . . . aj . . . aq, forming an activity vector a of dimension (q,1). A list of the q radionuclides potentially present in the object is drawn up beforehand. It includes all gamma ray-emitting radionuclides likely to be present in the object. The radionuclides in the list emit photons at energies E1 . . . Ek . . . Ep. The energies E1 . . . Ek . . . Ep correspond to the set, without duplicates, of the emission energies of the q radionuclides, classified in ascending order. A portion of this set, for example limited to energies for which the emission intensities are considered to be sufficient, may also be involved. Each radionuclide j with an activity equal to 1 Bq generates an energy Ek with an intensity Ijk. The intensity Ijk is non-zero when the index k corresponds to an emission energy Ek of the radionuclide.
The vector m is formed by a contribution uj of each radionuclide present in the object. uj is a vector of dimension (1, n), each term uji of which corresponds to a quantity of photons emitted by the radionuclide j and detected in the channel i, with 1≤j≤n. Thus,
Under the effect of imperfections in the detector 10 or in the circuit 12 or in the spectrometry unit 13, an interaction that releases an emission energy Ek may be detected not only in the channel of rank k corresponding to the energy Ek, but in other adjacent channels, by a dispersion effect of the energy estimated by the device. This is reflected in that a peak does not correspond to a Dirac distribution centered on the channel of rank k corresponding to the energy Ek, but to a peak, of a certain area sk, on either side of the channel of rank k.
Spectral dispersion is expressed as a full width at half maximum wk of the peaks at each emission energy Ek, with:
The resolution function may take various parametric forms, for example:
In addition to the full width at half maximum, the spectral dispersion may also be modeled by the shape of the peaks. The shape of the peaks may be taken into consideration by a shape function ƒs, which characterizes the shape of the peaks. The shape function is determined a priori, for example on the basis of feedback or previous tests. In the examples described below, the shape function ƒs is considered to be Gaussian. For example,
Taking into consideration the full width at half maximum wk and the shape function ƒs, it is possible to determine a probability dik of a photon releasing an energy Ek in the detector being detected in a channel of rank i with:
where:
Fs is a primitive of ƒs.
The probability dik is defined for all of the p emission energies Ek (1≤k≤p) along with all of the n spectral channels (1≤i≤n). Based on the various probabilities dik, it is possible to form a spectral dispersion matrix D, of dimension (n,p), each term D(i,k) of which is such that D(i,k)=dik.
The spectral dispersion matrix D assumes the prior definition of the resolution function ƒr, parameterized by α, of the shape function ƒs and also of the energy function ƒe, parameterized by β. The spectral dispersion matrix corresponds to a spectral response of the detector. A spectral response is understood to mean the function modeling the shape of a peak as a function of energy.
As an alternative, the spectral dispersion matrix may be established on the basis of modeling of the detector, with a possible readjustment carried out on the basis of experimental measurements. It may also be determined experimentally, in particular when the detector is intended to be used repeatedly on the same radionuclides.
In the course of certain steps that are described below, a previously established matrix of reference spectra S of dimension (q,p) is taken into consideration, each term S(j,k) of which is the area of a spectral peak, of energy Ek when a radionuclide j is present, in the source, with a predetermined activity. The predetermined activity is for example a unit activity: 1 Bq for each radionuclide. Each term S(j,k) thus corresponds to a quantity of photons detected in a peak centered on an emission energy Ek for a unit activity of the radionuclide 2j. The reference matrix S is of dimension (q,p).
εk is an observation efficiency of the device at the energy Ek. εk corresponds to the number of photons detected in a peak centered on the energy Ek, divided by the number of photons emitted by the object at this energy. The observation efficiency εk is obtained by calibration, for example by arranging standard sources the radionuclides and activity of which are known, in a calibration object representative of the object to be measured. Determining the observation efficiency may also involve modeling using computing codes, in particular based on Monte Carlo methods (MCNP for example).
It is possible to form an observation efficiency vector E, of dimension (p,1), each term Ek (1≤k≤p) of which is the observation efficiency at the energy Ek. The observation efficiency E may be considered to be a product of two vectors:
The matrix of reference spectra S corresponds to an efficiency response of the detector. An efficiency response is understood to mean the function modeling a ratio between the pulses detected in a peak associated with an energy and the number of photons emitted by the source at said energy.
The objective of this first embodiment is to process the measured spectrum y in order to estimate the activity aj of each radionuclide 2j likely to be present in the object under test.
The main steps of this embodiment are shown schematically in
The vector m+b is for example estimated by carrying out the subtraction:
ĉ may be estimated using a baseline estimation algorithm as described above.
U is a matrix of dimension (n,q), each term uij of which is a contribution of a radionuclide j, of activity 1 Bq, in the photons detected in the channel i.
The transfer matrix U corresponds to a response function of the detector, for the radionuclides j under consideration. It may also take into consideration the presence of screens between the detector and the radionuclides. The spectral response function corresponds to the matrix D, and the efficiency response function corresponds to the matrix S.
Taking into consideration a transfer matrix U adapted to certain predetermined radionuclides makes it possible to form a matrix one of the dimensions of which is reduced.
During this step, it is sought to estimate a vector a each term of which is an activity aj of the radionuclide j in the measured object. m and a: are linked by the direct model:
An optimization algorithm for minimizing a cost function J is implemented so as to estimate the vectors a, b and, optionally, the scalar kD.
a is a vector of dimension (q,1).
The cost function J may be such that:
where θ corresponds to unknown variables governing the cost function: these are a and optionally kD when m contains a peak centered on 511 keV. When m does not contain a peak on 511 keV, kD takes an arbitrary value. ∥ ∥ denotes the L2 norm operator. Minimizing the cost function makes it possible to estimate the unknowns θ using the expression:
The estimates of m and a are combined due to the relationship m=Ua.
According to another possibility, it will be assumed that J(θ) follows a normal law with respect to θ, in which case the cost function may be such that:
W is a diagonal matrix of dimension (n,n) each term of which is the inverse of the variance of the observation noise assigned to each channel of the vector y. For example, for each channel i,
Regardless of the cost function used, constraining the minimization
by imposing m=Ua, the matrix U being predetermined, facilitates the implementation of the inversion algorithm. Therefore, the formulation of a direct model, in the analytical form m=Ua, allows the joint estimation of m, a and optionally kD.
The objective of the second embodiment is to process a measured spectrum y, during a calibration, so as to extract peaks and estimate at least one parameter, chosen from among the position, the area and the full width at half maximum, of the peaks present in the vector m. According to this embodiment, the object is any object. Unlike the first embodiment, the energy function ƒe and resolution function ƒr are not assumed to be known. The same applies for the observation efficiency E. Therefore, the steps described below are implemented for the purposes of calibrating the detector.
The main steps of this embodiment are shown schematically in
The vector m+b is for example estimated by carrying out the subtraction:
ĉ may be estimated using a baseline estimation algorithm as described above. Step 220: taking into consideration a spectral dispersion matrix D′ of dimension (n,p), each term of which is such that
In this embodiment, the spectral dispersion matrix D′ forms the transfer matrix for the method, taking into consideration an arbitrary energy function, such that: ei=i−1: one channel is equivalent to 1 keV.
wc,k corresponds to the full width at half maximum of the peak of rank k, expressed in channels; the variables wc,k for each peak form a vector we of parameters of the matrix D′.
Ec,k is a channel of the spectrum corresponding to the position of the center of the energy peak Ek. Ec,k is a real number, between 0 and n+1. Ec,k may be between two successive ranks k and k+1. The channels Ec,k corresponding to each peak form a vector Ec of dimension (1,p). p denotes the number of peaks detected. The vector Ec is a vector of parameters of the matrix D′.
The spectral dispersion matrix D′ may be considered to be an initial spectral dispersion matrix, used prior to determining the energy function of the detector. The initial spectral dispersion matrix D′ is established analogously to the matrix D described above, taking into consideration a simplifying arbitrary energy function according to which each channel corresponds to 1 keV.
Unlike the first embodiment:
During this step, the direct model is taken into consideration:
where:
The vector s may be estimated by implementing an optimization algorithm, for example as described in step 150, which leads to obtaining an estimate ŝ together with the estimate of m.
The optimization algorithm makes it possible to minimize a cost function J so as to determine the vectors s and m and the vectors of parameters wc and Ec.
Just as in the first embodiment, an optimization algorithm for minimizing a cost function J is implemented so as to determine s, wc and Ec.
The cost function may be such that:
where θ corresponds to unknown variables governing the cost function: these are s and wc and Ec. ∥ ∥ denotes the L2 norm operator. Minimizing the cost function makes it possible to estimate the unknowns θ using the expression:
Regardless of the cost function used, constraining the minimization
by imposing m=D′s, the matrix D′ being conditioned, facilitates the implementation of the inversion algorithm.
The vector wc makes it possible to define the resolution function ƒr, according to expression (3), using the energy function ƒc, establishing the channel/energy relationship.
The vector Ec may be used during energy calibration, in particular to determine the energy function ƒe described above, establishing a channel/energy relationship. It is possible to take into consideration a threshold beyond which each channel, corresponding to an emission energy Ek, is considered to contain a significant quantity of detected photons. The ranks of the channels for which the value sk is greater than the threshold are extracted. The selected channels may be confronted with the emission energies of the radionuclides present in the calibration object. This thus gives various channel-energy pairs that may be used to determine the energy function ƒe.
For example, the ranks of the selected channels may be classified in ascending order, as may the emission energies, so as to associate an emission energy with each channel: the channel with the lowest rank is associated with the lowest emission energy—the channel with the highest rank is associated with the highest emission energy. The energy function ƒe has a predetermined parametric form, for example a polynomial one. The parameters of the energy function (coefficients of the polynomial) are adjusted on the basis of the various channel-energy pairs.
It should be noted that this embodiment makes it possible to carry out a calibration in a highly automated manner, without having to carry out manual or computer-aided delimitation of the peaks forming the spectrum y.
The objective of the third embodiment is to process a measured spectrum y during a calibration so as to:
In this embodiment, the object may be a calibration object, comprising sources the radionuclides and associated activities of which are known. When the absorption efficiency εa is known, the method makes it possible to estimate h. Otherwise, the method makes it possible to estimate E.
When the activities of the radionuclides is unknown, the method makes it possible to extract the areas of the peaks forming the vector m.
The main steps of this embodiment are shown schematically in
The vector m+b may be estimated by carrying out the subtraction:
ĉ may be estimated using a baseline estimation algorithm as described above.
The spectral dispersion matrix D is parameterized by: β, α, kD.
U′ is a matrix of dimension (n,p), each term u′ik of which is an estimate of the number of photons detected in each channel of rank i, taking into consideration the activity of the calibration radionuclides, and a detection efficiency, at each energy, equal to 1. U′ is conditioned by β, α, kD.
When the activity of the radionuclides is not known, s′k=1 is imposed.
The direct model may be established:
The vector h is estimated by implementing an optimization algorithm, for example a maximum likelihood algorithm, which leads to obtaining an estimate ĥ. Each term ĥk of the vector h corresponds to a detection efficiency at the energy Ek, between 0 and 1.
Regardless of the cost function used, constraining the minimization
by imposing m=U′h, the matrix D being conditioned, facilitates the implementation of the inversion algorithm. The vector h thus estimated may be used to establish the matrix of reference spectra U by combining expressions (13) and (14).
The vectors m, β, α, h and the optional scalar kD are determined by implementing an optimization algorithm, as described in the first and second embodiments.
When the absorption efficiency εa is not known, it is assigned a unit value at each energy. Expression (14) becomes:
The method then makes it possible to determine β, α, E and the optional scalar kD.
The method makes it possible to simultaneously carry out an energy calibration, a resolution calibration and an efficiency calibration.
According to one possibility, the method may comprise:
Although it has been described in connection with nuclear waste, the invention may be applied to the inspection of any other object: equipment or structure of a nuclear installation, fresh or irradiated fuel, or sample taken from the environment.
Number | Date | Country | Kind |
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FR2114707 | Dec 2021 | FR | national |
Filing Document | Filing Date | Country | Kind |
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PCT/EP2022/088054 | 12/29/2022 | WO |