EP3274863A1 - Procede et dispositif pour detecter des radioelements - Google Patents
Procede et dispositif pour detecter des radioelementsInfo
- Publication number
- EP3274863A1 EP3274863A1 EP16711607.8A EP16711607A EP3274863A1 EP 3274863 A1 EP3274863 A1 EP 3274863A1 EP 16711607 A EP16711607 A EP 16711607A EP 3274863 A1 EP3274863 A1 EP 3274863A1
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- EP
- European Patent Office
- Prior art keywords
- energy
- model
- distribution
- priori
- law
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Classifications
-
- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
- G01T1/16—Measuring radiation intensity
- G01T1/17—Circuit arrangements not adapted to a particular type of detector
- G01T1/178—Circuit arrangements not adapted to a particular type of detector for measuring specific activity in the presence of other radioactive substances, e.g. natural, in the air or in liquids such as rain water
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06F—ELECTRIC DIGITAL DATA PROCESSING
- G06F17/00—Digital computing or data processing equipment or methods, specially adapted for specific functions
- G06F17/10—Complex mathematical operations
- G06F17/18—Complex mathematical operations for evaluating statistical data, e.g. average values, frequency distributions, probability functions, regression analysis
Definitions
- the object of the invention relates to a method and a device for detecting radioelements contained in an object, to determine their nature and their activity. In particular, it makes it possible to take into account spurious effects originating from the environment in which the object to be analyzed is located.
- Gamma spectrometry is a technique for detecting gamma radiation emitted spontaneously by radioelements. This technique makes it possible to identify gamma emitting radioelements and to measure their activity. To achieve qualitative and quantitative objectives, the treatment of a gamma spectrum is based on the analysis of the peaks present in the spectrum. These correspond to the gamma radiation emitted by a specific radioelement, for example 137 Cs emitting a gamma at 661.5 keV or 60 Co emitting a gamma at 1173.2 keV and a gamma at 1332.5 keV.
- the presence of a peak in a gamma spectrum means that the energy of the incident gamma radiation has been fully absorbed in the detector, following one or more interactions, photoelectric effect, Compton effect or pair production, occurring within this last.
- the detectors used to perform gamma spectrometry measurements can be separated into two categories: scintillators and semiconductors.
- the quality of a gamma spectrum can be evaluated by two parameters specific to the detector used: the energy resolution, that is to say the ability to separate two near peaks in energy defined as the half-height width of the detector. a peak present in the spectrum at a given energy, and the detection efficiency, the denser the material, the greater the probability of absorbing all of the incident gamma radiation. These two parameters vary significantly depending on the detector used.
- FIG. 1 shows, in a channel energy diagram, blow per channel, an example of spectrum S (1) obtained using an HPGe detector and a 137 Cs source emitting gamma radiation at 661, 5 keV.
- Figure 2 compares S (HPGe), S (CZT), S (Nal) spectra obtained using a uranium sample and different types of detectors, with different performance in terms of energy resolution.
- FIG. 3 shows a spectrum S (II) obtained using a plastic scintillator of the EJ200 type, in the presence of 60 Co and 137 Cs sources. The characteristic forms of these spectra are due to the Compton fronts following the interactions within the detector. It can thus be noted the absence of the photoelectric peaks characteristic of the presence of 137 Cs and 60 Co.
- these detectors are generally used to perform total count measurements, detection of all the gamma radiation interacting within the detector without information on their energy.
- a traditional approach consisting of measuring the net area of the different peaks of interest is therefore not possible and an alternative solution must be used if it is desired to identify the radioelements present in the spectrum.
- a solution for treating a gamma spectrum, identifying the radioelements transmitters and measure the activity of the latter, is to analyze the spectrum as a whole and not to restrict only to the analysis of the photoelectric peaks.
- the approach followed is to express spectrum analysis in the following matrix form:
- nbre_energy_incidents a signal matrix, matrix of dimensions (number_channels, 1), where the variable number_channels is equal to the number of channels of the gamma spectrum
- A an activity matrix, matrix of dimensions (nbre_energies_incidents, 1).
- the variable nbre_energies_incidentes corresponds to the number of incident energies defined by the user and taken into account in the reconstruction. These incident energies correspond to the number of elementary volume elements of a classical problem of emission tomography,
- H a projector of the problem, matrix of dimensions (number_channels, number_energies_incidentes). This matrix includes all the detection efficiencies involved in the problem. By way of example, an element hij of this matrix corresponds to the probability that a photon of incident energy j is detected in channel i of the gamma spectrum.
- the signal matrix S corresponds to the result of the measurement, to the gamma spectrum to be analyzed, the projector matrix is generally calculated by simulation, the matrix A corresponds to the result of the reconstruction.
- FIG. 4A and FIG. 4B illustrate an example of the H projector concept, for an incident energy of 660 keV, FIG. 4A.
- the spectrum S (IV) of FIG. 4B corresponds to the incident energy corresponding to an entire column of the projector H.
- the projector thus contains the spectral response of the detector for each incident energy taken into account in the problem and defined by the user. . It is on this grid of incident energies that the reconstruction step will be carried out.
- FIGS. 5 and 6 represent the gamma spectrum to be analyzed, corresponding to a simulation of the response of a plastic scintillator type EJ200, in the presence of three gamma sources ( 241 Am, 137 Cs, 60 Co).
- the reconstructed spectrum Sr from the results of the analysis and the incident energies is shown in dashed lines in the figure.
- FIG. 6 illustrates the result of a reconstruction carried out using an ML-EM type algorithm, the incident energies reconstructed from the spectrum of FIG. 5.
- the latter is generally obtained following a simulation step, using a model describing the detector used and its environment. Nevertheless, it is generally difficult to arrive at a fine modeling, knowledge of the geometry of the detector, limitations of the code of computation which model only imperfectly the interactions within the detector, absence of taking into account of certain physical phenomena, as the collection of visible photons for example in the case of plastic scintillators. If the modeling of the detector and / or the environment is imperfect, a more or less important bias will be present during the reconstruction.
- Another approach, rather than considering a grid of incident energies on which one would perform the reconstruction is to use a database.
- we no longer simulate a grid of incident energies, but directly the signature of a given element, for example for the 60 Co we will directly simulate the response of the detector for two incident energies, emitted respectively at 1173.2 keV and 1332.5 keV.
- the reconstruction is performed directly on a grid of radioelements. It also has the advantage of converging faster than the grid approach, because the number of components to be taken into account is lower.
- One of the disadvantages of this method is its limitation to take into account only the radioelements initially present in the database. If the analysis of a gamma spectrum involves a radioelement missing from the database, the reconstruction will be erroneous.
- the invention relates to a method for determining the nature of the radioelements present in an object and their activity, characterized in that it comprises at least the following steps: A first phase of numerical simulation of spectrometric responses for a set of incident energy E and a set of measured output energy E ', in order to obtain a set of simulated data,
- a second phase of non-parametric regression on the simulated data nonparametric estimation of the quantity representing the joint probability of the triples (E, E ', y) from simulated points (Ei, Ei', yij) in order to deduce a meta-model S (E, E ') for any energy pair (E, E') on a continuous function
- the method comprises the following steps:
- the values ⁇ £ can be determined ; - using Monte-Monte software
- ⁇ ⁇ ⁇ , ⁇ 2 represents the Gaussian law of ⁇ and variance ⁇ 2 , ⁇ 2 ⁇ ⁇ ⁇ , ⁇ ) the bivariate Gaussian law of mean ⁇ GR 2 and covariance matrix ⁇ , where
- the a priori law of the parameter 3 ⁇ 4 is a Gaussian
- the variance r k is distributed according to a inverse-gamma law
- ifj k follows a Bernoulli-type prior distribution
- the a priori for the coefficients of regression coefficients k is a normal distribution (Gaussian) multivariate of dimension
- the approximation scheme may include a wafer sampling step using a finite random number ⁇ of components for each iteration and including the following steps:
- the method may include a step of calculating the posterior standard deviation and credible intervals from the set ⁇ S ⁇ E, E ') ⁇
- a Gamma a priori ( ⁇ p fc , 3 ⁇ 4) is introduced on the scale parameters b T and b ' T in the distribution of the amplitudes of components leading to a Gamma a posteriori distribution:
- the method generates an extended meta-model denoted ⁇ ( ⁇ , ⁇ ' , ⁇ ) where ⁇ is a parameter identified by an integer index and characteristic of a matrix effect.
- the method can estimate the activity of radioelements by performing the following steps:
- k l
- p is a positive parameter for converting the channel index into energy (keV / channel).
- the posterior standard deviation of activities is calculated by performing the following steps:
- FIG. 1 an example of a gamma spectrum obtained with an HPGe detector
- FIG. 3 an example of a spectrum obtained using a plastic scintillator
- FIG. 4a and FIG. 4B an example of energy incident at 660 keV and the spectrum measured by a plastic scintillator corresponding to this incident energy
- FIG. 5 an example of a gamma spectrum to be analyzed and a spectrum reconstructed according to the prior art
- FIG. 6 the energies reconstructed from the spectrum presented in FIG. 5,
- FIG. 7 an example of a system for implementing the method according to the invention
- FIG. 8 a block diagram of the steps implemented by the method according to the invention.
- FIGS. 9 and 10 an example of a spectrum of the incident energies obtained by the process according to the invention.
- FIG. 7 is an example of a system for implementing the method according to the invention.
- the system comprises an object 10 which is capable of spontaneously emitting gamma radiation due to the presence of radioactive elements.
- the gamma radiation is received by a device 20 comprising a radiation detection module, 21, connected to an acquisition electronics making it possible to obtain a spectrum, a processor 23 or computer unit adapted to perform the steps of FIG. method according to the invention, processing the data of the spectrum obtained, a display module 24 of the results, a storage means 25 for saving the results, for example.
- the storage means can also store incident energies defined by a user in the context of a given application.
- the method according to the invention is based in particular on a use of all the information present in the spectrum to be analyzed in order to carry out a succession of iterative steps of deconvolution of the incident spectrum.
- the method uses a continuous projector or meta-model.
- the response of the spectrometry system will be sought by a simulation technique by calculating whenever necessary the complete energy response of the system for a given configuration of the input spectrum.
- We will search for the system's answer in the form of a discrete spectrum whose support (incident energies) is a continuous space.
- This continuous model will make it possible to calculate the response of the spectrometry system for any incident energy E and any observed output energy E ', meta-model denoted S (E, E').
- a Bayesian reconstruction step uses the meta-model to determine the radioelements contained in the object to be analyzed.
- the method will comprise a first phase during which a numerical simulation of spectrometric responses S, 32 will be carried out for a grid of incident energies Ei, 31, followed by a second phase in which a non-parametric regression is applied. (statistical prediction), 33, on the simulated data.
- a numerical simulation of spectrometric responses S, 32 will be carried out for a grid of incident energies Ei, 31, followed by a second phase in which a non-parametric regression is applied. (statistical prediction), 33, on the simulated data.
- one will inject, for example of the physical knowledge, 34, in the form of a priori to guide the regression in regions of the incident energy where one does not have data simulated. In essence, this makes it possible to indicate that on restricted domains of energy, the signature of the spectral response has either characteristics proportional to the input energy, or constant regardless of the input energy E ,.
- the chosen regression model being a non-parametric model, the method does not assume any linear or polynomial model and can thus be adapted to any what non-linearity in the answer.
- the method will seek to estimate a continuous function of E 2 in
- n the number of points in the input grid (energy E) and n 'number of points in the output grid (£ energies ")
- E measured data
- the method according to the invention is based on the non-parametric estimation of the quantity f ⁇ E, E y), representing the joint probability density of the triplets ⁇ E, E y) from the simulated points ( ⁇ , ⁇ , ⁇ ⁇ ), in order to deduce the model 5 (£ " , £") for all (£, £ ") E KL 2 where IL is a continuous space:
- E (y) represents the expected value of the random variable y
- this symbol represents a statistical expectation used later in the description to characterize the intensity of an energy in the spectrum.
- DPM Dirichlet process
- DP (a, G 0 ) represents the distribution of a Dirichlet process (Hjort NL, Holmes C, Miiller P, Walker SG, Ghosal S, Lijoi A, Prunster I The YW, Jordan MI, Griffin J, DB Dunson and Quintana F 2010 Bayesian Nonparametrics Cambridge Series in Statistical and Probabilistic Mathematics) with a mean G 0 and a parameter called concentration.
- This probability distribution on random probability distributions plays a central role in non parametric Bayesian modeling.
- a common representation of DP comes from Sethuraman (1994) who expresses the random measure G (-) as:
- U (-) represents the Dirac function located in u.
- 9 k ⁇ G 0 represent the parameters associated with the k th component of G.
- the nonparametric character is derived from the number of potentially infinite component intervening in the sum characterizing the a priori on G.
- the distribution Beta (a, b), is defined for 0 ⁇ x ⁇ 1:
- f (E, E, y) ⁇ w k fo k ⁇ E, E ' , y)
- fe k denotes the k th component of f ⁇ E, E, y), parameterized by 9 k .
- X k ⁇ E) (l, E - ⁇ ⁇ ⁇ ' - ⁇ ' 3 ⁇ 4 )
- v T represents the transpose of the vector v) or polynomial in the DPGLM approach
- X K ( ⁇ ) (l, E - ⁇ ⁇ ⁇ - - ⁇ 3 ⁇ 4 ) (£ - ⁇ ' 3 ⁇ 4 ), (£ - ⁇ ⁇ 2 , (E - ⁇ ' k )) for a quadratic regression
- ⁇ ⁇ ⁇ , ⁇ 2 represents the Gaussian law of ⁇ and variance ⁇ 2 , ⁇ 2 ⁇ ⁇ ⁇ , ⁇ ) the bivariate Gaussian law of mean ⁇ GE 2 and covariance matrix ⁇ .
- a multivariate Gaussian distribution ⁇ ⁇ ( ⁇ , ⁇ ) is defined for XGR p ,
- the pr / or / G 0 measurement of the Dirichlet process is chosen as follows.
- the a priori law of the parameter 3 ⁇ 4 is a Gaussian
- the variance r k is distributed according to a inverse-gamma law
- ifj k follows a Bernoulli-type prior distribution
- the a priori for the coefficients of regression coefficients ⁇ ⁇ is a law normal (Gaussian) multivariate dimension
- the method uses, for example, a Gibbs sampler Markov Chain Monte Carlo (MCMC) scheme to generate samples of the target law.
- MCMC Gibbs sampler Markov Chain Monte Carlo
- the method adopts a so-called slice sampling approach according to Kalli et al. (Kalli M, Griffin JE and Walker SG 201 Slice Sampling Mixture Models, Statistics and Computing, 21, 93-105), where only a finite random number K of components is required at each iteration.
- This generative model is entirely equivalent to the probability density a priori f (w 1 , w 2 , ..., ⁇ ⁇ , ⁇ 2 , ...), and corresponds to a priori of the Dirichlet process type for the measurement.
- the nonparametric behavior of the process is characterized by the potentially infinite collection of parameters w k and 9 k .
- the denoised spectral response can, optionally, share or not the same grid (E £ , E) as the initial physical Monte-Carlo simulation. Indeed, the user can choose any point (£, £ ") of interest, in particular, it is possible to interpolate between the points of the initial grid.
- the hyper parameters can be considered fixed in the estimation of the response of the spectrometric system according to prior physical knowledge on the detector. On the other hand, these can be estimated by means of an additional level of hierarchy which allows them to be assigned a so-called vague a priori.
- the method has a continuous meta-model characterizing any type of detector for nuclear spectrometry, the meta-model taking into account all the physical interactions involved in the spectral response for an energy. given input.
- the meta-model thus generated could be injected into a nuclear spectrum convolution method using non-parametric probabilistic modeling such as that proposed by Barat et al 2007 (Barat, E., Dautremer, T., Montagu, T., "Nonparametric Bayesian Inference in Nuclear Spectrometry, "Nuclear Science Symposium Conference Record, 2007. NSS '07 .I EEE, vol.1, no., pp.880-887, Oct. 26, 2007-Nov. 3, 2007), to determine the radioelements present in the spectrum and their activity.
- spectral signature shape variations due to the presence of matrix effects at the input source may occur.
- the meta-model defined according to the invention can take into account several spectral responses estimated as has been explained above. For this, a solution is for example to use different shields of different thicknesses and different materials, to be simulated and intervene in the meta-model.
- Another solution is to conserve a Polya tree to model the diffuse interactions leading to continuous bottoms that may not be modeled in the response. Assuming that the meta-model takes into account a collection of matrix effects as previously described, the desired input spectrum then consists only of discrete peaks. It is then possible to substitute a priori Dirichlet process on mono-energetic lines, a priori Dirichlet process on radioelements of a database of radionuclides. The spectrum sought is then constituted by a discrete sum of elements of the periodic table whose number of components is unlimited. It then becomes possible to assign to each radioelement a prior probability of presence in the sample analyzed. The meta-model is again used to characterize the spectral response of the detector of the considered element.
- This response is directly determined by the discrete sum of the individual spectral responses corresponding to each monoenergetic line considered.
- the use of a radionuclide database makes it possible, in particular, to consider the energy calibration of the spectrum observed as uncertain and to estimate it from the data. For each proposed value of keV / channel it is necessary to evaluate the spectral response of the system for each energy of the output grid. This operation uses the continuous meta-model, eliminating the need for interpolations when using a discrete model.
- meta-model takes into account a collection of matrix effects
- ⁇ represents a parameter characteristic of the matrix effect associated with the source.
- the collection of matrix effects is discrete of size M and each element ⁇ is identified by an integer index.
- the activity estimation algorithm is based on a Markov Chain Monte Carlo (MCMC) approach and more particularly on a Gibbs sampler, an example of which is detailed below.
- MCMC Markov Chain Monte Carlo
- This Dirichlet process mixture is based on the probability measurement F generated by a Dirichlet process:
- F ⁇ DP (a, F ° XF ⁇ ) ⁇ ⁇ ) s j (x) represents the probability distribution a priori to observe an element ⁇ where / is the number of radionuclides of the base selected for the analysis and p °> 0.
- F ° is the discrete uniform prior law on the matrix effects collection, and a is the (positive) process concentration parameter:
- the Gibbs sampler consists in alternating random draws according to the following conditional laws, for all i ⁇ n,
- the algorithm allows the estimation of keV / channel conversion gain from only the data as well as the determination of a (potentially different) matrix effect for each element involved in the mixture. It also makes it possible to set a prior probability of the occurrence of radionuclides in the context under consideration and to obtain directly the activities of the constituent elements of the mixture as well as the associated uncertainties.
- Figures 9 and 10 illustrate the spectrum of the energies obtained from the spectrum analysis of Figure 10 using the method according to the invention.
- the dotted curve represents the simulated spectrum, the solid curve the reconstructed spectrum.
- Figures 1 1 and 12 illustrate a second example of spectrum.
- Figure 11 shows the spectrum of incident energies, with an emission region of the first peak at 60 Co, 1173.2 keV.
- Figure 12 the same spectrum with a zoom on the region of interest.
Abstract
Description
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Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1552415A FR3034221B1 (fr) | 2015-03-24 | 2015-03-24 | Procede et dispositif pour detecter des radioelements |
PCT/EP2016/056208 WO2016150935A1 (fr) | 2015-03-24 | 2016-03-22 | Procede et dispositif pour detecter des radioelements |
Publications (1)
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EP3274863A1 true EP3274863A1 (fr) | 2018-01-31 |
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ID=54366251
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
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EP16711607.8A Withdrawn EP3274863A1 (fr) | 2015-03-24 | 2016-03-22 | Procede et dispositif pour detecter des radioelements |
Country Status (4)
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US (1) | US20180059259A1 (fr) |
EP (1) | EP3274863A1 (fr) |
FR (1) | FR3034221B1 (fr) |
WO (1) | WO2016150935A1 (fr) |
Families Citing this family (7)
Publication number | Priority date | Publication date | Assignee | Title |
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JP7477890B2 (ja) | 2019-09-25 | 2024-05-02 | 国立大学法人大阪大学 | γ線計測方法およびγ線計測装置 |
US11181873B2 (en) * | 2019-12-05 | 2021-11-23 | Global Energy Interconnection Research Institute North America (Geirina) | Bayesian estimation based parameter estimation for composite load model |
CN110911007B (zh) * | 2019-12-29 | 2023-07-25 | 杭州科洛码光电科技有限公司 | 基于成像光谱仪的生物组织光学参数重构方法 |
US11815454B2 (en) | 2020-03-27 | 2023-11-14 | Samsung Electronics Co., Ltd. | Method and system for optimizing Monte Carlo simulations for diffuse reflectance spectroscopy |
EP4086665A1 (fr) | 2021-05-05 | 2022-11-09 | Soletanche Freyssinet | Fonction de réponse d'un scintillateur |
CN113408688B (zh) * | 2021-06-29 | 2022-06-07 | 哈尔滨工业大学 | 一种面向未知环境的多放射源在线探寻方法 |
FR3126155B1 (fr) * | 2021-08-11 | 2023-12-15 | Commissariat Energie Atomique | Procédé de traitement bayésien d’un spectre |
Family Cites Families (3)
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FR2931250B1 (fr) * | 2008-05-13 | 2012-08-03 | Commissariat Energie Atomique | Dispositif et procede de detection et d'identification en temps reel d'une source radioactive en mouvement |
FR2958411B1 (fr) * | 2010-04-02 | 2012-06-08 | Commissariat Energie Atomique | Procede d'analyse spectrometrique et dispositif apparente |
FR2961004B1 (fr) * | 2010-06-07 | 2012-07-20 | Commissariat Energie Atomique | Procede de determination d'intensite d'emission de rayonnement gamma d'un radioelement |
-
2015
- 2015-03-24 FR FR1552415A patent/FR3034221B1/fr active Active
-
2016
- 2016-03-22 WO PCT/EP2016/056208 patent/WO2016150935A1/fr active Application Filing
- 2016-03-22 EP EP16711607.8A patent/EP3274863A1/fr not_active Withdrawn
- 2016-03-22 US US15/560,480 patent/US20180059259A1/en not_active Abandoned
Also Published As
Publication number | Publication date |
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FR3034221A1 (fr) | 2016-09-30 |
WO2016150935A1 (fr) | 2016-09-29 |
FR3034221B1 (fr) | 2018-04-13 |
US20180059259A1 (en) | 2018-03-01 |
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