EP4275036A1 - Dispositif et procédé de mesure d'un absorbant neutronique dans un fluide - Google Patents
Dispositif et procédé de mesure d'un absorbant neutronique dans un fluideInfo
- Publication number
- EP4275036A1 EP4275036A1 EP22700080.9A EP22700080A EP4275036A1 EP 4275036 A1 EP4275036 A1 EP 4275036A1 EP 22700080 A EP22700080 A EP 22700080A EP 4275036 A1 EP4275036 A1 EP 4275036A1
- Authority
- EP
- European Patent Office
- Prior art keywords
- detector
- fluid
- detectors
- neutrons
- isotope
- 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.)
- Withdrawn
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Classifications
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material
- G01N23/025—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material using neutrons
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material
- G01N23/06—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption
- G01N23/09—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption the radiation being neutrons
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N23/00—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00
- G01N23/02—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material
- G01N23/06—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption
- G01N23/12—Investigating or analysing materials by the use of wave or particle radiation, e.g. X-rays or neutrons, not covered by groups G01N3/00 – G01N17/00, G01N21/00 or G01N22/00 by transmitting the radiation through the material and measuring the absorption the material being a flowing fluid or a flowing granular solid
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T3/00—Measuring neutron radiation
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
- G01T7/00—Details of radiation-measuring instruments
- G01T7/005—Details of radiation-measuring instruments calibration techniques
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01V—GEOPHYSICS; GRAVITATIONAL MEASUREMENTS; DETECTING MASSES OR OBJECTS; TAGS
- G01V5/00—Prospecting or detecting by the use of ionising radiation, e.g. of natural or induced radioactivity
- G01V5/04—Prospecting or detecting by the use of ionising radiation, e.g. of natural or induced radioactivity specially adapted for well-logging
- G01V5/08—Prospecting or detecting by the use of ionising radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays
- G01V5/10—Prospecting or detecting by the use of ionising radiation, e.g. of natural or induced radioactivity specially adapted for well-logging using primary nuclear radiation sources or X-rays using neutron sources
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01N—INVESTIGATING OR ANALYSING MATERIALS BY DETERMINING THEIR CHEMICAL OR PHYSICAL PROPERTIES
- G01N2223/00—Investigating materials by wave or particle radiation
- G01N2223/60—Specific applications or type of materials
- G01N2223/637—Specific applications or type of materials liquid
Definitions
- the technical field of the invention is the measurement of a neutron absorber in a fluid, a targeted application being the determination of the concentration of boron (or other absorbing isotope) in the water of the primary circuit of a nuclear reactor. .
- the reactivity in a nuclear reactor In a nuclear reactor, cooled by water, the reactivity must be controlled in order to prevent the occurrence of a criticality situation.
- the reactivity in the primary circuit is adjusted by adding an isotope with significant neutron absorption.
- Such an absorbing isotope can be 10 B, added to the water in the form of boric acid.
- the adjustment of the boron concentration in the water of the primary circuit is carried out by a chemical and volumetric control circuit, usually designated by the acronym RCV.
- the boron concentration can be increased or decreased by adding borated water (water containing boric acid) or demineralised water.
- the RCV circuit is an auxiliary circuit of the primary circuit.
- the boron concentration in the primary circuit is an important parameter for controlling nuclear reactors.
- devices for measuring the boron concentration called “boremeters”, are used. These devices are based on the absorption of neutrons by boron.
- a neutron source irradiates a pipe, usually at the RCV circuit.
- a neutron detector is placed close to the pipe. The detector is positioned so as to be exposed to neutrons emitted by the source, and having passed through the pipe before interacting in the detector. The higher the concentration of boron in the primary circuit, the greater the absorption of neutrons in the primary circuit, and the lower the quantity of neutrons detected by the detector.
- a layer of a moderating material extends between the detector and the pipe. This is called a moderating layer.
- This thermalizes the neutrons before they are detected by the detector.
- thermalizing we mean slowing down the neutrons, so that their energy reaches an energy range corresponding to thermal neutrons: typically less than 1 eV, for example a few tens or hundreds of meV (millielectronvolts), for example 25.3 meV at room temperature. It is in fact in such an energy range that the usual neutron detectors, for example proportional counters, are the most effective.
- the neutron measurement resulting from the neutron detector
- a temperature measurement so as to perform a readjustment of the calibration function.
- Such a solution is for example described in US3898467.
- such a compensation of the effect of the temperature entails uncertainties, in particular on the representativeness of the measured temperature. And this all the more so since the temperature is not homogeneous: it is generally high in the vicinity of the pipe, then decreases as one moves away from it, according to a temperature gradient.
- the inventors propose a device and a method allowing an estimation of a boron concentration in a fluid, without requiring a measurement independent of the temperature as well as a compensation of the calibration function.
- the invention makes it possible to take into account the temperature of the fluid, but also a possible variation in temperature in the moderating layer, between the fluid and at least one neutron detector.
- the temperature variation in the moderating layer appears in particular when the latter is solid.
- a first object of the invention is a method for determining a concentration of an isotope in a fluid, the isotope being capable of absorbing neutrons, the method comprising: a) arrangement of several neutron detectors respectively at different distances of the fluid, the detectors forming a group of detectors; b) irradiation of the fluid by a source emitting neutrons, the source emitting neutrons being arranged so that neutrons emitted by the source pass through the fluid before reaching the detectors; c) measurement, by each detector of the group of detectors, of a quantity representative of a quantity of neutrons reaching the detector; d) from the measurements resulting from c), estimation of a concentration of the isotope in the fluid; the method being characterized in that step d) comprises
- the calibration database comprising an estimate of the quantity measured by each detector
- the fluid may be water.
- step c) comprises a constitution of a measurement set, comprising the quantities measured by each detector, the size of the measurement set corresponding to the number of detectors in the group of detectors;
- step di) comprises, for the or each isotope concentration, and for each temperature distribution, a formation of a calibration set, comprising estimates of quantities measured by each detector, the size of each calibration set corresponding to the number of detectors of the group of detectors, each calibration set being associated with a concentration of the isotope and with a spatial distribution of temperature across the group of detectors;
- step dii) comprises an implementation of an optimization algorithm, so as to select, among the different calibration sets, the calibration set closest to the measurement set, the concentration of estimated isotope corresponding to the isotope concentration associated with the selected calibration set.
- step di) the calibration sets can be formed for different temperatures of the fluid, such that each estimation set is associated with a temperature of the fluid.
- the group of detectors is placed in an external medium, such as air, at an external temperature; - in step di) the calibration sets are formed for different outside temperatures, such that each calibration set is associated with an outside temperature.
- the fluid can extend into a pipe, the detectors being arranged around the pipe. According to one possibility:
- step di) the calibration assemblies are formed for different fluid flow rates in the pipe, such that each calibration assembly is associated with a fluid flow rate.
- the quantity measured by each detector can be any quantity measured by each detector.
- a layer of a moderator material can be interposed between each detector and the fluid, the thickness of the layer being different for each detector.
- the layer of moderator material can be divided into elementary layers, each detector extending in an elementary layer, the spatial temperature distribution corresponding to a temperature of each elementary layer.
- the isotope can be 10 B or 6 Li.
- a second object of the invention is a device for estimating a concentration of an isotope in a fluid, the fluid extending in an enclosure, the isotope being capable of absorbing neutrons, the device comprising:
- the neutron source being arranged so that some of the neutrons emitted by the source pass through the fluid before reaching the detectors;
- a processing unit connected to the detectors, and configured to implement step d) of the method according to the first object of the invention from measurements, carried out by each detector of the group of detectors, of a representative quantity of a quantity of neutrons reaching the detector.
- a layer of a moderating material extends around each detector, such that the thickness of the layer, between the detector and the enclosure, is different for each detector.
- the layer can be formed from different moderating materials.
- FIG. 1A to 1D show an example of a device allowing an implementation of the invention.
- Figure 2 shows a spectrum of neutrons thermalized by a moderator material brought to different temperatures.
- FIG. 3 schematizes the main steps of a method according to the invention.
- FIG. 4 shows another example of a device enabling the invention to be implemented.
- Figures IA to 1D represent an example of a device 1 according to the invention.
- the device 1 is arranged to be placed next to an enclosure 2 in which extends a heat transfer fluid 3.
- the device 1 is intended to estimate a concentration of an isotope 4 in the heat transfer fluid 3.
- the isotope 4 is a neutron-absorbing isotope.
- the isotope is 10 B knowing that it can be another isotope, for example s Li.
- the heat transfer fluid 3 is borated water (mixture of water and boric acid) and enclosure 2 is a borated water pipe.
- the pipe extends along a longitudinal axis Z.
- the fluid is contained in a tank.
- the longitudinal axis Z is perpendicular to a radial plane, the latter being defined by a first radial axis X and a second radial axis Y.
- the device comprises a neutron source 10.
- This may be an isotopic source, comprising one or more isotopes, allowing the emission of neutrons.
- the isotopic source is an Am/Be type source, whose neutron emission is based on an (a, n) type reaction.
- Other types of sources, based on the same principle, are possible, for example 241 Am/Li or 244 Cm/Be.
- the neutron source 10 can be a source of the spontaneous fission type, the most common isotopes being 252 Cf or 242 Cm.
- the device 1 comprises three neutron detectors 20i, 20 2 , 2O 3 , forming a group of detectors 20.
- the number of neutron detectors forming the group of detectors 20 is not limited to three. More generally, as described below, the device comprises a group of detectors 20 containing/detectors of neutrons 20i....20,...20i.
- the number / of neutron detectors is preferably between 2 and 20.
- the index i is an integer designating one row of each detector. In the example described, the higher the rank i, the further the detector is from the neutron source 10 and from the enclosure 2. In this example, the detectors are aligned along the second radial axis Y.
- FIG. 1B shows a cross-sectional view of the device, in a YZ plane passing through the center of the pipe 2.
- the neutron detectors 20 are arranged at different distances from the neutron source 10 and/or at different distances from the chamber 2 containing the fluid.
- Each neutron detector 20 extends at a distance d, from the enclosure 2, and at a distance n from the neutron source 10.
- the distances d, or n can for example be between 1 cm and 50 cm.
- the distances di, aj and d3 respectively separating the first, second and third detectors from enclosure 2 are shown in FIG. 1B.
- Each detector 20 i is configured to detect a quantity of neutrons TC, emitted by the neutron source 10, part of which has propagated through the borated water 3 before reaching the detector 20 i .
- the quantity of TC neutrons, detected by each detector 20, depends on the concentration C of the absorbing isotope in the fluid 3. It is understood that the more the concentration C increases, the more the quantity of TC neutrons, detected by each detector 20, decreases .
- the quantity of neutrons TC, detected by each detector 20, is usually expressed in the form of a counting rate, that is to say a number of neutrons detected per unit of time.
- the counting rate depends directly on a quantity of incident neutrons fi at the detector, as well as on the energy of the incident neutrons at the detector.
- the quantity of incident neutrons fi at the detector is expressed: in the form of a number of neutrons per unit of time (neutrons per second for example); or in the form of a fluence rate: number of neutrons per unit of time and area (neutrons per second and per cm 2 for example).
- CT i ⁇ i ( ⁇ ⁇ ) (1)
- each detector 20 is a boron deposit proportional counter. This type of counter is common. Under the effect of irradiation with a neutron flux, charged particles (a) are formed in the gas by capture (h,a). The a particles are detected by polarized electrodes. This results in a counting rate TC i . Boron deposition proportional counters have better detection efficiency when the neutron energy is low, typically in the thermal range, as mentioned in the prior art. In order to reduce the energy of the neutrons, a moderating layer 21 is interposed between each detector 20, and the enclosure 2.
- the moderating layer is formed of a material that scatters the neutrons: it is a question of thermalizing the neutrons, it that is, to slow them down, so that their energy decreases.
- the use of such a moderating layer is usual in the field of neutron detection.
- the moderating layer may comprise a material exhibiting high neutron scattering, for example polyethylene. It can also be graphite or a composite material, formed by a superposition of moderating materials.
- Each counter is connected to a processing unit 30, by a wired or wireless link.
- the processing unit 30 may include a microprocessor.
- the processing unit 30 is programmed to implement an estimation of a concentration of 10 B in the fluid 3 from counting rates TC, respectively measured by each detector 20 ,.
- the processing unit comprises a memory 32, in which are stored instructions making it possible to estimate the quantity of 10 B in the fluid.
- FIGS. 1C and 1D represent respectively a section of device 1 in an XZ plane passing through neutron source 10, and a section of device 1 in a radial plane XY passing through the source and each detector.
- the distances r 1 , r 2 and r 3 respectively separating the first, second and third detectors from the source 10 are shown in FIG. 1D.
- Figure 2 shows spectra of neutrons, thermalized by a moderator material (eg water or polyethylene or graphite), for different temperatures.
- a moderator material eg water or polyethylene or graphite
- the abscissa axis is the energy (meV - millielectronvolts) and the ordinate axis is a neutron flux normalized by a neutron density (unit ms -1 .ev -1 ).
- Figure 2 is obtained by applying the following analytical expression:
- ⁇ (E) is a flux of neutrons at an energy E (.cm -2 .J - 1 .s -1 ); n 0 is a density of neutrons in cm -3 ; k is the Boltzmann constant (J. K -1 ); m is the mass of a neutron (kg);
- the capture cross section of a moderator material varies according to the energy: when the energy increases, the capture cross section decreases.
- Table 1 shows, for different temperatures, and energies close to 25 meV, the respective neutron capture cross sections of:
- the energies at which the cross sections (unit millibarns) are calculated correspond to the maximum value of the spectra represented in FIG. 2, for the temperatures of 20°C, 38°C and 56°C.
- Table 1 shows a lowering of the capture cross section for each energy corresponding to the maximum value.
- the invention makes it possible to address the question of the sensitivity of the measurements to temperature, without requiring the use of one or more temperature sensors.
- the invention also takes into account the fact that the temperature can vary between the borated water 3 and the various detectors 20 i . As previously indicated, the temperature is maximum at the level of pipe 2, and decreases as one moves away from the latter.
- a source of uncertainty is the fact that the temperature within the moderating layer is generally not homogeneous: a decreasing temperature gradient, more or less marked, may exist between the pipe 2 and the various detectors 20 i . A measurement of this gradient by temperature sensors distributed in the moderating cover is difficult to envisage.
- FIG. 3 represents the main steps of a method for determining a concentration of 10 B by implementing a device as previously described.
- the method assumes a preliminary calibration phase, which corresponds to step 90.
- the objective of the calibration is to estimate, for each detector 20 i of the group of detectors 20, a quantity representative of a quantity of neutrons reaching the detector, and this under different conditions.
- the estimated quantity is a counting rate TC i measured by each detector (number of neutrons detected per second).
- the estimated magnitude is a number of neutrons N i incident to the detector per unit time or a number of neutrons ⁇ i incident to the detector per unit time and area (fluence rate).
- the relationship between the counting rate TC i and the number of neutrons incident on the detectors per unit time depends on the efficiency e, of the detector 20 i .
- the estimation of the counting rate TC i for each detector 20 i is carried out using a computer code modeling the transport of neutrons. It may for example be the calculation code MCNP6, based on a Monte Carlo type method. During the calibration phase, simulations are carried out taking into account: a predetermined concentration of 10 B, and different spatial distributions of effective absorption and scattering sections between the pipe 2 and the detectors 20 i .
- Each spatial distribution of absorption cross sections corresponds to a spatial distribution of temperature.
- the fact of considering different spatial distributions of effective absorption sections makes it possible to simulate the response of the device for different temperature distributions between the pipe 2 and the detectors 20 i .
- the moderating layer 21 is virtually divided into several elementary layers 21 j .
- the index j is an integer representing the rank of each layer.
- the calibration phase consists in estimating the counting rates TC i measured by each detector for different sets of input parameters.
- Each set of input parameters includes: a concentration of boron in the fluid; an absorption cross section in the fluid, which corresponds to a temperature of the fluid T; a spatial distribution of effective absorption sections for the various elementary layers 21 j as well as in the various detectors 20 i , which is representative of a spatial distribution of the temperature between the pipe and the various detectors.
- Each modeling leads to a set of modeled quantities, which are, in this example, the estimates of the counting rates TC i resulting from each detector 20 i .
- each modeling generates a set of I counting rates of each detector 20;.
- Each modeled set is associated with the modeling parameters, which are: the concentration C k of boron in the fluid, the index k designating each modeled concentration.
- the temperature T l of the water the subscript l designating each modeled concentration.
- At each temperature corresponds one or more cross sections ⁇ l,p of elements absorbents present in the water, in this case 1 H and 10 B.
- the index p designates each absorbent element considered in the water.
- the subscript m denotes each modeled spatial temperature distribution.
- ⁇ jq corresponds to an effective section of each absorbent material in the layer 21 j . It can for example be 1 H (present in the polyethylene) and 10 B (present in the detectors).
- the index q denotes each absorbent material considered in an elementary layer.
- the calibration step 90 can be summarized as follows:
- Sub-step 91 determination of input data: concentration of boron C k , temperature of the fluid T l , spatial distribution of the temperature ⁇ m .
- Sub-step 92 determination: o of the cross sections ⁇ lp of each absorbent material p in water at the temperature of the water in question. o a spatial distribution of cross sections ⁇ mq of each scattering material of each elementary layer 21 j , for each temperature considered of each elementary layer.
- Sub-step 93 Estimation of count rates at the level of each detector, corresponding to the modeling data taken into account.
- sub-step 93 aims to estimate a quantity representative of a quantity of neutrons reaching each detector 20 i .
- it may be the counting rate TC t , or a number of incident neutrons per unit of time or a number of incident neutrons per unit of time and area.
- the sub-steps 91 to 93 are implemented at least for different spatial distributions ⁇ m and possibly for different water temperatures T l -
- the sub-steps 91 to 93 can be implemented works for different concentrations C k of boron. If K, L and M correspond respectively to the numbers of concentrations C k , temperatures Ti and temperature distributions ⁇ m considered, the calibration phase provides K x L x M sets of counting rates also referred to as sets of calibration. Calibration sets are stored in the memory 32 connected to processing unit 30.
- the calibration sets result from neutron transport modeling for discrete values of C k , T l and ⁇ m . It is possible to complete the calibration with counting rates resulting from interpolations, for example between two different water temperatures T l and T l+1 . To perform the interpolations, it will be possible to use a nuclear data processing code, for example the NJOY code developed by Los Alamos National Laboratory.
- the database resulting from the calibration comprises modeled calibration sets and possibly calibration sets interpolated from modeled calibration sets.
- the database can be established experimentally, for example on a model, taking into account different water temperatures, different boron concentrations, different spatial distributions of temperature between different detectors as well as different temperatures. exterior.
- outside temperature is meant a temperature of the air, outside the measurement system formed by the various detectors and the moderating layer. Indeed, the temperature of the moderating layer, and the temperature gradient through the moderating layer, depend on the temperature of the water as well as the temperature of the air in which the measuring system extends.
- the outside temperature air temperature
- air temperature can then constitute an additional parameter to be taken into account in the database.
- the outside temperature can be adjusted by regulating the temperature of the air around the model.
- the water temperature can be regulated by a thermostat and a water heating system.
- Step 100 irradiation
- Step 110 measurement, by each detector, of a quantity representative of a quantity of neutrons reaching the detector. In this example, it is the counting rate TC i .
- Step 120 formation of a set of counting rates respectively measured by each detector 20; of the detector group 20. A measured set is thus formed
- Step 130 taking into account the database resulting from the calibration to determine the calibration set closest to the measured set
- the average deviation can for example be a sum of the absolute values of the differences between counting rates respectively measured and calibrated for the same detector:
- the closest calibration set to the measured set is the minimizing one.
- Step 140 estimation of the boron concentration: the estimated boron concentration ⁇ corresponds to the concentration C k of the calibration set considered, during phase 130, as the closest to the measured set ⁇ TC 1 ... TC i ... TC I ⁇ .
- the method also allows an estimation of the temperature of the water, as well as an estimation of the spatial distribution of temperature 6 between the different detectors, with
- Step 130 can be implemented using an optimization algorithm, for example an ML-EM (Maximum-Likelihood Expectation Maximization) method.
- ML-EM Maximum-Likelihood Expectation Maximization
- An important aspect of the invention is that the temperature, whether it is the temperature of the water or of the different elementary layers 21 j , does not constitute input data, allowing an estimation of the concentration sought. This is output data.
- each calibration assembly is associated with a flow rate Q of the water and/or with the outside temperature mentioned above.
- the calibration phase is preferably experimental, being carried out on a model.
- the database comprises, in addition to the parameters C k , T l , ⁇ m , a parameter T′ n (air temperature) and/or a parameter Q o (water flow rate).
- the database can be established by modeling, by coupling a particle transport code like MCNP with a thermohydraulics code.
- the parameter ⁇ m comprises 4 different spatial temperature distributions, each spatial distribution comprising a temperature assigned to each elementary layer 21 i , 21 2 and 21 3 respectively.
- Table 2 shows a ratio between calibration counting rates resulting from modeling, taking into account different configurations. Each value corresponds to a ratio of counting rates, measured by the same detector, respectively in a configuration, and in a reference configuration. The inventors have modelled, for each configuration, the reaction numbers (n, ⁇ ) per neutron emitted by the source. The count rate, in each configuration, is proportional to this number.
- Configuration 1 Temperature gradient taken into account: 350 K, 350 K, 350 K;
- Configuration 2 Temperature gradient taken into account: 350 K, 350 K, 293 K;
- Configuration 3 Temperature gradient taken into account: 350 K, 293 K, 293 K;
- Configuration 4 Temperature gradient taken into account: 293 K, 293 K, 293 K. The configuration
- Each row of the table corresponds to a concentration value C k .
- Each column of the table is assigned to a detector among the three modeled detectors.
- Table 2 shows that the counting rate, compared to the reference configuration, varies differently, between the different detectors, depending on the configuration chosen.
- the evolution, as a function of the detectors, of the counting rate constitutes a signature of the temperature distribution ⁇ m and of the concentration C k .
- FIG. 4 shows another example of the device, comprising 13 detectors 20 i distributed around a pipe 2.
- the detectors are distributed in a spiral.
- each calibration set and each measurement set constitutes a 13-tuple comprising 13 counting rates.
- each calibration set and each measurement set includes values corresponding to a quantity of neutrons not detected, but incident to each detector. It may for example be a number of neutrons per unit of time (number of neutrons per second) or a number of neutrons per unit of time and area (number of neutrons per second and per cm 2 ).
- the invention allows an estimation of a concentration of a neutron-absorbing isotope without requiring a measurement of the temperature, whether it is the temperature of the water or the temperature at the level of each neutron detector. Taking the temperature into account is implicit, insofar as it results from a confrontation between the calibration sets, forming the calibration database, and the measurement set. Thereby, the invention avoids having to resort to compensation functions, taking the temperature into account.
- the determination of the concentration is more precise, because it is determined by taking into account, in the modeled data, the temperature of the fluid, but also the spatial distribution of temperature between the various detectors.
- the invention can be used to quantify the concentration of other neutron absorbers, for example 6 Li.
- the invention can be applied to other types of neutron detectors, in particular detectors sensitive to neutrons having been slowed down by a moderating layer: thermal, epithermal or intermediate neutrons.
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Abstract
Description
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Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR2100066A FR3118666B1 (fr) | 2021-01-05 | 2021-01-05 | Dispositif et procédé de mesure d’un absorbant neutronique dans un fluide |
| PCT/EP2022/050037 WO2022148731A1 (fr) | 2021-01-05 | 2022-01-03 | Dispositif et procédé de mesure d'un absorbant neutronique dans un fluide |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| EP4275036A1 true EP4275036A1 (fr) | 2023-11-15 |
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Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP22700080.9A Withdrawn EP4275036A1 (fr) | 2021-01-05 | 2022-01-03 | Dispositif et procédé de mesure d'un absorbant neutronique dans un fluide |
Country Status (4)
| Country | Link |
|---|---|
| US (1) | US20240060910A1 (fr) |
| EP (1) | EP4275036A1 (fr) |
| FR (1) | FR3118666B1 (fr) |
| WO (1) | WO2022148731A1 (fr) |
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| US12372482B2 (en) * | 2023-05-26 | 2025-07-29 | Schlumberger Technology Corporation | Lithium detection apparatus systems and methods |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3898467A (en) * | 1974-03-18 | 1975-08-05 | Combustion Eng | Method and apparatus for continuous monitoring and control of neutron absorption properties of chemical shim with temperature compensation |
| CA1220571A (fr) * | 1984-08-03 | 1987-04-14 | John S. Redfern | Dispositif de surveillance du poison dans le moderateur d'un reacteur |
| DE19643375A1 (de) * | 1996-10-21 | 1998-04-30 | Siemens Ag | Meßvorrichtung zur Ermittlung einer Borkonzentration |
| US9761335B2 (en) * | 2013-10-21 | 2017-09-12 | Westinghouse Electric Company Llc | Method for monitoring boron dilution during a reactor outage |
| CN106205753A (zh) * | 2016-08-02 | 2016-12-07 | 中国核动力研究设计院 | 核电站水平管线式硼浓度探测设备 |
| DE102017222344A1 (de) * | 2017-12-11 | 2019-06-13 | Framatome Gmbh | Vorrichtung und Verfahren zur Bestimmung des Borgehalts in einem Medium |
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2021
- 2021-01-05 FR FR2100066A patent/FR3118666B1/fr active Active
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2022
- 2022-01-03 US US18/260,439 patent/US20240060910A1/en active Pending
- 2022-01-03 EP EP22700080.9A patent/EP4275036A1/fr not_active Withdrawn
- 2022-01-03 WO PCT/EP2022/050037 patent/WO2022148731A1/fr not_active Ceased
Also Published As
| Publication number | Publication date |
|---|---|
| US20240060910A1 (en) | 2024-02-22 |
| FR3118666A1 (fr) | 2022-07-08 |
| WO2022148731A1 (fr) | 2022-07-14 |
| FR3118666B1 (fr) | 2022-12-23 |
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