WO2022017663A1 - Procédé de mesure de sûreté nucléaire d'un matériau à mesurer au moyen d'un système de mesure de dégagement, produit-programme informatique et système de mesure de dégagement - Google Patents

Procédé de mesure de sûreté nucléaire d'un matériau à mesurer au moyen d'un système de mesure de dégagement, produit-programme informatique et système de mesure de dégagement Download PDF

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Publication number
WO2022017663A1
WO2022017663A1 PCT/EP2021/063366 EP2021063366W WO2022017663A1 WO 2022017663 A1 WO2022017663 A1 WO 2022017663A1 EP 2021063366 W EP2021063366 W EP 2021063366W WO 2022017663 A1 WO2022017663 A1 WO 2022017663A1
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WO
WIPO (PCT)
Prior art keywords
measurement
measured
measuring
detectors
chamber
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.)
Ceased
Application number
PCT/EP2021/063366
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German (de)
English (en)
Inventor
Tim Thomas
Michele Pastena
Bastian Weinhorst
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Safetec GmbH
Original Assignee
Safetec Entsorgungs und Sicherheitstechnik GmbH
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Safetec Entsorgungs und Sicherheitstechnik GmbH filed Critical Safetec Entsorgungs und Sicherheitstechnik GmbH
Priority to EP21728838.0A priority Critical patent/EP4182729A1/fr
Publication of WO2022017663A1 publication Critical patent/WO2022017663A1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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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
    • G01T1/167—Measuring radioactive content of objects, e.g. contamination

Definitions

  • the invention relates to a method for the decision-making measurement of a measurement item using a clearance measurement system and a computer program product and a clearance measurement system with a measurement chamber and a plurality of detectors surrounding the measurement chamber for detecting radioactive radiation.
  • the term "decision measurement” means the measurement of the radioactive activity of material subject to nuclear surveillance.
  • nuclear law monitoring is regulated by the Atomic Energy Act and the Radiation Protection Ordinance.
  • the material that is subject to nuclear monitoring arises in particular when a nuclear facility, in particular a nuclear power plant, is dismantled or demolished. In this respect, the material can be rubble, metal parts, etc., for example.
  • Material that is subject to nuclear law monitoring, the activity of which is demonstrably below the level required by the legislation, as determined by the decision measurement can be released on the basis of an official decision.
  • the metrological proof that the measured material is below the required level, which is the result of the decision measurement is also referred to as "clearance measurement".
  • clearance measurement and decision measurement are also used synonymously.
  • the actual decision to release the material from nuclear monitoring is referred to as "release” and in Germany is a legal administrative act by the relevant authority.
  • the clearance measurement is a preliminary stage of the release.
  • the measurements on the material itself are referred to as decision measurements, since they are used to decide whether to release it.
  • the material or the cleared material is no longer a radioactive substance within the meaning of nuclear law, so it no longer needs to be monitored under nuclear law and can be reused accordingly or disposed of more cheaply than nuclear waste, for example. This avoids an extremely costly disposal of nuclear waste in a special repository.
  • the vast majority of the total mass of the nuclear facility can be released, since most of the material has never come into contact with radioactivity.
  • the decision measurement is carried out in a measurement chamber surrounded by a number of detectors.
  • the detectors can record the activity of the material introduced into the measuring chamber.
  • the measuring chamber with the detectors surrounding it is therefore referred to as a clearance measuring system.
  • the material subject to nuclear regulatory surveillance is often sorted according to material type, for example concrete or metal, and typically filled into a measuring container, for example a lattice box or a big bag.
  • the filled measuring container can then be placed in the measuring chamber of the clearance measuring system be introduced and the activity of the material in the measuring container can be determined by means of the detectors by means of the decision measurement.
  • the material that is subject to nuclear monitoring is referred to in decision measurements and in the following as measured material, since it is the subject of decision measurements.
  • an efficiency of the detectors In order to determine the activity, in addition to the measurement data obtained, an efficiency of the detectors must also be determined, which can be used to calculate the actual activity and which, in particular, must be multiplied by the count rate measured by the detectors.
  • the efficiency of a detector indicates the ratio between the particles emitted from the material being measured into a detector surface or a detector volume of the detector and the particles counted by the detector.
  • the degrees of effectiveness can be determined by appropriate calibration of the detectors, for example with the aid of calibration containers.
  • calibration containers are used with a homogeneous activity distribution within the material to be measured. Strictly speaking, however, the efficiencies determined in this way may only be used if the activity in the measuring material in the measuring container is also homogeneously distributed. If the activity distribution in the measured material in the measuring container deviates from the activity distribution in the calibration container, the activity is underestimated or overestimated. In order to avoid an underestimation (also referred to as non-conservative), a statement as accurate as possible about the activity distribution in the measured material in the measuring container must be made.
  • the object of the invention is therefore to provide an improved method for the decision-making measurement of a measurement item using a clearance measurement system and a computer program product and a clearance measurement system, by means of which the activity distributions within the measurement material can be determined very precisely in a simple manner and the probability of a to be measured in the clearance measurement system is as high as possible.
  • the object is therefore achieved by a method for decision-making measurement of a measurement item using a clearance measurement system with a measurement chamber and a plurality of detectors surrounding the measurement chamber for detecting radioactive radiation, the method having the following steps:
  • the method according to the invention provides that the material to be measured is arranged at at least two or more different measurement positions within the measurement chamber and is measured by means of the detectors.
  • a counting rate is recorded in each case.
  • additional location-dependent information is generated compared to a measurement at only one measuring position. This additional location-dependent information allows a particularly exact localization of the activity in the measured material or, in other words, a particularly exact determination of the activity distribution.
  • Measurement positions mean spatial positions of the volume of the material to be measured within the volume of the measurement chamber in which the material to be measured is located. In this respect, the measurement position also includes an orientation of the material to be measured relative within the measurement chamber.
  • the at least one further measurement position can differ from the at least one first measurement position not only in that the material to be measured is closer to an inside of the measurement chamber than it is still in the first measurement position, but instead, for example, in that the material to be measured has been rotated, for example .
  • the material to be measured can be shifted from the first measuring position into the at least one further measuring position in any of the three spatial directions and/or rotated in any way.
  • the measurement position can be from the first measurement position to the at least one additional measurement position, and also from one of the additional measurement positions to another of the additional measurement positions, by moving the material to be measured accordingly within the measurement chamber.
  • the steps of the method are carried out in the order listed. Accordingly, the material to be measured is first measured in the first measurement position and then in the at least one further measurement position by means of the detectors, or its radioactive radiation is recorded.
  • the method also has the step: simulating a count rate of each detector in the at least one further measurement position of the material to be measured.
  • the simulation can take place before the item to be measured is arranged in the at least one further measuring position and/or before the item to be measured is arranged in the first measuring position.
  • the step of simulating the count rate of each detector can of course also be carried out in the first measurement position.
  • the additional measurement positions can first be determined by simulation. This can ensure that further measurement positions that are as suitable as possible are determined, in which there is a high probability that the material to be measured can be cleared.
  • the simulation of the counting rate takes place under the assumption that a point source is arranged within the measurement material at the at least one further measurement position of the measurement material within the measurement chamber. Accordingly can the count rate can also be simulated for assuming the arrangement of the point source within the measurement material at the first measurement position.
  • the point source has a known activity, so that the efficiency of the detectors for the point source at the at least one additional measurement position or in the additional measurement positions can be determined using the simulated count rate.
  • the spotlight can be formed by the isotope Co-60.
  • the energy of the particles emitted by Co-60 is relatively high compared to the particle energies of other radionuclides that usually occur during the dismantling of nuclear facilities. The higher the particle energies, the more likely it is that the particles can penetrate the material and hit the detectors. They are more likely to deposit greater energy there. If the measured material actually emits particles with lower energy (e.g. Cs-137), the assumption of the point emitter formed from the isotope Co-60 leads to conservatism for the purposes of the simulation. This means that an activity that can be determined within the scope of the method overestimates the actual activity in the measured material.
  • the spotlight is assumed to be arranged in a center of the material to be measured.
  • the center refers in particular to a volume center of the material to be measured or its volume.
  • the activity for the measured material is also overestimated by such an arrangement or assumption of the point source or assumed to be maximally conservative.
  • the at least one further measurement position comprises at least two further measurement positions that differ from the first measurement position and from one another.
  • the at least one further measurement position can in particular be a plurality of further measurement positions.
  • the further measurement positions each differ from the first measurement position and the other measurement positions. If several other measurement positions are used, the material to be measured is arranged and measured in one of these several other measurement positions and then arranged and measured in another of these several other measurement positions, with this being repeated for each of the other measurement positions.
  • the number of further measuring positions can be in particular in the range from 2 to 20, and in particular in the range from 3 to 12 specifically in the 4 to 10 range.
  • the number of further measurement positions can therefore be 6, for example. It has been shown that this number of additional measurement positions significantly increases the probability of a clearance measurement.
  • the efficiency of each detector in relation to the respective one of the at least two further positions is determined from the simulation for each of the at least two further measurement positions.
  • the efficiency can also be determined for the first measurement position before the corresponding measurement of the material to be measured is carried out in the first measurement position.
  • the corresponding information can be saved. This can be done, for example, in the form of a table.
  • the radioactive radiation or count rates recorded by the detectors in each case at the further measurement positions with the greatest possible efficiency are used.
  • the activity distribution in the material to be measured is then determined using the radioactive radiation or measured values or count rates recorded by the detectors in each case at the further measurement positions with the greatest possible efficiency.
  • those radioactive radiations or count rates detected by the detectors that have been carried out with the highest efficiency are used to determine the activity distribution in the measurement material for each measurement carried out on the measurement material in the further measurement positions.
  • those recorded radioactive radiations or count rates are used.
  • the recorded radioactive radiation or count rates can also be used in other Measurement positions are included in the evaluation and thus provide further information. This reduces the detection limit and conservatism.
  • the probability of measuring the material to be measured increases significantly compared to the solution in the prior art, in which an attempt is made to increase the overall efficiency of all detectors.
  • the material to be measured from a large number of simulated further measurement positions is only arranged in those further measurement positions within the measurement chamber and its radioactive radiation is detected by means of the detectors in which at least one of the large number of simulated further measurement positions has at least one greatest possible efficiency detector has been determined.
  • more further measurement positions are simulated than are actually measured, or in other words only those are selected from the simulated further measurement positions for which at least one detector exhibited the highest efficiency.
  • the material to be measured can be arranged in a measuring container within the measuring chamber.
  • a lattice box, a metal box, a big bag (flexible bulk material container), a pallet or the like can be used as the measuring container.
  • the measuring container can be a container that is used, for example, during the dismantling or demolition of a nuclear facility, in particular a nuclear power plant, for storing and transporting the dismantling material that is used as the measured material is measured, is used.
  • the material to be measured can in particular be a dismantling material of a nuclear facility.
  • one of the at least one further measurement position of the material to be measured within the measurement chamber is assumed by moving and/or rotating the material to be measured within the measurement chamber in relation to the first measurement position or a previous further measurement position.
  • the object is achieved by a computer program product that can be executed by a processing unit of a clearance meter, the computer program product being set up to execute the method according to the first aspect of the invention.
  • the processing unit can be designed, for example, as a control unit and/or computing unit of the clearance measurement system. Accordingly, the Processing unit adjust the arrangement of the measurement material within the measurement chamber and also control the detectors and determine the activity distribution.
  • the object is achieved by a clearance measurement system with a measurement chamber and a plurality of detectors surrounding the measurement chamber for detecting radioactive radiation, the clearance measurement system being set up to carry out the method according to the first aspect of the invention.
  • the clearance measurement system has a movement device in the measurement chamber, which is set up to arrange the material to be measured in the first measurement position and in the at least one further measurement position within the measurement chamber. Accordingly, the movement device can provide at least the first measurement position and the at least one further measurement position of the material to be measured in the measurement chamber.
  • the movement device can be a device that is separate from or combined with a feed device for feeding the material to be measured into the measurement chamber.
  • the movement device can be, for example, a roller or conveyor belt or the like, which can be correspondingly adjusted in height and/or tilted.
  • the measurement position of the measurement material in the measurement chamber can be changed, for example, by a corresponding feed of the measurement material by means of the roller or conveyor belt into the measurement chamber.
  • the detectors can in particular be gamma detectors.
  • Gamma detectors are designed to detect gamma radiation or gamma quanta.
  • the detectors can be in the form of scintillation counters, in particular plastic scintillation counters.
  • the scintillation counters can have a detector volume and a detector area.
  • the term detector surface designates the surface of the detector facing the radiation source.
  • the particles, in particular gamma quanta can fall through the detector surface into the detector volume and be detected in the detector volume.
  • the detectors can have, for example, a detector volume of 2200 cm 3 with a detector area of approximately 400 cm 2 .
  • the detectors can be shielded from alpha and beta radiation.
  • the detectors may further include a photomultiplier, a discriminator and a counting unit.
  • the volume effect in the crystal can be used, while the detection mechanism in the case of a counter tube, for example, is only an area effect on its surface.
  • a large number of gamma quanta can thus be detected in the detection volume of the scintillation counter, which means that the counting rate is very high and there is a high probability that an interaction will occur.
  • the detector surfaces of the detectors surround the measuring chamber essentially without interruption. Essentially means that a completely uninterrupted environment does not have to or can be achieved. For example, it may be sufficient if the measuring chamber is surrounded by the detector surfaces of the detectors by at least 95%, for example 98%. A 4TT space coverage is preferably achieved so that all particles emitted by the measurement material can be detected by the detectors. Accordingly, the detector surfaces can be located on the inside of the measuring chamber.
  • FIG. 1 shows a perspective side view of an exemplary embodiment of a clearance measurement system according to the invention
  • FIG. 2 shows a schematic representation of the measuring chamber of the clearance measuring system from FIG. 1 with its detectors
  • FIG. 3 shows a schematic representation of the material to be measured in a first measurement position within the measurement chamber from FIG. 2;
  • FIG. 4 shows a schematic representation of the material to be measured in an example of a further measurement position within the measurement chamber from FIG. 2, which is different from the first measurement position;
  • FIG. 5 shows a schematic representation of the material to be measured in an exemplary further measuring position within the measuring chamber from FIG. 2, which is different from the first measuring position and the further measuring position from FIG. 4;
  • Figure 6 is a schematic representation of a sequence of an inventive
  • FIG. 1 shows an exemplary embodiment of a clearance measurement system 100 according to the invention.
  • the clearance measurement system 100 has a measurement chamber 30 and a feed device 60 .
  • the feed device 60 is designed as a roller conveyor, but can alternatively also be designed in some other way, for example as a conveyor belt, an industrial truck, a crane or the like.
  • a measuring container 40 with the material to be measured 50 located therein is fed to the measuring chamber 30 or arranged in the measuring chamber 30.
  • the measuring container 40 is in the present case designed as a lattice box, but can also be designed in some other way, for example as a big bag, a metal box, a pallet or the like.
  • the measuring chamber 30 is enclosed by a container 70 .
  • the measuring chamber 30 is designed as a type of container that is set up to hold the measuring container 40 .
  • the measuring container 40 can be arranged inside the measuring chamber 30 .
  • the measuring chamber 30 can be opened in order to arrange the measuring container 40 therein.
  • the measuring chamber 30 has corresponding doors which allow the measuring chamber 30 to be opened.
  • the measuring chamber 30 is equipped with a plurality of detectors 1, 2, 3, 4, 5, 6, 7, 8, 9, 10, 11, 12, 13, 14, 15, 16, 17, 18, 19, 20, 21, 22, 23, 24 (hereinafter 1...24).
  • the measuring chamber has 3024 detectors 1...24.
  • the measuring chamber 30 can also have fewer or more detectors 1...24. With a sufficient number of detectors 1 . . .
  • the detector surfaces of the detectors 1...24 are arranged on the sides of the measuring chamber 30 around it.
  • FIG. 3 now shows the measurement material 50 received by the measurement container 40 and therefore not visible in a first measurement position 80 within the measurement chamber 30.
  • the measurement material 50 is located in the center of the measurement chamber 30.
  • Gamma particles emitted within the measurement material 50 can pass through the measurement material 50 step through and then meet one of the detectors 1...24.
  • the detector 1...24 detects the radioactive radiation of the material to be measured 50, as is described below.
  • the gamma particles interact within a detector volume with the electrons of a detector material of the respective detector 1...24. Through this interaction, so-called scintillation photons are generated, which are generated using the photo effect of a photo-electron multiplier of the respective detector 1...24 can be converted into an electrical pulse.
  • the electrical pulse is forwarded to a discriminator of the respective detector 1...24, which forwards the electrical pulse to a counting unit of the detector 1...24 when a certain threshold value is exceeded.
  • the counting unit records the electrical pulse as a counting event and thus forms a counting rate over the period of the measurement.
  • FIG. 4 shows the same measurement item 50 from FIG. 3 in a further measurement position 81 which differs from the first measurement position 80 .
  • the material to be measured 50 which is picked up by the measuring container 40, is located on a lower and left edge of the measuring chamber 30.
  • FIG. 5 shows the same item 50 to be measured from FIGS. 3 and 4 in yet another further measuring position 82 which differs from the first measuring position 80 and the further measuring position 81 .
  • the material to be measured 50 which is received by the measuring container 40, is located on an upper and right edge of the measuring chamber 30.
  • FIG. 6 shows a sequence of an exemplary embodiment of a method according to the invention for the decision measurement of the measurement item 50. This method is explained below with regard to the previously explained FIGS. 1 to 5, in particular FIGS. 3 to 5.
  • a first step 200 the measurement material 50 arranged in the first measurement position 80 within the measurement chamber 30, as shown in FIG 50 determined.
  • the central position of the material to be measured 50 in the measuring chamber 30 maximizes the overall efficiency of the detectors 1...24.
  • the material to be measured 50 can already be cleared in this first step 200 . If this is not possible, but it cannot be ruled out that the item to be measured 50 cannot be measured after all, a transition is made to the second step 210 .
  • the material to be measured 50 is simulated inside the measuring chamber 30 in the further measuring position 81, as shown in FIG.
  • a point emitter arranged within the material to be measured 50 at the further measurement position 81 is assumed, so that the activity distribution within the material to be measured 50 is assumed to be as conservative as possible.
  • the efficiency of each detector 1...24 is determined.
  • the second step 210 of the simulation for the material to be measured 50 within the measurement chamber 30 in the further measurement position 82, as shown in FIG. 5, is repeated.
  • the efficiency of each detector 1...24 is determined.
  • the second step 210 and the third step 220 can then be repeated for further measurement positions 83, 84, etc. (not shown) that differ from the other measurement positions 80, 81, 82. In the following, however, it is assumed by way of example that the simulation was only carried out for the further measurement positions 81 , 82 .
  • the simulations according to the second step 210 and the third step 220 can be carried out in a corresponding simulation module of the clearance measurement system 100, which is not shown here.
  • the efficiency is determined for each of the detectors 1...24 as a function of the simulated further measurement position 81, 82. For each detector 1 .
  • the material to be measured 50 is measured in addition to the first measurement position 80 in those selected ones of the simulated further measurement positions 81, 82 in which, according to the fourth step 230, the greatest or greatest possible efficiency of the detectors 1...24 in all simulated further measurement positions 81, 82 have been determined.
  • an activity distribution of the material to be measured 50 is determined on the basis of the measurements of its radioactive radiation that have taken place.
  • the detected count rates of each detector 1...24 are used, which have been made at the further measuring positions 81, 82 with the highest degree of efficiency.
  • the associated activity for each counting rate measured by the respective detector 1...24 can be determined from the respective maximum efficiency of each detector 1...24.
  • the activity distribution can be determined using the measurements on the different other measurement positions 81, 82 determine location-dependent information obtained very precisely. The highest efficiencies result in a low detection limit. conserveatism is reduced and the probability of measuring the item 50 free increases accordingly.

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  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • General Physics & Mathematics (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Molecular Biology (AREA)
  • Spectroscopy & Molecular Physics (AREA)
  • Measurement Of Radiation (AREA)

Abstract

L'invention concerne un procédé de mesure de sûreté nucléaire d'un matériau à mesurer (50) au moyen d'un système de mesure de dégagement (100) comportant une chambre de mesure (30) et une pluralité de détecteurs (1...24) entourant la chambre de mesure (30) pour détecter un rayonnement nucléaire, le procédé comprenant les étapes suivantes consistant à : (a) utiliser le matériau à mesurer (50) ; (b) disposer le matériau à mesurer (50) dans une première position de mesure (80) à l'intérieur de la chambre de mesure (30) ; (c) détecter un rayonnement nucléaire à partir du matériau à mesurer (50) disposé dans la première position de mesure (80) à l'intérieur de la chambre de mesure (30) au moyen des détecteurs (1...24) ; (d) disposer le matériau à mesurer (50) dans au moins une autre position de mesure (81, 82), différente de la première position de mesure (80), à l'intérieur de la chambre de mesure (30) ; (e) détecter un rayonnement nucléaire à partir du matériau à mesurer (50) disposé dans ladite autre position de mesure (81, 82) au moyen des détecteurs (1...24) ; et (f) déterminer une distribution d'activité dans le matériau à mesurer (50) sur la base du rayonnement nucléaire détecté au moyen des détecteurs (1...24). L'invention concerne également un produit-programme informatique et un système de mesure de dégagement (100).
PCT/EP2021/063366 2020-07-20 2021-05-19 Procédé de mesure de sûreté nucléaire d'un matériau à mesurer au moyen d'un système de mesure de dégagement, produit-programme informatique et système de mesure de dégagement Ceased WO2022017663A1 (fr)

Priority Applications (1)

Application Number Priority Date Filing Date Title
EP21728838.0A EP4182729A1 (fr) 2020-07-20 2021-05-19 Procédé de mesure de sûreté nucléaire d'un matériau à mesurer au moyen d'un système de mesure de dégagement, produit-programme informatique et système de mesure de dégagement

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE102020119065.4 2020-07-20
DE102020119065.4A DE102020119065A1 (de) 2020-07-20 2020-07-20 Verfahren zum Entscheidungsmessen eines Messguts unter Verwendung einer Freimessanlage, Computerprogrammprodukt sowie Freimessanlage

Publications (1)

Publication Number Publication Date
WO2022017663A1 true WO2022017663A1 (fr) 2022-01-27

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EP (1) EP4182729A1 (fr)
DE (1) DE102020119065A1 (fr)
WO (1) WO2022017663A1 (fr)

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Publication number Priority date Publication date Assignee Title
DE102021121088A1 (de) 2021-08-13 2023-02-16 Safetec Gmbh Hubtisch zur Positionierung eines Messguts in einer Prüfkammer

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2910976A1 (fr) * 2014-02-17 2015-08-26 EnBW Energie BADEN-WÜRTTEMBERG AG Dispositif de vérification et procédé de détection d'une contamination de surface sur des objets allongés
WO2015135885A1 (fr) * 2014-03-10 2015-09-17 Nukem Technologies Engineering Services Gmbh Procédé permettant de mesurer un produit en vrac
JP2018179907A (ja) * 2017-04-20 2018-11-15 原子燃料工業株式会社 密度偏在状態の見積方法及び放射能の評価方法

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2000054071A1 (fr) 1999-03-09 2000-09-14 Central Research Institute Of Electric Power Industry Procede et dispositif de mesure de radioactivite, de concentration radioactive et de concentration superficielle de radioactivite
GB0506602D0 (en) 2005-03-31 2005-05-04 British Nuclear Fuels Plc Improvements in and relating to data collection

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP2910976A1 (fr) * 2014-02-17 2015-08-26 EnBW Energie BADEN-WÜRTTEMBERG AG Dispositif de vérification et procédé de détection d'une contamination de surface sur des objets allongés
WO2015135885A1 (fr) * 2014-03-10 2015-09-17 Nukem Technologies Engineering Services Gmbh Procédé permettant de mesurer un produit en vrac
JP2018179907A (ja) * 2017-04-20 2018-11-15 原子燃料工業株式会社 密度偏在状態の見積方法及び放射能の評価方法

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