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WO2006095188A1 - Detection de materiaux radioactifs par exemple dans les camions en utilisant la spectroscopie a rayons gamma et la detection de neutrons - Google Patents

Detection de materiaux radioactifs par exemple dans les camions en utilisant la spectroscopie a rayons gamma et la detection de neutrons Download PDF

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Publication number
WO2006095188A1
WO2006095188A1 PCT/GB2006/000859 GB2006000859W WO2006095188A1 WO 2006095188 A1 WO2006095188 A1 WO 2006095188A1 GB 2006000859 W GB2006000859 W GB 2006000859W WO 2006095188 A1 WO2006095188 A1 WO 2006095188A1
Authority
WO
WIPO (PCT)
Prior art keywords
radiation
detector
count rate
detectors
gamma
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/GB2006/000859
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English (en)
Inventor
Edward Marsden
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.)
Corus UK Ltd
Original Assignee
Corus UK Ltd
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 Corus UK Ltd filed Critical Corus UK Ltd
Publication of WO2006095188A1 publication Critical patent/WO2006095188A1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

Links

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
    • 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
    • G01V5/20—Detecting prohibited goods, e.g. weapons, explosives, hazardous substances, contraband or smuggled objects
    • G01V5/26—Passive interrogation, i.e. by measuring radiation emitted by objects or goods
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T1/00—Measuring X-radiation, gamma radiation, corpuscular radiation, or cosmic radiation
    • G01T1/36—Measuring spectral distribution of X-rays or of nuclear radiation spectrometry
    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01T—MEASUREMENT OF NUCLEAR OR X-RADIATION
    • G01T3/00—Measuring neutron radiation
    • G01T3/001—Spectrometry

Definitions

  • This invention relates to the detection of radiation associated with bodies under investigation.
  • the invention has application in security systems for detecting the unauthorised transport or importation of radioactive materials or devices which may present a security risk to the public.
  • EP 0746760 Bl discloses a method for the detection of the presence of radioactive impurities in an agglomeration of scrap metal, the method including the following steps;
  • a similar method can be beneficial in detecting the presence or otherwise of radioactive material or devices concealed about the bodies of persons, vehicles, baggage and the like.
  • the method can be adapted for use in monitoring the levels of radiation present in, for example, fumes or waste products emitted by processing plants or in any articles passing through a suitably configured detection apparatus on a conveyor belt.
  • Emissions monitored may be from non-metallic contaminants, and the energy bands may be selected from those characteristic of potassium, actinium, bismuth, lead and thallium.
  • the method may include measurement by scanning by a matrix of gamma ray detectors disposed around the body under investigation. The level of the emissions measured with the body present may be compared with a pre-selected level to estimate additionally the quantity of radioactive impurities present.
  • the apparatus and method of the present invention seeks to reduce and, if possible minimise the number of false alarms by providing a system that first detects the presence of a radiation source and then cross-checks the detected peak distribution against a relevant part of an energy spectrum to conclude whether the radiation is emitted from a specific point source or whether it is part of the natural background.
  • an apparatus for the detection of radiation associated with bodies under investigation comprising;
  • a plurality of radiation detectors configured for detecting one or both of gamma and neutron radiation, the radiation detectors being arranged around a portal through which bodies under investigation may pass; an integrated interface unit for receiving and displaying levels of gamma and/or neutron radiation detected by the radiation detectors; a processor unit associated with the interface unit, which processor unit is configured to perform the following method steps;
  • the method further includes the method of analysing the neutron radiation detected by each detector.
  • the method further includes the step of comparing the increased gamma count rate with a pre-determined value based on the probability of the increased count rate occurring, whereby the count rate is only analysed in accordance with steps (e) to (h) if the count rate is in excess of the pre-determined value.
  • the value is pre-determined at the point of a specific incident, the value is continually computed from prior background levels and all foreground data.
  • the method further includes the step of recording a picture of a body to which the an alert if generated.
  • the method further includes identifying the location of the radiation source on the body by analysing the relative time for each detector to detect an increased count and the relative distances between each detector.
  • the detectors are plastic scintillation detectors.
  • the radiation detectors are inorganic scintillation detectors. The latter are advantageous in that they have improved resolution in the detection of gamma energy (around 10% resolution) and an enhanced sensitivity and ability to categorize different sources. Furthermore, they are compact in size and thus allow flexible and easy installation around the portal.
  • Suitable detector configurations include but are not strictly limited to the following:
  • Hybrid Csl/plastic gamma and He3 neutron detector (GN 1000/P).
  • the combined detector configurations are desirably arranged such that a gamma crystal is sunk into a surface of the neutron moderator. Such an arrangement provides background shielding to the gamma crystal and optimises the overall size of the combined detector.
  • the apparatus may be provided with one or more of, a speed detection sensor, an image capture device, a vehicle occupancy detector and a vehicle number plate recognition device.
  • a speed detection sensor e.g., a Bosch Sensortec XPS detector
  • an image capture device e.g., a Bosch Sensortec XPS detector
  • a vehicle occupancy detector e.g., a Bosch Sensortec XPS detector
  • the portal size and shape may be adapted to specific applications.
  • the portal may be designed to be floor mounted and suitably proportioned to allow pedestrians to walk through.
  • the portal may be configured to allow large motor vehicles to pass through.
  • a smaller scale portal may be positioned around a conveyor on which objects such as packages or luggage are placed.
  • the portal may be located about an exit conduit from a processing plant so as to detect unexpectedly high levels of radioactive material in fluids released from the plant.
  • Figure 1 illustrates schematically an embodiment of the invention configured for detecting the presence of radioactive materials or devices in motor vehicles.
  • Figure Ia) shows the portion of the apparatus through which a motor vehicle passes
  • Figure Ib) shows the user interface part of the apparatus
  • Figure 2 illustrates a combined gamma and neutron radiation detector suitable for use in the embodiment of Figure 1;
  • Figure 3 illustrates schematically the operation of the sensors and processor of the embodiment of Figure 1 as a lorry passes through the portal.
  • the apparatus comprises a substantially square shaped portal frame 1 positioned over a gangway 2 along which a vehicle 3 can travel. Beneath the gangway 2 and along each side of the portal frame 1 are provided a plurality of gamma and/or neutron radiation sensors 4.
  • a camera 5 is also fixed to the portal frame 1. The camera 5 captures an image of the vehicle and occupants for recording and incorporates a an alphanumeric character recognition system by means of which vehicle registration plate numbers can be cross checked and validated with a central database.
  • the interface of the apparatus basically comprises a personal computer 6 terminal including a processor 7 connectable with a keyboard 8, mouse 9, display monitor 10, audio speakers 12 and a printer 13.
  • the processor is provided with a plurality of digital inputs 14 for receiving data from the plurality of sensors 4, one or more inputs 11 for receiving image data from the camera 5 and is powered by an uninterruptible power supply 15 which may be a mains supply or a dedicated supply.
  • the processor is optionally also provided with a network/modem interface to permit remote access to remote data bases and/or transmission of data to other locations.
  • the display monitor 10 is optionally provided with a touch screen interface (not shown).
  • Figure 2 illustrates in more detail a combined gamma and neutron radiation detector suitable for use in the embodiment of Figure 1.
  • the device detector comprises a moderator 21 (typically of polyethylene), in to which are set a pair of He3 neutron tubes 22a, 22b.
  • a recess 23 which is positioned about midway between the two He3 neutron tubes 22a, 22b.
  • the recess 23 is lined with a lead screen 24, behind which is located a CsI gamma radiation detector 25.
  • the compact design of the detector permits improved, directional shielding resulting in a reduced background radiation count without a reduction in the count rate detected from the body under investigation.
  • the detectors are automatically stabilised. This is achieved by applying variable gain based on detector temperature and on the energy peak produced by 4OK (1.46 MeV) emission. In most circumstances sufficient 4OK is present with normal background measurement for this purpose. Should this not be the case a. small amount of this isotope can be encapsulated within the detector. Alternatively, an automated calibration source may be used.
  • Temperature control may be incorporated within the detector to maintain calibration of the detector.
  • FIG 3 illustrates the radiation detection and analysis operation performed by the embodiment of Figure 1. The mode of operation is further described below.
  • the processor is controlled by a software package which is configured to run under a Windows TM operating system on a standard personal computer.
  • the processor when installed with the software performs the following functions;
  • Suspected sources are initially identified by repeated calculation of the statistical probability of a given count rate with respect to the background datum or 'gamma rareness', i.e., a count rate that is significantly above the datum will have a low probability of occurring or a high 'rareness'. Only when a pre-defined rareness is exceeded is the data point identified as 'suspect'. By using this 'rareness' measurement, the user can effectively select an acceptable false alarm rate which is preferable to an arbitrary threshold which might typically be used in prior art systems. Data adjacent the 'suspect' data point in time and space is successively combined with the data at the 'suspect' point and the degree of 'rareness' recalculated. This process is repeated until the 'rareness' measurement is maximised.
  • Energy information associated with all the data points is combined to produce a definitive energy spectrum for the 'suspect' area.
  • the energy is fed into a peak-fitting algorithm, which approximates the energy data presented to it with a series of energy peaks shaped to the performance of the detector.
  • a look up table is then used to identify the most likely isotope (or combination of isotopes) to match to the identified 'suspect' peaks.
  • the isotope may be identified as an industrial isotope, a special nuclear material (SNM), naturally occurring radioactive material (NORM) or a medical isotope.
  • SNM nuclear material
  • NOM naturally occurring radioactive material
  • the peak distribution should be considered. If, for example, the peak is not a point source then the radiation detected may well be natural. A wide distribution of the energy spectra is also likely to indicate NORM.
  • the relationship of all detectors must also be considered. If all the detectors detect similar patterns then the radiation detected then this may indicate NORM rather than a point radiation source.
  • the position of a 'suspect' area in time and space is used to predict the location of the source in the body. This can be displayed pictorially on the display monitor. A 'suspect' area that extends over a significant portion of a vehicle length and/or cross section is indicative of NORM; this information can be combined with the isotope results to assist in identifying discrete sources of NORM.
  • Neutron sensitivity is optimised by combining counts from adjacent detectors, in a master slave arrangement.

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

Abstract

Cette invention se rapporte à un appareil destiné à détecter la radiation associée à des éléments à examiner, comprenant, - une pluralité de détecteurs de radiations configurés pour détecter aussi bien la radiation gamma que la radiation de neutrons, les détecteurs de radiation étant disposés autour d’un portail au travers duquel les éléments à examiner doivent passer ; une unité de processeur configurée pour accomplir les étapes du procédé suivant ; a) l’analyse du taux de comptage total de gammas et le spectre d’énergie pour chaque détecteur ; b) la détection d’un taux de comptage de gammas augmenté à travers un ou plusieurs détecteurs ; c) l’altération du taux de comptage à travers chaque détecteur pour compenser le rayonnement de fond ; d) la combinaison de spectres d’énergie associés à chaque détecteur détectant un taux de comptage augmenté, afin de fournir un unique spectre combiné ; e) l’analyse du spectre pour identifier des pics associer aux isotopes spécifiques ; f) l’analyse de la répartition des pics pour identifier une source ; et g) le fait de prévenir l’utilisateur lorsque qu’une source de radiations est détectée.
PCT/GB2006/000859 2005-03-11 2006-03-10 Detection de materiaux radioactifs par exemple dans les camions en utilisant la spectroscopie a rayons gamma et la detection de neutrons Ceased WO2006095188A1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB0504951.5 2005-03-11
GB0504951A GB2424065A (en) 2005-03-11 2005-03-11 Radiation detection apparatus

Publications (1)

Publication Number Publication Date
WO2006095188A1 true WO2006095188A1 (fr) 2006-09-14

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Country Status (2)

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GB (1) GB2424065A (fr)
WO (1) WO2006095188A1 (fr)

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DE102006061006A1 (de) * 2006-10-13 2008-04-17 Tsinghua University Vorrichtung und Verfahren zur schnellen Abbildungsinspektion eines beweglichen Gegenstandes
RU2417386C2 (ru) * 2007-12-29 2011-04-27 Нуктек Компани Лимитед Способ и система обнаружения радиации с использованием многоканального спектрометра и устройство для обработки данных
DE202010005853U1 (de) 2010-04-19 2011-08-10 Cetto Maschinenbau Gmbh & Co. Kg Strahlungsdetektorvorrichtung
US8389941B2 (en) 2008-06-11 2013-03-05 Rapiscan Systems, Inc. Composite gamma-neutron detection system
US8837670B2 (en) 2006-05-05 2014-09-16 Rapiscan Systems, Inc. Cargo inspection system
US8840303B2 (en) 2008-05-20 2014-09-23 Rapiscan Systems, Inc. Scanner systems
US8963094B2 (en) 2008-06-11 2015-02-24 Rapiscan Systems, Inc. Composite gamma-neutron detection system
WO2015057973A1 (fr) * 2013-10-16 2015-04-23 Rapiscan Systems, Inc. Systèmes et procédés pour résolution d'alarme de menace de z élevé
US9052403B2 (en) 2002-07-23 2015-06-09 Rapiscan Systems, Inc. Compact mobile cargo scanning system
US9218933B2 (en) 2011-06-09 2015-12-22 Rapidscan Systems, Inc. Low-dose radiographic imaging system
US9223050B2 (en) 2005-04-15 2015-12-29 Rapiscan Systems, Inc. X-ray imaging system having improved mobility
US9223049B2 (en) 2002-07-23 2015-12-29 Rapiscan Systems, Inc. Cargo scanning system with boom structure
US9285498B2 (en) 2003-06-20 2016-03-15 Rapiscan Systems, Inc. Relocatable X-ray imaging system and method for inspecting commercial vehicles and cargo containers
US9310323B2 (en) 2009-05-16 2016-04-12 Rapiscan Systems, Inc. Systems and methods for high-Z threat alarm resolution
US9332624B2 (en) 2008-05-20 2016-05-03 Rapiscan Systems, Inc. Gantry scanner systems
US9429530B2 (en) 2008-02-28 2016-08-30 Rapiscan Systems, Inc. Scanning systems
US9557427B2 (en) 2014-01-08 2017-01-31 Rapiscan Systems, Inc. Thin gap chamber neutron detectors
US9618629B2 (en) 2014-11-25 2017-04-11 Jens Hovgaard Apparatus and method for monitoring performance of radiation detector
US9632205B2 (en) 2011-02-08 2017-04-25 Rapiscan Systems, Inc. Covert surveillance using multi-modality sensing
US9791590B2 (en) 2013-01-31 2017-10-17 Rapiscan Systems, Inc. Portable security inspection system
CN113466923A (zh) * 2020-03-31 2021-10-01 同方威视技术股份有限公司 放射性物质检测方法及放射性物质检测装置
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US9310323B2 (en) 2009-05-16 2016-04-12 Rapiscan Systems, Inc. Systems and methods for high-Z threat alarm resolution
DE202010005853U1 (de) 2010-04-19 2011-08-10 Cetto Maschinenbau Gmbh & Co. Kg Strahlungsdetektorvorrichtung
WO2011131339A2 (fr) 2010-04-19 2011-10-27 Cetto Maschinenbau Gmbh & Co. Kg. Dispositif détecteur de rayonnement
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US10942291B2 (en) 2011-02-08 2021-03-09 Rapiscan Systems, Inc. Covert surveillance using multi-modality sensing
US11822041B2 (en) 2011-02-08 2023-11-21 Rapiscan Systems, Inc. Systems and methods for improved atomic-number based material discrimination
US9632205B2 (en) 2011-02-08 2017-04-25 Rapiscan Systems, Inc. Covert surveillance using multi-modality sensing
US11307325B2 (en) 2011-02-08 2022-04-19 Rapiscan Systems, Inc. Covert surveillance using multi-modality sensing
US9218933B2 (en) 2011-06-09 2015-12-22 Rapidscan Systems, Inc. Low-dose radiographic imaging system
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GB2534799A (en) * 2013-10-16 2016-08-03 Rapiscan Systems Inc Systems and methods for high-Z threat alarm resolution
GB2534799B (en) * 2013-10-16 2020-09-02 Rapiscan Systems Inc Systems and methods for high-Z threat alarm resolution
WO2015057973A1 (fr) * 2013-10-16 2015-04-23 Rapiscan Systems, Inc. Systèmes et procédés pour résolution d'alarme de menace de z élevé
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