MX2008007094A - Container verification system for non-invasive detection of contents - Google Patents

Container verification system for non-invasive detection of contents

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Publication number
MX2008007094A
MX2008007094A MXMX/A/2008/007094A MX2008007094A MX2008007094A MX 2008007094 A MX2008007094 A MX 2008007094A MX 2008007094 A MX2008007094 A MX 2008007094A MX 2008007094 A MX2008007094 A MX 2008007094A
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MX
Mexico
Prior art keywords
sensors
gamma
radiation
further characterized
housing
Prior art date
Application number
MXMX/A/2008/007094A
Other languages
Spanish (es)
Inventor
David L Frank
Original Assignee
Innovative American Technology Inc
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Filing date
Publication date
Application filed by Innovative American Technology Inc filed Critical Innovative American Technology Inc
Publication of MX2008007094A publication Critical patent/MX2008007094A/en

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Abstract

A radiation, explosives, and special materials, detection and identification system includes a housing supporting one or more gamma sensors and one or more solid-state neutron sensors proximate to container contents under examination. The system collects radiation data from the sensors and compares the collected data to one or more stored spectral images representing one or more isotopes to identify one or more isotopes present. The identified one or more isotopes present are corresponded to possible materials or goods that they represent. The possible materials or goods are compared with the manifest relating to the container to confirm the identity of materials or goods contained in the container or to detect and/or identify unauthorized materials or goods in the container. A battery powered sensor arrangement is also disclosed.

Description

CONTAINER VERIFICATION SYSTEM FOR NON-INVASIVE DETECTION OF CONTENTS FIELD OF THE INVENTION This invention relates in general to shipping container content detection systems, and more particularly to a non-invasive system and method for detecting and identifying hazardous materials within containers, such as radiation and / or neutron emission materials, explosives. , and special materials such as highly enriched uranium and additionally to identify the radiological materials that normally occur within the containers. Such detection of non-invasive container content and verification system works without having to enter the cavity of a container under examination. The system can include a radiation sensor system that uses integrated sensors for gamma and neutron detection, and with a spectral analysis capability to identify the specific isotope (s) of materials in containers. Such a system may also include detection and identification of explosives and special materials in containers. These special materials can include highly enriched uranium.
BACKGROUND OF THE INVENTION Current attempts to provide radiation, neutrons, explosives, and special materials, detection systems to verify shipping containers, such as those that have been mounted on gantry crane arms have resulted in detection systems that have limited sensitivity and efficiency and do not They can withstand the severe environment. Radiation detection systems to detect radiation from shipping containers did not have the ability to detect specific isotopes. The inability to identify the specific isotopes present in the containers had not allowed these systems to additionally identify the goods or materials within the containers and therefore have restricted their ability to reliably evaluate the validity of the contents. Furthermore, it has not been allowed for an express use for verification of container content which has resulted in substantial false alarm rates and has impacted the flow of trade. In addition, these conventional implementations can be difficult to overcome analog noise caused by analogous wiring systems. In addition, high-impact factors of up to 200 G-forces per minute during normal operations of handling large vessels can cause failure and unreliable operation for key components of conventional radiation detection systems. These characteristics of current shipping container detection systems, such as for use with gantry cranes, detrimentally affect the commercial viability of radiation, neutron, explosives, and special materials, detection systems, cause substantial negative impacts to the flow of trade, and particularly reduce their effectiveness and reliability in environments of rugged use. In addition, the technologies used to detect explosives can not penetrate metal or include methods that are harmful to humans such as active X-ray or gamma imaging, leaving ineffective means to detect or identify explosives hidden in shipping containers. Therefore there is a need to overcome problems with prior art as discussed above.
BRIEF DESCRIPTION OF THE INVENTION In accordance with one embodiment of the present invention, a detection system and method detects neutron radiation with more efficient methods that effectively eliminate issues of accumulated vibration by analog wiring, and shock factors, such as those found in rugged operating environments. . The gamma sensors provide data with high resolution of 1 kev to 3 kev to allow spectral analysis. In addition, one embodiment of the present invention provides radiation sensor support functions such as automated calibration, automated gain control, and verification of Automated calibration to allow highly accurate calibration of a sensor or sensor array. The present invention, in accordance with one embodiment, allows simple integration of proprietary or commercially produced radiation sensors in a non-aggressive container verification system. Additionally, one embodiment of the present invention includes highly accurate and rapid spectral analysis software for interrogating radiation data acquired from radiation sensors, and for identifying the one or more specific isotopes and their proportion. To verify if radioactive materials are hidden within a shipping container, identification and isotope detection systems can be implemented in combination with a container, such as with a crane assembly used to elevate shipments and transfer containers. Typically, the container crane includes a lifting attachment which engages the shipping container. An isotope identification and detection system could consist of one or more neutron and gamma sensors that are mounted on the crane lifting attachment (or on the separating arm) and provide detailed radiation spectral data to a computer that performs spectral analysis for the detection and identification of isotope (s) that are present in the containers. Many radiological materials that occur normally exist in common property and cause radiation detection systems to produce false alarms. By identifying the specific isotope (s) that is present, the system is also allowed to identify the types of goods or materials that the isotopes represent. With a list of potential goods representing the isotopes identified, the system can make a comparison between the identified goods or materials and the declared shipping container to determine if the radiological material (s) presents correspondence of the expected materials within the container. The procedure of 1) identifying the isotope (s) that is inside a container, 2) identifying the goods or materials representing the isotopes, and 3) verifying the contents of the manifest against the identified goods, allowing efficient verification of the container without impact negative for the flow of trade. Also, one embodiment of the present invention benefits from gamma sensors that are integrated with analog circuits and digital converters to eliminate analog wiring and greatly reduce the analog portion of the system design thereby reducing background noise in the system design. The introduction of solid-state neutron sensors that are not affected by system vibration or impact and that have integrated analog-to-digital converters greatly reduces background noise during system operation. This results in more reliable detection and detection of radiation inside the vessels during normal shipping and container handling operations. In one embodiment, a Sensor Interface Unit (SIU) provides an open interface for radiation sensors based on an analog sensor interface module contained in an interchangeable daughter card. The analog section is responsible for amplifying and molding the sensor output, and convert the analog pulses to a digital signal. The digital section reads the digital signal, detects the peaks of the incoming pulses, and sends the peak data over a communication path to a processor that performs spectral analysis. In accordance with one embodiment, the gamma sensors are incorporated into the lifting accessory (eg, such as in the separator bar), or the gamma sensors are mounted in a housing (eg, metal tube designed to be strong and rugged). to work in combination with the crane arm environment (or separator bar) still has a lower surface (or surface facing the vessels under examination) that provides minimal impact on the gamma particles that pass through the housing to maintain the sensitivity of the gamma sensors This can be achieved through the use of specialized or machined materials on the surface of the housing in proximity to the containers under examination, such as the lower metal surface of the sensor tube at each sensor location. In accordance with one modality, the neutron sensors are incorporated in the separator bar of the crane assembly. Alternatively, the neutron sensors can be mounted in a housing, such as a metal box, which is designed to be strong and rugged such as to work in combination with the crane arm assembly and / or spacer bar, however it has minimal impact on the neutron particles that pass through the housing to maintain sensitivity of the sensors neutronics A neutron moderator can be deployed inside the housing to assist in the detection of thermal neutrons. Additional impact absorber methods provided by crane manufacturers further reduce the impact and vibrations on the separator bar of the crane assembly and finally on the gamma sensors and neutron sensors. In accordance with another modality, the gamma radiation sensors include environmental temperature detectors with high resolution and a gamma range of 1 kev to 3 Mev. A sensor combination could be through the deployment of sodium iodide detectors to allow a range of up to 3 Mev with good resolution from 662 kev to 3 Mev and adding cadmium-zinc telulide detectors (CZT) to allow high resolution 1 kev and 662 kev. The combination of these two types of detectors or other types of detectors allows high resolution and provides coverage to identify a complete range of radiation isotopes. In accordance with another embodiment, activated neutron sensors with one or more batteries and / or battery activated gamma sensors are deployed within the shipping container. In accordance with another embodiment, the radiation sensors are connected to a processor system that collects and analyzes the gamma energy levels and detected spectral data and then sends this data to a spectral analysis engine. The data of each sensor is treated individually and sent to the spectral analysis engine to allow analysis of individual sensor data or sensor group data. The processor system and a data collection system is electrically coupled with each sensor device within the sensor system of the crane arm (or separating head), to collect signals from the array of neutron sensor devices to form histograms with the collected spectral data. The histograms are used by the spectral analysis system to identify the isotopes that are present. The spectral analysis system, in accordance with one modality, includes an information and software processing system to analyze the collected data and identifies the isotopes that are present. The spectral analysis software consists of several filtering techniques for background noise removal, interfering signals, such as backscattering radiation, and more than one method for providing multi-confirmation of the identified isotopes. More than one isotope should be present, the system identifies the proportion of each isotope present. Examples of methods that can be used for spectral analysis such as in the spectral analysis software in accordance with a modality of a container verification system include: 1) a method and system for improving the performance of the pattern recognition system as described in the US Patent No. 6,847,731; and 2) a LINSCAN method (a linear spectral analysis method) as described in the Application for Patent of E.U.A. Provisional No. 60 / 759,331, filed January 17, 2006, by the inventor David L. Frank, and entitled "Method For Determination Of Constituents Present From Radiation Spectra And, If Available, Neutron And Alpha Occurrent"; The complete collective teachings of which are incorporated in this document for reference. A user interface of the information processing system, in accordance with a modality, provides a graphic view of the detected radiation spectrum and the identified isotopes. The user interface allows a system user to observe, among other things, individual sensors, groups of sensors, individual sensors, and groups of sensors, to quickly identify maintenance conditions, detected radiation, and identified isotopes. Another embodiment of the present invention provides detection of material using radiofrequencies that are directed into the shipping container by means of the raw metal contacts that exist between the container and the crane arm (or separator bar) during operation of the crane assembly. The use of radiofrequency to detect material such as Nuclear Quadripolar Resonance (NQR) is a recognized technology for the detection and identification of explosives and other materials. Such a method could be used in the crane assembly (for example, on the separator bar) for pulse RF energy within the container cavity under examination and use of the container as a means to collect return signals for analysis, detection, and container content identification.
A key aspect of this modality is to take advantage of electrical connections (metal-to-metal contacts) between the crane arm (or spacer arm) and the container to allow in a non-invasive manner, RF analysis and detection of explosives and other materials contained within the container under examination. This method overcomes the inability of RF signals to penetrate sealed metal objects, such as a shipping container, and to analyze the contents of the container for hazardous or harmful materials using a method that is safe when used in an area with Human contact. In one embodiment of this invention, a sensor interface unit is used to allow the integration of commercial sensors, and also exclusive sensors, into a non-invasive container verification system.
BRIEF DESCRIPTION OF THE DRAWINGS FIG. 1 is an image illustrating a container in the vicinity of a crane arm assembly (or spacer bar) with sensors in a sensor housing, in accordance with one embodiment of the present invention. FIG. 2 is a simplified schematic view illustrating an exemplary arrangement of sensors and associated electronics on a crane arm assembly (or a separator bar).
FIG. 3 is a simplified schematic view illustrating an exemplary configuration of sensors in a sensor housing. FIG. 4 is a side longitudinal cross-sectional view of a spacer bar of a crane arm assembly showing an exemplary configuration of a sensor housing mounted on the spacer bar, in accordance with one embodiment of the present invention. FIG. 5 is a simplified schematic view illustrating an exemplary RF detection system for detecting explosives and special materials in a container. FIG. 6 is a block diagram illustrating an exemplary data collection and analysis system, in accordance with one embodiment of the present invention. FIG. 7 is a block diagram illustrating an exemplary battery operated sensor.
DETAILED DESCRIPTION OF THE INVENTION Although the specification concludes with claims defining the characteristics of the invention that are considered novel, it is believed that the invention will be better understood from the consideration of the following description in combination with the appended figures, in which like reference numbers are used. they carry forward.
It is understood that the embodiments described are merely exemplary of the invention, which may be represented in various forms. Therefore, specific structural and functional details described herein are not to be construed as limiting, but merely as a basis for the claims and as a representative basis for the teachings of a person skilled in the art to variously employ the present invention in Virtually any properly detailed structure. In addition, the terms and phrases used in this document are not intended to be limiting; but instead, provide an understandable description of the invention. The terms "a" or "an", as used herein, are defined as one or more than one. The term "plurality", as used herein, is defined as two, or more than two. The term "other", as used herein, is defined as at least one second or more. The terms "including" and / or "having", as used herein, are defined as comprising (i.e., open language). The term "coupled", as used herein, is defined as connected, though not necessarily directly, and not necessarily mechanically. The terms "program", "computer program", "software application" and the like as used herein are defined as a sequence of instructions designed for execution in a computer system. A program, computer program, or software application may include a subroutine, a function, a procedure, an object method, an object implementation, an executable application, a Java program, a server program, a source code, an object code, a dynamic load library / shared library and / or another sequence of instructions designed for execution in a computer system. A data storage medium, as defined herein, includes many different types of computer readable media that allow a computer to read data from there that keeps the data stored so that the computer is able to read the data again. Such a data storage medium may include, for example, non-volatile memory, such as ROM, flash memory, battery-backed RAM, disk drive memory, CD-ROM, DVD, and other permanent storage media. However, still such volatile storage as RAM, buffers, cache memory, and network circuits are contemplated to serve as such data storage means in accordance with different embodiments of the present invention. The present invention, in accordance with one embodiment, overcomes problems with prior art by providing high resolution gamma sensors with integrated analog-to-digital converters to reduce noise and shock factor and provide solid-state neutron sensors that are strong and unaffected by vibration or shock factor. In addition, by mounting these radiation detection devices in a shock absorbing housing which is also mounted with impact on a Separating bar of a crane assembly allows a strong design that can withstand impact forces of up to 200 G-force every minute for an extended period of time. The collected radiation sensor data allows the detection and identification of the specific isotopes that are present in a container under examination. One embodiment of the invention includes gamma and neutron sensors that provide significantly improved isotope detection and identification and sensitivity efficiency, especially for use in a harsh environment such as mounted on a spacer bar of a crane arm assembly. The sensors are connected to a Sensor Interface Unit (SIU) that provides calibration, automated gain control, calibration verification, remote diagnostics, signal processing and processor communications for spectral analysis of sensor data. The SIU is described in the U.S. Patent Application. Provisional No. 60 / 759,332, filed January 17, 2006, by the inventor David L. FRANK, and entitled "Sensor Interface Unit And Method For Automated Support Functions For CBRNE Sensors", which is incorporated herein by reference . The neutron sensor devices are solid state and address the deficiencies of conventional neutron sensor devices especially when deployed in a harsh and aggressive operating environment such as on a spacer bar of a crane arm assembly.
In accordance with one embodiment of the present invention, a sensor system mounted on the crane arm assembly (or separator bar) may comprise a node within a distributed architecture system of Explosives (CBRNE) and Nuclear, Radiation, Biological, Chemical, Integrated. An example of such a system is described in the U.S. Patent Application. No. 60 / 759,373, filed January 17, 2006, and entitled "Distributed Sensor Network ITU Common Platform For CBRNE Devices", whose full teachings are incorporated for reference. In accordance with one embodiment of the present invention, a radiation sensor system mounted on a crane arm (separator bar) comprises one or more impact and neutron sensor devices mounted on impact to protect against impact forces of up to 200 G- forces per minute for an extended period of time. One such method is a spring-cushion-mass that can be used to suppress impact effects. It is assumed that the sensing device is infinitely rigid, and the impact pulse is transferred directly into the spring mass absorber. Examples of such impact absorbing systems are found in FIGS. 3 and 4, will be discussed more fully below. The sensors can also be shielded from electromagnetic interference (EMI). A data collection system, electrically coupled to each sensor device, collects signals from the sensor devices. The collected signals represent if each sensor device has detected neutron or gamma radiation. Optionally, a remote monitoring system is communicatively coupled with the data collection system to remotely monitor the signals collected from the sensor devices and thus remotely determines whether one or more neutron or gamma sensor devices in the array have provided gamma data or data. of neutron radiation, and a spectral analysis system identifies the specific isotopes detected by the sensors, as will be discussed more fully below. A user interface provides data related to the sensor, such as a graphical presentation of the data from each sensor and group of sensors, the detection of radiation, and the identification of one or more isotopes detected by the sensors. An exemplary radiation identification and detection system mounted on a spacer bar of a crane assembly and the operation thereof is now described in accordance with exemplary embodiments of the present invention. An exemplary radiation detection and identification system deployed on a crane arm (or spacer bar) 101, or on the exterior 102 or within a container 103, as illustrated in FIG. 1, provides significantly improved detection efficiency and sensitivity over previous attempts for radiation detection devices deployed in combination with a crane assembly. FIG. 1 illustrates exemplary installation positions for various housing units sensor 104. The characteristics and inventive advantages of the exemplary embodiments of a radiation detection and identification system, as deployed in combination with a crane assembly or other shipping container handling operation, will be discussed below. However, it is assumed that the reader has an understanding of radiation and sensor technologies. Examples of neutron detection semiconductor devices and technology are described in the U.S. Patent. No. 6,545,281 to McGregor et al., Filed July 6, 2001, and entitled "PCKED SURFACE NEUTRON SENSOR", and further described in the U.S. Patent. No. 6,479,826 to Klann et al., Filed November 22, 2000, and entitled "COATED SEMICONDUCTOR FOR NEUTRON DETECTION" and in the U.S. Patent Application. No. 10 / 695,019, entitled "HIGH EFFICIENCY NEUTRON SENSORS AND METHODS OF MAKIN SAME" by McGregor et al., The full group teachings thereof are incorporated herein by reference. With reference to FIG. 2, an exemplary radiation detection and identification system is deployed on a crane arm assembly (or spacer bar) 201. The system includes one or more sensors 202, including gamma sensors and neutron sensors. Gamma sensors 202 provide high resolution detection through a range of 1 kev to 3 Mev. One or more neutron sensors 202 comprise solid state devices. The sensors 202 are communicatively coupled with a communications and data collection system 203. The mounting of the sensors 202 on the crane arm assembly 201 will be discussed in more detail below. With reference to FIG. 3, an exemplary frame structure, illustrated as a housing 300, can be configured to support multiple types of gamma sensors 303, 304, and neutron sensors 305. The housing 300 is mounted on a crane arm assembly (or spacer arm) ( it is not shown in FIG 3). The housing 300 provides modular installation of a radiation sensor system as well as impact absorption capabilities to deal with impact forces of up to 200 G-forces per minute for an extended period that may be experienced during the operation of such crane arm assemblies. while handling large containers. The accommodation 300, in this example, is electrically isolated from the crane arm assembly and additionally provides EMI shielding for any electronic circuits and other devices in the housing 300. Impact absorbing assemblies 301, 302 for the housing 300 provide impact absorption between the housing 300 and the crane spacer bar (not shown). Impact sensor assemblies 306 are provided to additionally isolate sensors 303, 304, 305, from impact forces experienced during operation of the crane spacer bar (not shown). Other electronics and devices such as sensor interface modules, data collection electronics, and data communication electronics may be included within the housing 300. Any of these circuits and / or modules can also be mounted in the housing 300, or in another separate housing (not shown), using impact absorbing mounts to also help isolate these from the impact forces experienced during the operation of the spacer bar. the crane (not shown). Additionally, in addition to impact absorption, these circuits and modules in housing 301, in accordance with the present example, benefit from electrical isolation of the crane arm assembly, and EMI shielding by housing 300. FIG. 4 illustrates another example of a mounting arrangement between a crane arm assembly (or spacer bar) 401 and a frame structure (eg, a housing) 402. The frame structure 402 in this example comprises at least one housing part containing the sensors 414. At least one partial housing 402 includes one or more housing walls fixed to a frame structure 402. One or more walls help to protect the sensors 414, and other electronics and devices, in the less partial accommodation 402 of external environmental hazards. Areas that do not include a wall in the frame structure 402 may provide a clearer and more clear path (without interference from another wall structure) between detection surfaces of the sensors 414 and a container under examination to improve the detection sensitivity of the sensors 414. A group of impact assemblies 404, 406, 408, 410, 412, provides impact absorption to help isolate frame structure 402, and sensors 414 and other electronics and modules in the at least partial housing 402, of impact forces experienced during operation of the crane spacer bar 401. The at least partial housing 402 is mounted on the spacer bar 401 in a region with recesses, such as in a recessed region of a beam-l shape of the spacer bar 401. In this example, the sensors 414 are mounted in the frame structure 402 for extending the sensors 414 out of the recessed region of the beam-1 of the rod 401. This mounting arrangement of the sensors 414 provides a direct and clearer path (without interference from another structure such as the spacer bar 401 = between radiation detection surfaces of the sensors 414 and a container under examination (not shown in FIG. 4) being maintained by the crane arm assembly (or spacer bar) 401. Although the frame structure 402 has been discussed for example comprising at least a partial housing supporting one or more sensors 414, it should be understood by those skilled in the art. The technique in view of the present discussion that the term "frame structure" should be given a very broad meaning to include many different types of frame structures that can support one or more sensors 414 in accordance with alternative embodiments of the present invention. A frame structure may include a frame without housing walls A weapon structure zon may also include the structure of a crane arm assembly, such as the spacer bar itself, to provide support for sensors 414. For example, sensors 414, and even a digital data collection system 610 and a spectral analysis system 640 (shown in FIG 6) can be integrated on the separating bar of a gantry crane. The frame structure may also include a structure that is separate and independent of a crane arm assembly. For example, a frame structure may comprise a forklift truck structure. Alternatively, a frame structure may comprise a stationary support structure that supports sensors 414 and containers that can be positioned in proximity to sensors 414 for a content examination operation of the container. In a modality, the frame structure is contemplated to include the frame structure of the container under examination. Such a frame structure can support one or more sensors 414 within the container and / or outside the container, as will be discussed in more detail below. With reference to FIG. 5, in accordance with one embodiment of the present invention, a sensor system of special material and crane arm explosives comprises one or more RF generators and receivers 502 generating signals that are pulsed within the vessel cavity through the contacts electrical cables 503 between the crane arm assembly (separator bar) 501 and the container 504 under examination. The RF return signals (from the cavity of the container under examination) are received by one or more receivers 502 through the container 504 and the electrical connection for the crane arm assembly (separator bar) 501.
The container and interconnecting structures collectively provide one or more RF antenna systems by coupling the RF return signals to the RF 502 receivers. The RF 502 receivers then send the RF return signals to a data collection and analysis system (such as the system shown in FIG 6) for processing. The receivers 502, in this example, include processing circuits that convert the received return signals (eg, received analog signals) into data signals that are provided to the data collection and analysis system for further processing. With reference to FIG. 6, a data collection system 610, in this example, is communicatively coupled via wiring, wireless communication link, and / or other communication link 605 with each of the gamma radiation sensor devices 601 and neutron sensor devices 602 in each sensor unit, and with each of the RF sensor device (s) 603 such as including one or more receivers 502 shown in FIG. 5. The cabling preferably includes shielded analog cable to reduce background noise in the output signals from one or more sensors 601, 602, 603. The data collection system 610 includes an information processing system with data communication interfaces 624 that collect signals from the radiation sensor units 601, 602 and from the RF sensor device (s) 603. The collected signals, in this example, represent spectral data detailed from each gamma sensor device that has detected radiation. The 610 data collection system is modular in design and can be used specifically for detection and identification of radiation, or for RF signal collection for detection and identification of explosives and special materials, or it can be combined to support radiation detection and collection of RF signal. The data collection system 610 is communicatively coupled with a local controller and monitor system 612. The local system 612 comprises an information processing system that includes a computer, memory, storage and a user interface 614 such as a screen on a monitor and keyboard, or other user input / output device. In this example, the local system 612 also includes a multiple channel analyzer 630 and a spectral analyzer 640. The multiple channel analyzer (MCA) 630 comprises a device composed of many single channel analyzers (SCA). The single channel analyzer interrogates analog signals received from the individual radiation sensors 601, 602, and determines whether the specific energy range of the received signals is equal to the range identified by the individual channel. If the received energy is inside the SCA the SCA counter is updated. Over time, the SCA counts accumulate. In a specific time interval, a multi-channel analyzer 630 includes a number of SCA counts, which results in the creation of a histogram. The histogram represents the spectral image of the radiation that is present. The MCA 630, in accordance with one example, uses analog-to-digital converters combined with computer memory that is equivalent to hundreds of thousands of SCAs and meters and is dramatically more powerful and cheaper. The histogram is used by the 640 spectral analysis system to identify the isotopes that are present in materials that are contained in the container under examination. One of the functions performed by the information processing system 612 is spectral analysis, performed by the spectral analyzer 640, to identify one or more isotopes, explosives or special materials contained in a container under examination. With respect to radiation detection, the 640 spectral analyzer compares one or more spectral images of the radiation present with known isotopes that are represented by one or more spectral images 650 stored in the isotope database 622. By capturing multiple variations of spectral data for each isotope there are numerous images that can be compared with one or more spectral images of the present radiation. The isotope database 622 maintains the one or more spectral images 650 of each known isotope. These multiple spectral images represent several levels of acquisition of known isotope spectral radiation data so the isotope radiation data to be identified can be compared and identified using various amounts of spectral data that may be available from one or more sensors. If there are small quantities (or large amounts of data acquired from the sensor, the spectral analysis system 640 compares the radiation data acquired from the sensor with one or more spectral images associated with each known isotope.) In summary, the spectral analysis system analyzes the radiation data collected to identify one or more isotopes associated with the radiation data collected by comparing one or more spectral images of the collected radiation data to one or more spectral images stored in the isotope database 622, where each known isotope is associated with one or more spectral images stored in the isotope database 622. One or more stored spectral images associated with a known isotope represent one or more levels of spectral radiation data that can be collected from one or more sensors when the known isotope is detected This analysis by comparison n with several spectral images associated with known isotopes significantly improves the reliability and efficiency of matching acquired spectral image data from the sensor to spectral image data of each isotope may be identified. Once one or more possible isotopes are determined present in the radiation detected by the sensor (s), the information processing system 612 can compare the isotope mixture against possible materials, goods, and / or products, which may be present In the container under examination. Additionally, a manifest database 615 includes a detailed description of the contents of each container to be examined. The manifest 615 can be referred by the information processing system 612 to determine whether the possible materials, goods, and / or products, contained in the container correspond to the authorized materials expected, goods, and / or products, described in the manifest for the particular container under examination. This matching process, in accordance with one embodiment of the present invention, is significantly more efficient and reliable than any container content monitoring process in the past. The spectral analysis system 640, in accordance with one modality, includes an information and software processing system that analyzes the collected data and identifies the isotopes that are present. The spectral analysis software consists of more than one method to provide multiple confirmation of the identified isotopes. If more than one isotope is present, the system identifies the proportion of each isotope present. Examples of methods that can be used for spectral analysis such as in the spectral analysis software in accordance with a modality of a container content verification system, include: 1) a method and system for improving the performance of the receiver recognition system; pattern as described in the US Patent No. 6,847,731; and 2) an LINSCAN method (a linear spectral method analysis) as described in the Provisional Patent Application of E.U.A. Do not. 60 / 759,331, filed January 17, 2006, by the inventor David L. Frank, and entitled "Method For Determination Of Constituents Present From Radiation Spectra And, If Available, Neutron And Alpha Occurrences"; whose complete group teachings are incorporated in this document for reference. With respect to the analysis of collected data pertaining to special materials and / or explosives, the spectral analyzer 640 and the information processing system 612 compare special materials and / or possible explosives identified with the manifest 615 by converting the manifest data stored related to the shipping container under examination with the expected radiological and / or explosive materials and then comparing the special materials and / or possible explosives identified with the expected explosives and / or radiological materials. If the system determines that there is no correspondence with the manifest for the container then the identified special materials and / or explosives are unauthorized. The system can then provide information to the system's supervisory personnel to alert them to the alarm condition and take appropriate action. The user interface 614 allows a supervisory or service personnel to operate the local system 612 and monitor the status of the detection and identification of isotope radiation and / or the detection of RF signals by the collection of sensor units 601, 602 and 603 deployed in the frame structure, such as in the crane arm assembly (or separator bar). The user interface 614, for example, may present to the user a representation of the collected return signals received, or the identified possible explosives and / or special materials in the shipping container under examination, or some special materials system and / or unauthorized explosives identified contained within the shipping container under examination, or some combination thereof. The data collection system may also be communicatively coupled to a remote control and monitoring system 618 such as via a network 616. The remote system 618 comprises an information processing system that has a computer, memory, storage, and a computer. user interface 620 such as a screen on a monitor and keyboard, or other user input / output device. The network 616 comprises some number of local area networks and / or wide area networks. This may include wired and / or wireless communication networks. This network communication technology is well known in the art. The user interface 620 allows supervising or service personnel located remotely to operate the local system 612 and monitor the verification status of the shipping container by the group of sensor units 601, 602 and 603 deployed on the frame structure, such as in the crane arm assembly (or separator bar).
Operating the system remotely, such as from a central monitoring location, a large number of sites can be safely monitored by a limited number of supervisory personnel. In addition to monitoring container handling operations such as from crane arm assemblies, as illustrated in the example of FIG. 1, it should be clear that many different applications can benefit from the shipping container verification function to detect and identify radiation, explosives and special materials. For example, sensor units mounted on the forklift truck communicating with a remote monitoring system allows radiation detection and identification where large quantities of cargo are moved and handled, such as at ports, railroads, and intermodal stations, and on ships , airplanes, trucks, warehouses, and other transportation environments, and in other places that have large quantities of cargo to handle as should be understood by those skilled in the art in view of the present discussion. Note that the 414 sensors can be mounted in many different types of frame structures and related environments. This monitoring capacity, both remote and local monitoring, and with a significantly reduced cost of deployment and run of such a monitoring system, provides a significant commercial advantage. Additionally, the monitoring function of the system can be combined to monitor more than radiation and explosives. Other types of Hazardous elements can be monitored in combination with radiation detection by combining appropriate sensors and sensors for those other types of hazardous elements with the RF sensor and radiation units and monitoring system in accordance with alternative embodiments of the present invention. With reference to FIG. 7, it should be understood that sensor devices such as gamma sensors 202 and neutron sensors 202 as shown in FIG. 2 can be deployed as battery powered devices 700. The power consumption requirements of such sensor devices 700 can be supplied for long periods of time by modern battery technologies and energy conservation techniques. This allows these sensors 700 to be mounted in many different mounting arrangements in relation to different types of frame structures, and without needing to be assigned to a continuous power source. The sensor 702, in accordance with an example illustrated in FIG. 7, may include one or more gamma sensors, neutron sensors, or a combination thereof. The processor 704 stores data signals collected from the sensor 702 in the memory 708. The memory 708 also stores configuration and other parameters and other data and programs used by the processor 704 to perform its functions as a controller processor 704 for the device 704. sensor activated with battery 700. One such function is the communication of data collected from sensor 702 to a data collection system 610 (as shown in FIG 6). The function of communication, in this example, is manipulated via wireless communication such as using RF communication via a wireless communication module 710 and an RF antenna 71 1. A form of wireless communication is over wireless networks using the ad-hoc communication mode where the wireless devices, such as a group of battery activated sensors 700 deployed in various frame structures, communicate directly with each other (in a peer-to-peer communication style) to dynamically establish a network of neighboring wireless devices. Operating in an ad-hoc mode allows all wireless devices within the range of each other to discover and communicate in par-apar style without involving central access points. In one example, each neighboring wireless device in such a network will communicate its collected radiation data with the other neighboring devices which then store all radiation data collected from all neighboring sensor devices 700 in memory 708. In this way, when a data collection system 610 communicates with one of the sensor devices 700 this can interrogate and receive data collected from all neighboring sensor devices 700. This is particularly useful where the sensor devices 700 are deployed in various frame structures which include one or more containers, which are commonly stacked in a container handling environment. This allows, for example, to examine the containers located near the center of a pile which could otherwise be very difficult or impossible to examine without first removing the container of the pile. This allows a shipping port operation, for example, to handle muye containers efficiently while monitoring for possible unauthorized contents in any of the containers. Also, as another example, a monitoring vessel carrying the 610 data collection system and the 612 monitoring and analysis system could travel together with a container loading vessel and the 610 data collection system could interrogate one or more 700 sensors mounted on one or more frame structures on the container ship. The data collection system 610, communicating with one of the sensors 700, could be able to receive the data collected from all the sensors 700 in the ad hoc network. The battery and power conditioning circuits 712 provide power (such as via at least one power bus 714) to all electronics, modules, and devices in the sensor 700. Additionally, the power circuits 712 provide an indicator signal of power 715 to the processor 704. This allows the processor 704 to monitor when the power is good and when the power is getting too low. In the last condition, the processor 704 can send an alarm condition via the wireless communication module 710 to the data collection system 610 and to the information processing system 612. This allows the system to take the appropriate corrective action. For example, the identification of the particular sensor 700 with the low power alarm may indicate to the service personnel to replace the battery (to recharge the battery) on the sensor 700 as soon as possible. Also, the system 712 can disregard detection and detect signals from such a device 700 that has sent an alarm indicating an unreliable power condition. This will help avoid false detection, or failed detection, conditions for sensors 700 that have unreliable power. Battery operated sensor devices 700, such as including neutron and / or gamma sensors, can be mounted in any position in a container (a type of frame structure). For example, one or more devices 700 can be mounted on one or more internal surfaces of a container. A suggested position, in accordance with one embodiment, is on an internal surface of the roof / roof center of the container to allow equal access to monitor all goods and materials in the container. As can be appreciated by those skilled in the art in view of the present discussion, multiple sensors 700 can be used and sensors 700 can be mounted at any position within the container, on the outer side of the container, or any combination thereof. The sensor devices 700, in accordance with one embodiment, are deployed on the outer side of the containers, integrated into (mounted to) the stacking interlock mechanisms commonly found in most shipping containers. These interlock mechanisms are normally found in the corners of a container. There are approximately 16 million containers around the world and stacking interlock mechanisms are commonly in use throughout the world. Incorporating (or mounting) a sensor device 700 into the metal structure of a stacking interblocking mechanism, such as by mounting a sensor device 700 in a cavity in each return latch of the interboxing stacking mechanism of each container, one or more 700 sensors could be used more efficiently to monitor the contents of the containers. The use of these sensor devices 700 in each interboxing mechanism of each container and communicating with each other in an Ad-Hoc network could allow Clients of E.U.A. of the ship to go to the side of a cargo ship, initiate communications with any of the wireless communications modules 710, determine if there is a radiation detection in a particular container, even one that is stored deep in a stack of vessels within the Boarding boat hull. This is a significant advantage of one embodiment of the present invention that has not been available in the past. A radiation reference source may be in the vicinity of one or more sensors 702 on a sensor 700 (also see sensors 202 shown in FIG.2) to facilitate real-time calibration of sensors 702 through communication with the multi-channel analyzer 630. It is known that the radiation sensors 702 have an analogous trend over time. The 640 spectral analysis system typically depends on precise spectral data (within the calibration) from the 700 sensors to identify the specific isotopes that are present in the container under examination. To provide accurate data over time, a small radiological source can be exposed to the radiation sensor 702 during calibration checks. The source of radiation (such as a trace level of a radiological material) can be a source of continuous exposure to the sensor 702, an intermittent (selective) source of exposure (such as in a cup that can be opened or closed to selectively expose the source for calibration), or any combination of one or more sources in the sensor 702, and / or in the sensor 700. A reference signal for the detection of this reference source is analyzed by the multiple channel analyzer system 630 for Ensure that the sensor 702 is in calibration. If the sensor 702 is out of calibration, the multiple channel analyzer system 630 modifies the sensor data received from the particular sensor 700 to carry the sensor data in calibration (sensor calibration) before placing the data within the histogram for analysis Spectral analysis system 640. Preferred embodiments of the present invention can be realized in hardware, software, or a combination of hardware and software. A system of conformance to a preferred embodiment of the present invention can be realized in a centralized style in a computer system, or in a distributed style where different elements are distributed through several interconnected computer systems. Any type of computer system - or other device adapted for carry out the methods described in this document - is appropriate. A typical combination of hardware and software could be a general purpose computer system with a computer program that, when loaded and executed, controls the computer system in such a way that it carries the methods described in this document. An embodiment in accordance with the present invention can also be incorporated into a computer program product, which comprises all the features that allow the implementation of the methods described herein, and which - when loaded into a computer system - is able to carry out these methods. Means of computer program or computer program in the present context means any expression, in any language, code or notation, of a set of instructions that is intended to cause a system having an information processing capability to perform a particular function either directly or after either or both of the following a) conversion to another language, code or, notation; and b) reproduction in a different material form. Each computer system may include one or more computers and at least one computer-readable medium allowing a computer to read data, instructions, messages or message packets, and other computer-readable information from the computer-readable medium. Computer-readable media may include non-volatile memory, such as ROM, Flash memory, Disk drive memory, CD-ROM, and other permanent storage. Additionally, a computer readable medium may include, for example, volatile storage such as RAM, buffers, cache memory, and network circuits. In addition, the computer readable medium may comprise computer-readable information in a transient state medium such as a network link and / or a network interface, including a wired network or a wireless network, which allows a computer to read such information. readable on computer. Although specific embodiments of the invention have been described, those skilled in the art will understand that changes can be made to the specific embodiments without departing from the spirit and scope of the invention. The scope of the invention is not, therefore, restricted to the specific embodiments, and it is intended that the appended claims cover any and all applications, modifications, and embodiments within the scope of the present invention.

Claims (22)

NOVELTY OF THE INVENTION CLAIMS
1. - A radiation identification and detection system, comprising: a frame structure for mounting on, and / or being part of, a container moving device, wherein the container moving device mechanically engages and moves the container, and wherein the frame structure moves with the container; one or more gamma sensors; one or more solid-state neutron sensors, wherein one or more gamma sensors and one or more solid-state neutron sensors are collectively mounted on the frame structure which may be located in the vicinity of the container under examination; a digital data collection system, communicatively coupled with one or more gamma sensors and one or more solid state neutron sensors, to collect radiation data from one or more gamma sensors and one or more solid state neutron sensors; a multiple channel analyzer system, communicatively coupled with the digital data collection system, to prepare histograms of the collected radiation data; a spectral analysis system, communicatively coupled with the multiple channel analyzer system and the digital data collection system, to receive and analyze the collected radiation data and histograms to detect radiation and to identify one or more isotopes associated with
the radiation data collected; a first data storage means for storing data representing isotope spectrum for use by the spectral analysis system, where one or more spectral images stored in the first data storage unit represents each isotope, the first data storage medium coupled communicatively with the spectral analysis system; an information processing system, communicatively coupled with the spectral analysis system, to analyze one or more identified isotopes and to determine the materials or possible goods they represent; and a second data storage means for storing data representing a manifest related to the container under examination, the second data storage means being communicatively coupled with the information processing system, the information processing system additionally for comparing the materials or possible bins determined with the manifest related to the container under examination to determine if there are unauthorized materials or goods contained within the container under examination.
2. The system according to claim 1, further characterized in that: one or more gamma sensors comprise: integrated analog interface and analog to digital converter, sensor resolution of 3.4% or better between 1 kev and 662 kev, and resolution of sensor 12% or better between 662 kev and 3 Mev; and one or more neutron status sensors
Solid include: integrated analog interface and analog to digital converter, and a moderator for thermal neutron detection.
3. - The system according to claim 1, further characterized in that the frame structure is mounted on a separate support structure comprising any of the following: a crane arm assembly, a spacer rod, a stationary support, a Forklift, a boat; an airplane, a truck, a railway wagon, and any combination thereof.
4. - The system according to claim 1, further characterized in that the frame structure is mounted on a separate support structure that is part of a fork lift truck.
5. - The system according to claim 1, further characterized in that the frame structure is mounted on a separate support structure comprising at least one of a railway line, airport, and seaport, crane system.
6. - The system according to claim 1, further characterized in that it comprises: an impact absorber system mechanically coupled to the frame structure to protect one or more gamma sensors and one or more solid state neutron sensors mounted on the structure of frame.
7. - The system according to claim 6, further characterized in that the frame structure is mounted on
a separate support structure and wherein the impact absorbing system protects one or more gamma sensors and one or more solid-state neutron sensors from impact forces of up to 200 G-forces present in the separate support structure every minute for a period of extended time.
8. The system according to claim 1, further characterized in that the frame structure comprises at least one partial housing around one or more gamma sensors and one or more solid-state neutron sensors.
9. The system according to claim 8, further characterized in that at least one partial housing comprises one or more housing walls fixed to the frame structure. 10. - The system according to claim 8, further characterized in that at least one partial housing comprises a complete compartment around one or more gamma sensors and one or more solid-state neutron sensors. 1.
The system according to claim 1, further characterized in that it additionally comprises: an impact absorbing system mechanically coupled with a spacer rod of a gantry crane; and a sensor housing containing one or more gamma sensors and one or more solid-state neutron sensors and being mounted on the separator bar via the impact absorber system to protect one or more gamma sensors and one or more sensors
Neutron solid-state forces of up to 2000 G-forces present in the separator bar every minute for an extended period of time.
12. The system according to claim 1, further characterized in that it additionally comprises: a housing for containing one or more gamma sensors, the housing being constructed strong to support the environment in a separator bar of a gantry crane, and the accommodation providing minimal reduction of gamma radiation by passing through the housing to the surfaces of each of the one or more gamma sensors.
13. The system according to claim 1, further characterized by comprising: a housing for containing one or more gamma sensors, the housing being constructed of material comprising one or more strong metals to withstand a rough environment in a separating bar of a gantry crane, the housing has at least one housing wall that is ground to a thin layer at each position of one or more gamma sensors to minimize gamma radiation shielding by the housing to detect gamma radiation at any of the sensor surfaces individual gamma.
14. The system according to claim 1, further characterized in that it additionally comprises: a housing for containing one or more gamma sensors, the housing being constructed of metal comprising beryllium to support a rough environment in a separating bar of a crane. gantry while minimizing particle shielding
gamma that pass through the housing to detect the gamma particles on any of the individual gamma sensor surfaces.
15. - The system according to claim 1, further characterized in that it additionally comprises: at least one sensor mounted with shock absorption including one or more analog gamma sensors with shielded analog cable to reduce background noise in the output signals from one or more sensors and to reduce mechanical shock impact on one or more sensors.
16. - The system according to claim 1, further characterized in that it additionally comprises: a wired or wireless line communications system for transporting the radiation data collected by one or more gamma sensors and one or more solid state neutron sensors towards the spectral analysis system.
17. - The system according to claim 1, further characterized in that the sensors, the digital data collection system, and the spectral analysis system, are integrated on a separating bar of a gantry crane.
18. - The system according to claim 1, further characterized in that one or more gamma sensors include one or more respective gamma sensors, and wherein one or more gamma sensors are continuously exposed or selectively exposed to a trace level of radiological material to provide an associated reference signal
with one or more gamma sensors for sensor calibration of one or more gamma sensors.
19. - The system according to claim 18, further characterized in that the multiple channel analyzer system uses the reference signal associated with one or more gamma sensors to adjust the radiation data collected from one or more gamma sensors to obtain the calibration appropriate of the radiation data collected.
20. - The system according to claim 1, further characterized in that the spectral analysis system analyzes the radiation data collected to identify one or more isotopes associated with the radiation data collected by: comparing one or more spectral images of the data from radiation collected with one or more spectral images stored in the first data storage means, each known isotope is related to spectral images stored in the first data storage medium, and wherein one or more stored spectral images associated with known isotopes represent one or more levels of spectral radiation data that can be collected from one more sensors when the known isotope is detected.
21. The radiation identification and detection system according to claim 1, further characterized in that the container displacement device is a separating rod of a gantry crane.
22. - The radiation identification and detection system according to claim 1, further characterized in that the container displacement device is at least one truck, a forklift, and a crane and truck assembly. 23.- A system for the identification and detection of special material and explosives, comprising: one or more RF signal generators, mounted on a separating bar of a gantry crane, which transmits RF signals through electrical contacts between the separator bar and a shipping container under examination and then inside a cavity of the shipping container under examination; one or more RF receivers for coupling one or more RF antenna systems to receive return signals from within the cavity of the shipping container under examination, one or more RF antenna systems receiving return signals from within the cavity of the receiving vessel. shipment under examination through electrical contacts between the shipping container under examination and the separator bar; a data collection system communicatively coupled with one or more RF receivers, to collect the return signals received from one or more RF receivers; an information processing and spectral analysis system communicatively coupled with the data collection system, to analyze the received return signals collected to detect materials in the shipping container cavity under examination, and to identify possible explosives and / or special materials there; and data storage means for storing data representing a manifest related to the container of
shipment under examination, the data storage medium communicatively coupled with the information processing and spectral analysis system, the information processing and spectral analysis system in addition to compare the special materials and / or possible explosives identified with the manifesto related to the shipping container under examination to determine if there are unauthorized explosives and / or special materials contained within the shipping container under examination. 24. - The system according to claim 23, further characterized in that it additionally comprises: a user interface, communicatively coupled to the information processing and spectral analysis system, to present the user with at least one of a representation of the signals return received, special materials and / or possible explosives identified in the shipping container under examination, and special materials and / or non-authorized explosives identified by the system contained within the shipping container under examination. 25. - The system according to claim 23, further characterized in that the special materials include highly enriched uranium. 26.- The system according to claim 23, further characterized in that the information processing and spectral analysis system compares the special materials and / or possible explosives identified with the manifesto by converting the manifesto related to the
shipping container under examination for expected radiological and / or explosive materials and then compare the special materials and / or possible explosives identified with the expected radiological and / or explosive materials.
MXMX/A/2008/007094A 2005-12-01 2008-05-30 Container verification system for non-invasive detection of contents MX2008007094A (en)

Applications Claiming Priority (6)

Application Number Priority Date Filing Date Title
US11291574 2005-12-01
US60/759,375 2006-01-17
US60/759,332 2006-01-17
US60/759,373 2006-01-17
US60/759,331 2006-01-17
US11363594 2006-02-27

Publications (1)

Publication Number Publication Date
MX2008007094A true MX2008007094A (en) 2008-10-03

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