Using Neutron Generator with APT/NNA for Detection of Explosives

Similar documents
Detection of Explosives and Other Illicit Materials by Nanosecond Neutron Analysis

Concept of a Combined Device for Localization and Identification of Explosives

Plasma Accelerator for Detection of Hidden Objects by Using Nanosecond Impulse Neutron Inspection System (NINIS)

NEUTRON GENERATORS AND DAQ SYSTEMS FOR TAGGED NEUTRON TECHNOLOGY

Simulation of nonorganic scintillation detector response for the problems of active interrogation by tagged neutron technology

Principles and Applications of Neutron Based Inspection Techniques. Tsahi Gozani Rapiscan Laboratories 520Almanor Ave, Sunnyvale, CA

Powerful Nanosecond Single- Shot Technique for Detection of Illicit Materials and Explosives

Plasma Accelerator for Detection of Hidden Objects by Using Nanosecond Impulse Neutron Inspection System (NINIS)

The Use of Neutron Generators for the Detection of Illicit Materials in the Sea Transportation System

The Use of Neutron Generators for the Detection of Hidden Explosives and Illicit Materials. Giancarlo Nebbia

Neutron and Gamma Ray Imaging for Nuclear Materials Identification

n+a n +A *, A * γ+a, (2)

Neutronics Experiments for ITER at JAERI/FNS

Detection of explosives and fissile material based on neutron generators, survey of techniques and methods. M. Bruggeman

Neutron TOF spectroscopy in a single-shot nanosecond neutron pulsed technique for a disclosure of hidden explosives and fissile materials

This paper should be understood as an extended version of a talk given at the

INSTRUMENTAL TECHNIQUE FOR THE DETECTION AND IDENTIFICATION OF RADIOACTIVE, FISSILE AND EXTRA HAZARDOUS SUBSTANCES

Status Report on the detection of illicit materials in cargo containers by using neutron beams.

Higher -o-o-o- Past Paper questions o-o-o- 3.6 Radiation

SCANNING OF CARGO CONTAINERS BY GAMMA-RAY AND FAST NEUTRON RADIOGRAPHY

Physics Dept. PHY-503-SEMESTER 112 PROJECT. Measurement of Carbon Concentration in Bulk Hydrocarbon Samples

MCNP Simulations of Fast Neutron Scattering by Various Elements and their Compounds in View of Elaboration of a Single Shot Inspection System

Using Fast Neutrons to Detect Explosives and Illicit Materials

Portable neutron generators of VNIIA and their applications

Joint Institute for Nuclear Research. Flerov Laboratory of Nuclear Reactions. University Center LABORATORY WORK

AUTOMATED TEMPLATE MATCHING METHOD FOR NMIS AT THE Y-12 NATIONAL SECURITY COMPLEX

CALIBRATION OF SCINTILLATION DETECTORS USING A DT GENERATOR Jarrod D. Edwards, Sara A. Pozzi, and John T. Mihalczo

Design of an Integrated Inspection System For Detection of Explosive and Illicit Materials

POSITION SENSITIVE DETECTION OF CONCEALED SUBSTANCES EMPLOYING PULSED SLOW NEUTRONS

Shielded Scintillator for Neutron Characterization

The Neutronic Check Point: fast neutron transmission measurements to detect explosives in vehicles.

Background Reduction Using Collimators on a Portable HPGe Nuclide Identifier

A POSITION SENSITIVE ALPHA PARTICLE DETECTOR BASED ON A LYSO CRYSTAL AND A MICRO-PIXEL AVALANCHE PHOTODIODE

NGN PhD Studentship Proposal

Alpha-Energies of different sources with Multi Channel Analyzer

PINS Measurements of Explosive Simulants for Cargo Screening

WM2013 Conference, February 24 28, 2013, Phoenix, Arizona, USA

(PHENS) for Active Diagnostics of Radiation Environment in Spacecraft

Alpha particle scintillation detector based on micro pixel avalanche photodiode and LYSO crystal

Survey Meter OD-01 Address: Phone: Fax: URL:

Advances on the Development of the Detection System of the C-BORD's Rapidly Relocatable Tagged Neutron Inspection System

Special Nuclear Material Detection Studies With The SMANDRA Mobile System

The EURITRACK Project: Status of a Tagged Neutron Inspection System for Cargo Containers

New perspectives in X-ray detection of concealed illicit materials brought by CdTe/CdZnTe spectrometric detectors

Neutron Transport Calculations Using Monte-Carlo Methods. Sean Lourette Fairport High School Advisor: Christian Stoeckl

CRaTER Pre-Environmental Review (I-PER) Science Requirements Update

Determination of the boron content in polyethylene samples using the reactor Orphée

WM2014 Conference, March 2 6, 2014, Phoenix, Arizona, USA

Neutron Based Techniques for the Detection of Illicit Materials and Explosives

A Proposal of Nuclear Materials Detection and Inspection Systems in Heavily Shielded Suspicious Objects by Non-destructive Manner.

FRAM V5.2. Plutonium and Uranium Isotopic Analysis Software

DEVELOPMENT OF ADVANCED NEUTRON INDUCED PROMPT GAMMA- RAY ANALYSIS SYSTEM FOR SURVEY OF ANTI-PERSONNEL MINES

Active Interrogation of SNMs by use of IEC Fusion Neutron Source

NSD GRADEL FUSION NEUTRON GENERATORS

1 of :32

DIGITAL PULSE SHAPE ANALYSIS WITH PHOSWICH DETECTORS TO SIMPLIFY COINCIDENCE MEASUREMENTS OF RADIOACTIVE XENON

NEUTRON RADIOGRAPHY OF CARGO CONTAINERS USING 2.5 MEV TAGGED NEUTRONS

Measurements of the gamma-quanta angular distributions emitted from neutron inelastic scattering on 28 Si

International Journal of Scientific & Engineering Research, Volume 5, Issue 3, March-2014 ISSN

Reactor On/Off Monitoring with a Prototype of Plastic Anti-neutrino Detector Array (PANDA)

IdentiFINDER Digital Hand Held Spectrometer & Dose Rate Meter for Portable Applications

Department of Chemistry, University of Rochester, Rochester, N.Y POC:

New irradiation zones at the CERN-PS

1 Gamma-Ray Burst Polarimeter GAP aboard

ON THE OMNIPRESENT BACKGROUND GAMMA RADIATION OF THE CONTINUOUS SPECTRUM

TIIVISTELMÄRAPORTTI (SUMMARY REPORT)

ɣ-radiochromatography

Application of Nuclear Quadrupole Resonance to Detection of Explosives and Research Activities at CIAE

Digital simulation of neutron and gamma measurement devices

International Journal of Scientific & Engineering Research, Volume 5, Issue 3, March-2014 ISSN

Verification of fissile materials

Radionuclide Imaging MII Positron Emission Tomography (PET)

TIIVISTELMÄRAPORTTI (SUMMARY REPORT)

Comments on the possible observation of d-d fusion in sonoluminescence (Reference-31 in Taleyarkhan et al. [2002] 1 )

Water Cherenkov Detector installation by the Vertical Muon Equivalent technique

TECHNICAL WORKING GROUP ITWG GUIDELINE ON IN-FIELD APPLICATIONS OF HIGH- RESOLUTION GAMMA SPECTROMETRY FOR ANALYSIS OF SPECIAL NUCLEAR MATERIAL

Compton suppression spectrometry

(Tandem Collimators for the Tangential GammaRay Spectrometer - KM6T-TC)

EXPERIMENTAL STUDY OF NEUTRON FIELDS PRODUCED IN PROTON REACTIONS WITH HEAVY TARGETS. Nuclear Physics Institute AS CR, Rez Czech Republic

Design and production of Scintillation Detectors

Systems for Detection of Threat Materials

Office of Nonproliferation and Verification Research and Development University and Industry Technical Interchange (UITI2011) Review Meeting

Explosives Detection and Identification by PGNAA

NDT as a tool, for Post-Irradiation Examination.

Fast Neutron and Gamma-Ray Detectors for the CSIRO Air Cargo Scanner

Single Channel Beta-Gamma Coincidence Detection of Radioactive Xenon Using Digital Pulse Shape Analysis of Phoswich Detector Signals

Introduction to Environmental Measurement Techniques Radioactivity. Dana Pittauer 1of 48

An Optimized Gamma-ray Densitometry Tool for Oil Products Determination

Alpha-energies of different sources with Multi Channel Analyzer (Item No.: P )

Characterization and Monte Carlo simulations for a CLYC detector

Analyzing Radiation. Pre-Lab Exercise Type of Radiation Alpha Particle Beta Particle Gamma Ray. Mass (amu) 4 1/2000 0

Distillation purification and radon assay of liquid xenon

EFFICIENCY SIMULATION OF A HPGE DETECTOR FOR THE ENVIRONMENTAL RADIOACTIVITY LABORATORY/CDTN USING A MCNP-GAMMAVISION METHOD

Scintillation Detector

Collimated LaBr 3 detector response function in radioactivity analysis of nuclear waste drums

Measurements of Neutron Total and Capture Cross Sections at the TOF spectrometers of the Moscow Meson Factory

THE INSTALLATION FOR EXPERIMENTAL NEUTRON SPECTRA RESEARCH IN REACTOR MATERIALS COMPOSITIONS Hliustin D.V. Institute for Nuclear Research, Moscow,

VERIFICATION OF MONTE CARLO CALCULATIONS OF THE NEUTRON FLUX IN THE CAROUSEL CHANNELS OF THE TRIGA MARK II REACTOR, LJUBLJANA

Design, Construction, Operation, and Simulation of a Radioactivity Assay Chamber

Transcription:

Using Neutron Generator with APT/NNA for Detection of Explosives A.V. Kuznetsov, A.V. Evsenin, I.Yu. Gorshkov, O.I. Osetrov, D.N. Vakhtin V.G. Khlopin Radium Institute, Saint-Petersburg, Russia Email contact of main author: apl@atom.nw.ru Abstract. Nanosecond Neutron Analysis (NNA) method with spatial selection of secondary gamma-radiation, proposed at V. G. Khlopin Radium Institute as a further development of the well-known Associated Particle Technique (APT), allows one to substantially (by two orders of magnitude) reduce the level of the background radiation, making possible creation of devices for detection of small amounts of hazardous materials. A prototype APT/NNA device is based on a DT neutron generator with built-in nine-segment semiconductor detector of accompanying alpha-particles. The prototype is the basis for further development of the NNA method in order to create devices for detection of explosives and other hazardous materials in luggage, sea cargo containers, etc. A concept of a device for detection of hazardous materials in sea cargo containers 3D NNA Scanner has been developed. Results of numerical modeling suggest, that the device will be capable of detecting 30 kg of explosives hidden anywhere inside a 40-feet cargo container within a 12 minute-long inspection cycle. 1. Introduction The main problem encountered in the non-destructive analysis of materials by neutron methods is a very high counting rate in the secondary radiation detection channels, caused by interaction of probing neutrons with the materials of the neutron source, the inspected object, and the materials of the environment. The resulting very high level of background has until recently ruled out a wide use of neutron-based methods for detection of small amounts of hazardous materials hidden among other objects in passenger luggage, cargo containers, etc. The Nanosecond Neutron Analysis (NNA) method with spatial selection of secondary gammaradiation, proposed at V. G. Khlopin Radium Institute as a further development of the wellknown Associated Particle Technique (APT) [1], allows one to substantially (by two orders of magnitude) reduce the level of the background radiation, making possible creation of prototype devices for detection of small amounts of hazardous materials [2, 3]. The method is based on irradiation of the inspected object or volume with fast neutrons and detection of characteristic prompt gamma-rays from inelastic neutron scattering reactions. The background suppression is achieved by equipping a deuteron-tritium (DT) neutron generator with a built-in position-sensitive detector of alpha-particles, which accompany neutron emission, and detecting characteristic gamma-rays within a narrow time interval, counted from the moment of detection of each alpha-particle. Only those gamma-rays that are produced in reactions of 14 MeV neutrons in the area of interest are accepted by the data acquisition system (they coincide with alpha-particles), while those produced in the surrounding material (or of cosmic origin etc.) are suppressed (they do not coincide with alpha-particles). Each of the nine pixels of the alpha-particle detector corresponds to reactions of 14 MeV neutrons in a separate region of space ( in-plane position resolution). A 3 3 matrix of 1 cm 2 alpha-detectors corresponds to nine 8 8 cm 2 areas at 50 cm from the target of the neutron generator (NG).

Time of arrival of each gamma-quantum relative to the corresponding alpha-particle (which accompanied the 14 MeV neutron that produced this gamma-quantum) allows one to distinguish between objects located at different distances from the target of the neutron generator ( in-depth resolution). Every 1 ns time-of-flight of the 14 MeV neutron means, that it reacts at ~5 cm further from the NG target. Thus, in-plane position resolution due to pixelization of the alpha-detector is complemented by in-depth resolution due to time-offlight measurement. 2. Prototype NNA/APT Device A prototype APT/NNA device (FIG. 1) is based on a DT neutron generator with built-in ninesegment semiconductor detector of accompanying alpha-particles. The neutron generator NG27 was produced at the All-Russian Research Institute of Automatics, Moscow 1. It produces up to 5 10 7 14 MeV neutrons per second (into 4π). The nine-segment detector of accompanying alpha-particles was produced by APSTEC Ltd., St.-Petersburg 2. It is a 3 3 matrix of 1 cm 2 semiconductor detectors equipped with the appropriate electronics, which determines the detection time of each alpha-particle and the number of the hit segment. The geometrical efficiency of the alpha-detector is about 2%, and its intrinsic efficiency to 3 MeV alpha-particles is close to 100%. FIG. 1. Prototype device based on neutron generator with built-in nine-segment associated particle detector and BGO-based gamma-ray detector (in front), and portable digital electronics (behind). 1 www.vniia.ru 2 www.apstec.ru 2

The current version of the prototype includes one or two gamma-detectors based on 2.5 2.5 BGO crystal and Hamamatsu R6233-01 photo multiplier. The prototype is serviced by a custom-made electronics, which includes the following components (see FIG. 1): Alpha-detection module, which can handle count rates up to 10 7 α/s with dead time depending only on signal s length. Gamma-detection module, which can handle count rates up to 10 6 γ/s per second from a BGO-based gamma-ray detector. PC-controlled HV power supplies for photo multipliers used in gamma-ray detectors and for the position-sensitive associated particle detector. Single-board PC. Data transfer interface module. System indicator module. All parameters of the device can be controlled remotely, using a standard RF network connection. The data acquisition system is based on fast flash-adcs, programmable logic devices (PLD) and digital signal processors (DSP), which perform on-line correlation analysis of signals from BGO-based gamma-detectors and from the nine-segment alpha-detector. This approach allows one to preserve good energy- and time-resolution at very high counting rates: more than 10 6 α/s and more than 10 5 γ/s. Time resolution of the alpha-detector gamma-detector pair is FWHM = 1.7 ns (for 4.43 MeV 12 C line), which corresponds to about 8 cm in-depth position resolution. 3. Experimental Results with Prototype Device Experiments were carried out with specially prepared imitators of different explosives and some non-explosive materials. These imitators correctly reproduced relative concentrations of carbon, nitrogen and oxygen in the following explosives: RDX, TNT, C4, nitroglycerine, and PETN. Other samples of non-explosive materials were sugar (the same C/O ratio as in TNT) and melamine (a very nitrogen-rich substance). Mass of each imitator was 300 g, and they were sealed inside 24 g aluminum cans. For each detected gamma-quantum the following information is stored: its energy; its time-of-flight relative to the associated alpha-particle; number of the hit segment of the nine-segment alpha-detector. This information is enough to construct a separate energy spectrum for each 3D voxel of the sensitivity zone of the device with resolution about 8 8 8 cm 3. Example of energy spectra measured in 120 seconds for RDX imitator and sugar are shown at FIG. 2. The counting rate of gamma-rays from 300g imitators that are accepted by the data acquisition system was about 6 s -1 (in the energy range from 2 MeV to 8 MeV). The corresponding counting rate of the background was about 5 s -1. 3

Counts per 100keV 60 40 20 NG intensity: 1.5x10 7 n/s Measurement time: 2 minutes, two BGO detectors spectrum from 300g RDX imitator + background spectrum from 300g sugar + background spectrum of background (without imitator) C: 4.43MeV N: 5.1MeV O: 6.1MeV 2 3 4 5 6 7 E γ [MeV] FIG. 2. Example of spectra measured for 300g RDX and sugar imitators, and spectrum of the background (without samples in the sensitive area). Since the distance from the inspected object to the NG target is generally not known (e. g. when one is inspecting the content of a closed container), the experimental data are automatically scanned by the data analysis software along the time ( in-depth distance) coordinate in order to determine, whether any of the nine in-plane areas contain candidates for the explosive substance. For example, spectra on FIG. 2. are shown for the in-plane area #9 (corresponding to one of the nine segments of the alpha-detector) for distances (40 50) cm from the NG target. In two cases (lines with symbols) these voxels contained at least part of the 300g samples, while in one case (line) it contained only air. The remaining background (line) comes mostly from accidental coincidences between alpha-particles and gamma-rays. If no NNA/APT were used, this background spectrum would be a factor of 100 higher than on the above figure. Energy spectra from each voxel are analyzed by a combination of non-linear regression method (using response functions to individual chemical elements calculated by MCNP5 3 code), principal component analysis (using calculated responses to different known explosives), and possibly other methods like partial least squares. As a result, one gets a number of characteristics, such as relative concentrations of different chemical elements in different voxels, proximity of the experimental gamma-spectrum to those of individual explosives, etc. These results are then analyzed by a fuzzy logic engine, which makes the decision about the nature of the investigated object. If the collected statistics is not enough to make a definite decision, the fuzzy logic engine automatically starts additional measurements. 3 MCNP A General Monte Carlo N-Particle Transport Code, Los Alamos National Laboratory. 4

Measurements with 300 g imitators located at 45 cm from the NG target with 1.5 10 7 n/s neutron flux yielded typical measurement times about 30-40 seconds, within which the device was able to correctly identify the imitator as either an explosive or a non-explosive. For 1 kg of explosives the detection time would be less than 10 seconds. Further shortening of the detection time is possible, if one increases the neutron flux from the NG (the present version allows up to 5 10 7 n/s without severe degradation of the target), and increases the number of gamma-ray detectors (present version of portable fast digital data acquisition electronics allows expansion up to 12 gamma-detectors without any changes). Characteristics of the existing prototype are listed in Table I. TABLE I: CHARACTERISTICS OF THE EXISTING PROTOTYPE APT/NNA DEVICE. Explosives detection limit 100 g in tens of seconds Detection method Nanosecond neutron analysis (NNA) with spatial resolution (APT technology) Decision-taking algorithm Automatic Simultaneously inspected area 30 30 30 cm 3 Spatial resolution 7-8 cm in-plane, 8-10 cm in-depth Total mass of the device not more than 20 kg Dimensions 70 45 20 cm 3 Radiation safety Safe when switched-off 3. 3D NNA Scanner for Cargo Container Inspection The described prototype is the basis for further development of the NNA method in order to create devices for detection of explosives and other hazardous materials in luggage, sea cargo containers, etc. These devices will be based on universal module ( NNA/APT basic module ) consisting of an APT neutron generator and 12 gamma-ray detectors (see left side of FIG. 3). Each NNA/APT basic module will be able to simultaneously inspect about 1 m 3 volume with spatial resolution needed for the given application. Depending on the geometry of the inspected object several NNA/APT basic modules can be combined to ensure the required inspection time. Alternatively, large objects can be scanned by a single NNA/APT basic module installed on a movable support. Experiments with the existing prototype and MCNP calculations show, that in case of the inspection of a large transport container with six NNA/APT basic modules (see right part of FIG. 3) within about 10 minutes the device will be able to detect about 10 kg of explosives hidden anywhere inside the container filled by 30% with organic (non-explosive) material. If the explosive is located close to the wall of the container, the detection limit drops to about 2 kg. The inspection device can be optionally equipped with neutron detectors, which would allow simultaneous detection of shielded and unshielded fissioning materials by induced neutron emission. 5

FIG. 3. Left: one NNA/APT basic module consisting of one APT neutron generator and 12 gammaray detectors. Right: 3D NNA Scanner for Inspection of Sea Containers. 1 NNA/APT basic modules. 2 neutron detectors. 3 volume inside the 40'-high sea container screened by one measurement module. 4 construction frame. 5 remote control and data analysis module In order to estimate the parameters of the NNA/APT device for inspection of containers and to check the results of MCNP calculations, measurements with the existing prototype were carried out. The experimental setup simulated explosives inside a metallic container filled with organic materials. The prototype device was located outside the metallic wall, simulating the wall of the container (see left part of FIG. 4). FIG. 4. Measurements with 700g melamine sample. imitating explosive inside a container. The prototype device (left) was outside the metallic wall, and the 700g melamine sample (right) was placed at about 1 meter from the NG target behind a bag filled with organic materials. A plastic bag with 700g of melamine (67% nitrogen, 33% carbon, white plastic bag in the right part of FIG. 4) was placed at ~1 meter from the target of the neutron generator (45 cm from the BGO gamma-ray detector) behind a bag filled with organic materials. Among these materials were wool, cotton, books, soap, electric appliances, melamine, etc. In order to see the effect from the sample, two measurements were carried out: with and without melamine. Each measurement lasted 5 minutes at NG intensity 1.5 10 7 n/s. The results 6

were analyzed by non-liner regression procedure, and concentrations of carbon, nitrogen, oxygen, and other elements were simultaneously obtained for spectra, measured in coincidence with each of the nine segments of the associated particles detector at different distances from the NG target. 300 Segment #9 With melamine: Without melamine: C N O Concentration [arb. units] 250 200 150 100 Bag filled with organic material (wool, cotton, books, soap, etc.) 700g of melamine 50 0 0 10 20 30 40 50 60 "In-depth" coordinate [cm] 300 Segment #2 C N O 250 Concentration [arb. units] 200 150 100 Bag filled with organic material (wool, cotton, books, soap, etc.) small bag with clothes and water 50 0 0 10 20 30 40 50 60 "In-depth" coordinate [cm] FIG. 5. Distribution of C, N and O along in-depth coordinates (counted from the front plane of the BGO detector) in Segments #9 and #2. Results were corrected for the distance from NG target to the given coordinate. Experiment was carried out in the geometry shown at FIG. 4. 7

FIG. 5 shows examples of distributions of concentrations of C, N and O for alpha-detector segment #9 (which corresponded to the direction towards the melamine sample), and segment #2 (which corresponded to neutron flight path through two bags on FIG. 4). Results were smoothed and corrected for the difference in distances to NG target and BGO detector for different locations along the in-depth axis, so the presented concentrations directly correspond to the mass of the material at the given location. The effect from melamine sample can be clearly seen on the top figure (Segment #9) between 40 cm and 50 cm. The variety of C/N/O relations on the bottom figure (Segment #2) reflects the complexity of the filling of the two bags. 4. Conclusions Prototype device for detection of explosives, based on Nanosecond Neutron Analysis and Associated Particles Technique (NNA/APT), was shown to be able to detect several hundred grams of concealed explosives within tens of seconds at distances about 50 cm and within several minutes at distances around 1 meter from the NG target. The fast digital electronics, which is servicing the device, is capable of handling extremely high gamma-ray and alpha-particle counting rates, which allows up-scaling the existing prototype to include up to 12 gamma-ray detector and neutron generator with intensity up to 10 8 n/s without significant changes. Work is under way to create a full-scale prototype NNA/APT basic module, which can serve as a component for large-scale devices for inspection of cargo containers and luggage. Acknowledgements This work was supported in part by the US Civilian Research and Development Foundation (CRDF) grant #RP2-564-ST-03, and in part by International Atomic Energy Agency (IAEA) Contract #12600. References [1] BRUSCHINI C., Commercial System for Direct Detection of Explosives (for Explosive Ordnance Disposal Tasks), École Polytechnique Fédérale de Lausanne (EPFL) & Vrije Universiteit Brussel (VUB), (2001). [2] EVSENIN, A.V. et al., Detection of hidden explosives by nanosecond neutron analysis technique. // H.Schubert, A.Kuznetsov (eds.), Proc. of the NATO ARW #979920 Detection of bulk explosives: advanced techniques against terrorism, St.-Petersburg, Russia, 16 21 June 2003. Kluwer Academic Publishers, (2004) 89-103. [3] KUZNETSOV, A.V. et al., Detection of buried explosives using portable neutron sources with nanosecond timing. Applied Radiation and Isotopes, Vol. 61, Issue 1, (2004) 51-57. 8