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Radiation detection is necessary for isotope identification and assay in nuclear forensic applications. The principles of operation of gas proportional counters, scintillation counters, germanium and silicon semiconductor counters will be presented. Methods for calibration and potential pitfalls in isotope quantification will be described.
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With the largest band gap energy of all commercial semiconductors, GaN has found wide application in the making of optoelectronic devices. It has also been used for photodetection such as solar blind imaging as well as ultraviolet and even X-ray detection. Unsurprisingly, the appreciable advantages of GaN over Si, amorphous silicon (a-Si:H), SiC, amorphous SiC (a-SiC), and GaAs, particularly for its radiation hardness, have drawn prompt attention from the physics, astronomy, and nuclear science and engineering communities alike, where semiconductors have traditionally been used for nuclear particle detection. Several investigations have established the usefulness of GaN for alpha detection, suggesting that when properly doped or coated with neutron sensitive materials, GaN could be turned into a neutron detection device. Work in this area is still early in its development, but GaN-based devices have already been shown to detect alpha particles, ultraviolet light, X-rays, electrons, and neutrons. Furthermore, the nuclear reaction presented by {sup 14}N(n,p){sup 14}C and various other threshold reactions indicates that GaN is intrinsically sensitive to neutrons. This review summarizes the state-of-the-art development of GaN detectors for detecting directly and indirectly ionizing radiation. Particular emphasis is given to GaN's radiation hardness under high-radiation fields.
Thousands of radiation detection systems have been deployed over the last decade to domestic and international locations, primarily at ports of entry or departure. An essential ingredient in supporting sensor deployment is the capability to develop and test emerging systems and replicate the behavior of deployed systems. Pacific Northwest National Laboratory recently designed and constructed a laboratory for developing and testing these large-scale radiation detection systems. The Large Detector Laboratory is capable of housing up to 30 fully integrated radiation portal monitoring systems and allows for complex testing scenarios that include background suppression, equipment shielding, and source cross talk between systems. The laboratory design also allows implementation of applications ranging from pedestrian screening to baggage or package inspection to vehicle and cargo inspection to standoff detection. This manuscript describes the unique attributes of this laboratory that includes reproducing operational conditions faced by integrated systems, realistic source configurations and measurements across multiple systems.
We investigated cadmium telluride selenide (CdTeSe) crystals, newly grown by the Traveling Heater Method (THM), for the presence and abundance of point defects. Deep Level Transient spectroscopy (I-DLTS) was used to determine the energies of the traps, their capture cross sections, and densities. The bias across the detectors was varied from (1–30) V. Four types of point defects were identified, ranging from 10 meV to 0.35 eV. Two dominant traps at energies of 0.18 eV and 0.14 eV were studied in depth. Cd vacancies are found at lower concentrations than other point defects present in the material.
A radiation detector includes a photodetector and a scintillator coupled thereto. The scintillator is formed of a scintillator material comprising an organic glass scintillator (OGS) material and at least one of a polymer additive or a plasticizer additive. The scintillator emits light when radiation is received at the scintillator, and the light is received by the photodetector. The radiation detector can further include a frame that has an interior cavity that holds the scintillator in position with respect to the photodetector, such that the light emitted by the scintillator is transmitted to the photodetector. The scintillator can be formed by casting amorphous scintillator material in the interior cavity of the frame. The frame can then be coupled to the photodetector to form the radiation detector.
A radiation detector includes a photodetector and a scintillator coupled thereto. The scintillator is formed of a scintillator material comprising an organic glass scintillator (OGS) material and at least one of a polymer additive or a plasticizer additive. The scintillator emits light when radiation is received at the scintillator, and the light is received by the photodetector. The radiation detector can further include a frame that has an interior cavity that holds the scintillator in position with respect to the photodetector, such that the light emitted by the scintillator is transmitted to the photodetector. The scintillator can be formed by casting amorphous scintillator material in the interior cavity of the frame. The frame can then be coupled to the photodetector to form the radiation detector.
A networked gamma radiation detection system with directional sensitivity and energy spectral data acquisition capability is being developed by the National Security Technologies, LLC, to support the close and intense tactical engagement of law enforcement who carry out counterterrorism missions. In the proposed design, three clusters of 2' × 4' × 16' sodium iodide crystals (4 each) with digiBASE-E (for list mode data collection) would be placed on the passenger side of a minivan. To enhance localization and facilitate rapid identification of isotopes, advanced smart realtime localization and radioisotope identification algorithms like WAVRAD (wavelet-assisted variance reduction for anomaly detection) and NSCRAD (nuisance-rejection spectral comparison ratio anomaly detection) will be incorporated. We are testing a collection of algorithms and analysis on the problem of radiation detection with a distributed sensor network, examining such a network’s associated characteristics, and also the trade-offs between false positive alarm rates, true positive alarm rates, and time to detect multiple radiation sources in a large area. Empirical and simulation analyses of critical system parameters, such as number of sensors, sensor placement, and sensor response functions, are being examined. This networked system will provide an integrated radiation detection architecture and framework with (i) a large nationally recognized search database equivalent that would help generate a common operational picture in a major radiological crisis; (ii) a robust reach back connectivity for search data to be evaluated by home teams; and, finally, (iii) a possibility of integrating search data from multi-agency responders.
Tensioned metastable fluid detectors are disclosed that minimize false positive detection events. The methods involve the use of new fluids that provide improved neutron-alpha fission detection at reduced tension states. The rate of spin is also increased using a new protocol that avoids the creation of liquid imbalances in the arms of a CTMFD (centrifugally tensioned metastable fluid detector). The disclosed CTMFD radiation detection system includes a detector assembly containing a detection fluid, a base, a safety enclosure, a motor and motor mounting bracket, speed sensors, a cooling system that includes an air inlet and outlet and a safety enclosure. The CTMFD radiation detection system can include a plurality of independent detector arms having fluids with distinct Pneg requirements such that the range of detectable radiation is increased. Also disclosed are methods for detecting radiation using the disclosed CTMFD radiation detection system. Motor speed calibration procedures are also disclosed.
A standoff alpha radiation detection technique based on the physical mechanism of excited state absorption of air molecules was explored and is presented in this paper. Instead of directly detecting the radiation via measuring the intensity of radiation induced air fluorescence, the radiation is detected via the excited state absorption of alpha radiation excited/ionized air molecules. Both theoretical analyses and experimental verifications were conducted. The experimental results confirmed that the radiation could be detected via excited state absorption of radiation excited/ionized air molecules at a 10 m standoff distance, which was consistent with the theoretical analyses.
Modeling forms an important component of radiation detection development, allowing for testing of new detector designs, evaluation of existing equipment against a wide variety of potential threat sources, and assessing operation performance of radiation detection systems. This can, however, result in large and complex scenarios which are time consuming to model. A variety of approaches to radiation transport modeling exist with complementary strengths and weaknesses for different problems. This variety of approaches, and the development of promising new tools (such as ORNL’s ADVANTG) which combine benefits of multiple approaches, illustrates the need for a means of evaluating or comparing different techniques for radiation detection problems. This report presents a set of 9 benchmark problems for comparing different types of radiation transport calculations, identifying appropriate tools for classes of problems, and testing and guiding the development of new methods. The benchmarks were drawn primarily from existing or previous calculations with a preference for scenarios which include experimental data, or otherwise have results with a high level of confidence, are non-sensitive, and represent problem sets of interest to NA-22. From a technical perspective, the benchmarks were chosen to span a range of difficulty and to include gamma transport, neutron transport, or both and represent different important physical processes and a range of sensitivity to angular or energy fidelity. Following benchmark identification, existing information about geometry, measurements, and previous calculations were assembled. Monte Carlo results (MCNP decks) were reviewed or created and re-run in order to attain accurate computational times and to verify agreement with experimental data, when present. Benchmark information was then conveyed to ORNL in order to guide testing and development of hybrid calculations. The results of those ADVANTG calculations were then sent to PNNL for compilation. This is a report describing the details of the selected Benchmarks and results from various transport codes.
This report presents a series of recommendations for data to train and evaluate radiation detection algorithms and performance metrics to evaluate these algorithms. These recommendations were formed through a community consensus approach through the Detection Radiation Algorithms Group (DRAG), a multi-institution collaboration spanning eight Department of Energy laboratories and John Hopkins Applied Physics Laboratory. This report includes recommendations on background data variability, and metrics to quantify variability, sources and shielding configurations to include in data collection campaigns and detector response variability. In addition, this report describes several anomaly detection and identification algorithms and recommends metrics to report their performance. Finally, this report ends with a discussion on machine learning algorithms.
The Background Adaptive Radiation Software can be deployed with static sensors in urban environments. It provides a real-time robust radiation detection based on a unique adaptive learning approach. Local radiation background models are automatically learnt for various environmental conditions, and monitored/re-trained, and selected over time for optimal radiation anomaly detection, informed by source templates directly derived from the data.
The lifecycle of radiation detection systems functioning within a State’s Nuclear Security Detection Architecture encompasses all activities associated with acquisition, deployment, and eventual disposal. Throughout a system’s lifecycle, testing and evaluation activities are needed to ensure requirements are continually met, as underscored by recent experiences.This paper provides:1.A discussion of reasons why testing should be part of the radiation detection equipment lifecycle before, during, and after acquisition.2.A general process for determining applicable evaluation methods.3.A discussion of issues related to integrating testing and evaluation into procurement and operational processes and mitigation strategies.
The present disclosure relates to a method for detecting incoming radiation having a plurality of differing properties including at least one of differing types, differing energies or differing incoming directions. The method involves using a scintillator structure formed from first and second dissimilar scintillator materials, where the first and second dissimilar scintillator materials emit first and second different colors of light in response to the incoming radiation. A first light detector is used for detecting light having the first color, and a second light detector is used for detecting light having the second color. A first output signal is generated in response to the detection of light having the first color, and a second output signal is generated in response to detecting light having the second color. The first and second output signals are then analyzed to determine at least one property of the incoming radiation.
GammaPix™ is a smartphone application that uses smartphone cameras to detect ionizing radiation. Brookhaven National Laboratory (BNL) evaluated the performance of the software in detecting radioactive materials. For this purpose, a series of tests were conducted at the Radiation Calibration Facility Annex at BNL. The experiments included dose measurements with three types of NIST-traceable calibration sources, 60Co, 241Am, and 137Cs. The recorded results by GammaPix™ were compared with the values measured by calibrated dosimeters to determine the detection thresholds. Several selected models of iPhones and Android cell phones with different pixel sizes and resolution were tested. In this paper, we present the test procedures and discuss the test results.