Edward R. Siciliano

Comparison of plastic and NaI(Tl) scintillators for vehicle portal monitor applications

Experimental data and computer simulations are presented for gamma-ray detection by vehicle portal monitors for homeland security applications at international borders. The experiments and simulations use spectral processing of gamma rays from various sources (/sup 241/Am, /sup 57/Co, /sup 133/Ba, /sup 137/Cs, /sup 60/Co) and background to provide data for comparing plastic and NaI(Tl) detectors. The effects of gamma-ray scattering in cargo are also examined. Plastic scintillators are well suited for primary screening of gamma-ray sources because of their large size and low cost. Sodium iodide is preferable to plastic for applications of isotope identification based on gamma-ray spectrometry. Some applications may benefit from integrating features from both types of detectors.

Boron-Lined Neutron Detector Measurements

Radiation portal monitors used for interdiction of illicit materials at borders include highly sensitive neutron detection systems. The main reason for having neutron detection capability is to detect fission neutrons from plutonium. The currently deployed radiation portal monitors (RPMs) from Ludlum and Science Applications International Corporation (SAIC) use neutron detectors based upon 3He-filled gas proportional counters, which are the most common large neutron detector. There is a declining supply of 3He in the world, and thus, methods to reduce the use of this gas in RPMs with minimal changes to the current system designs and sensitivity to cargo-borne neutrons are being investigated. Four technologies have been identified as being currently commercially available, potential alternative neutron detectors to replace the use of 3He in RPMs. Reported here are the results of tests of a newly designed boron-lined proportional counter option. This testing measured the neutron detection efficiency and gamma ray rejection capabilities of a system manufactured by Reuter Stokes.

Final Technical Report for the Neutron Detection without Helium-3 Project

This report details the results of the research and development work accomplished for the ‘Neutron Detection without Helium-3’ project conducted during the 2011-2013 fiscal years. The primary focus of the project was to investigate commercially available technologies that might be used in safeguards applications in the relatively near term. Other technologies that are being developed may be more applicable in the future, but were outside the scope of this study.

Boron-10 lined proportional counter model validation

The decreasing supply of 3He is stimulating a search for alternative neutron detectors; one potential 3He replacement is 10B-lined proportional counters. Simulations are being performed to predict the performance of systems designed with 10B-lined tubes. Boron-10-lined tubes are challenging to model accurately because the neutron capture material is not the same as the signal generating material. Thus, to simulate the efficiency, the neutron capture reaction products that escape the lining and enter the signal generating fill gas must be tracked. The tube lining thickness and composition are typically proprietary vendor information, and therefore add additional variables to the system simulation. The modeling methodologies used to predict the neutron detection efficiency of 10B-lined proportional counters were validated by comparing simulated to measured results. The measurements were made with a 252Cf source positioned at several distances from a moderated 2.54-cm diameter 10B-lined tube. Models were constructed of the experimental configurations using the Monte Carlo transport code MCNPX, which is capable of tracking the reaction products from the (n,10B) reaction. Several different lining thicknesses and compositions were simulated for comparison with the measured data. This paper presents the results of the evaluation of the experimental and simulated data, and a summary of how the different linings affect the performance of a coincidence counter configuration designed with 10B-lined proportional counters.

Optimal Background Attenuation for Fielded Radiation Detection Systems

Radiation detectors are often placed in positions difficult to shield from the effects of terrestrial background. This is particularly true in the case of Radiation Portal Monitor (RPM) systems, as their wide viewing angle and outdoor installations make them susceptible to terrestrial background from the surrounding area. A low background is desired in most cases, especially when the background noise is of comparable strength to the signal of interest. The problem of shielding a generalized RPM from terrestrial background is considered. Various detector and shielding scenarios are modeled with the Monte-Carlo N Particle (MCNP) computer code. Amounts of nominal-density shielding needed to attenuate the terrestrial background to varying degrees are given, along with optimal shielding geometry to be used in areas where natural shielding is limited, and where radiation detection must occur in the presence of natural background. Common shielding solutions such as steel plating are evaluated based on the signal to noise ratio and the benefits are weighed against the incremental cost.

Naturally Occurring Radioactive Materials in Cargo at US Borders

Abstract In the USA and other countries large numbers of vehicles pass through border crossings each day. The illicit movement of radioactive sources is a concern that has resulted in the installation of radiation detection and identification instruments at border crossing points. This activity is judged to be necessary because of the possibility of an act of terrorism involving a radioactive source that may include any number of dangerous radionuclides. The problem of detecting, identifying and interdicting illicit radioactive sources is complicated by the fact that many materials present in cargo are somewhat radioactive. Some cargo contains naturally occurring radioactive material that may trigger radiation portal monitor alarms. Such nuisance alarms can be an operational limiting factor for screening of cargo at border crossings. Information about the nature of the radioactive materials in cargo that can interfere with the detection of radionuclides of concern is necessary to help anticipate and recognise likely sources of these nuisance alarms.

Modeling and Simulation Optimization and Feasibility Studies for the Neutron Detection without Helium-3 Project

This report details the results of the modeling and simulation work accomplished for the ‘Neutron Detection without Helium-3’ project during the 2011 and 2012 fiscal years. The primary focus of the project is to investigate commercially available technologies that might be used in safeguards applications in the relatively near term. Other technologies that are being developed may be more applicable in the future, but are outside the scope of this study.

Comparison of NaI(Tl) scintillators and high purity germanium for vehicle portal monitor applications

Radiation portal monitors are being deployed at international border crossings to detect illicit transport of radioactive material. Typically, vehicles which have a gamma-ray radiation signature above a certain gross-count threshold proceed through a more thorough inspection to locate and identify the source of radiation. Plastic scintillators (e.g., poly vinyl toluene (PVT)) are the most common gamma-ray detectors for portal monitors, mainly because of their relatively low cost for large-area, high-sensitivity detectors. Plastic scintillators provide gamma-ray detection, but limited spectroscopic information. Sodium iodide [NaI(Tl)] scintillator-based portal monitors can provide isotopic identification and may be useful where isotopic identification is needed. Recently, high purity germanium [HPGe]-based portal monitors have been evaluated since the increased resolution from HPGe can potentially provide isotopic identification more precisely and rapidly if deployed with adequate efficiency.

BF3 Neutron Detector Tests

Radiation portal monitors used for interdiction of illicit materials at borders include highly sensitive neutron detection systems. The main reason for having neutron detection capability is to detect fission neutrons from plutonium. The currently deployed radiation portal monitors (RPMs) from Ludlum and Science Applications International Corporation (SAIC) use neutron detectors based upon 3He-filled gas proportional counters, which are the most common large neutron detector. There is a declining supply of 3He in the world; thus, methods to reduce the use of this gas in RPMs with minimal changes to the current system designs and detection capabilities are being investigated. Reported here are the results of tests of the efficiency of BF3 tubes at a pressure of 800 torr. These measurements were made partially to validate models of the RPM system that have been modified to simulate the performance of BF3-filled tubes. While BF3 could be a potential replacement for 3He, there are limitations to its use in deployed systems.

Boron-10 ABUNCL Prototype Models And Initial Active Testing

The Department of Energy Office of Nuclear Safeguards and Security (NA-241) is supporting the project Coincidence Counting With Boron-Based Alternative Neutron Detection Technology at Pacific Northwest National Laboratory (PNNL) for the development of a 3He proportional counter alternative neutron coincidence counter. The goal of this project is to design, build and demonstrate a system based upon 10B-lined proportional tubes in a configuration typical for 3He-based coincidence counter applications. This report provides results from MCNPX model simulations and initial testing of the active mode variation of the Alternative Boron-Based Uranium Neutron Coincidence Collar (ABUNCL) design built by General Electric Reuter-Stokes. Initial experimental testing of the as-delivered passive ABUNCL was previously reported.