Doctor of Philosophy / Department of Mechanical and Nuclear Engineering / Douglas S. McGregor / Interest in high-efficiency replacements for thin-film-coated thermal neutron detectors led to the development of single-sided microstructured semiconductor neutron detectors (MSNDs). MSNDs are designed with micro-sized trench structures that are etched into a vertically-oriented pvn-junction diode, and backfilled with a neutron converting material, such as ⁶LiF. Neutrons absorbed by the converting material produce a pair of charged-particle reaction products that can be measured by the diode substrate. MSNDs have higher neutron-absorption and reaction-product counting efficiencies than their thin-film-coated counterparts, resulting in up to a 10x increase in intrinsic thermal neutron detection efficiency. The detection efficiency for a single-sided MSND is reduced by neutron streaming paths between the conversion-material filled regions that consequently allow neutrons to pass undetected through the detector. Previously, the highest reported intrinsic thermal neutron detection efficiency for a single MSND was approximately 30%. Methods for double-stacking and aligning MSNDs to reduce neutron streaming produced devices with an intrinsic thermal neutron detection efficiency of 42%. Presented here is a new type of MSND that features a complementary second set of trenches that are etched into the back-side of the detector substrate. These dual-sided microstructured semiconductor neutron detectors (DS-MSNDs) have the ability to absorb and detect neutrons that stream through the front-side, effectively doubling the detection efficiency of a single-sided device. DS-MSND sensors are theoretically capable of achieving greater than 80% intrinsic thermal neutron detection efficiency for a 1-mm thick device. Prototype DS-MSNDs with diffused pvp-junction operated at 0-V applied bias have achieved 53.54±0.61%, exceeding that of the single-sided MSNDs and double-stacked MSNDs to represent a new record for detection efficiency for such solid-state devices.

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Livestock and companion animals are valuable economically and emotionally in the economy of many states and to their citizens. In a radiological emergency situation, the loss of a large amount of livestock could be devastating to a state or national economy. If such an event occurred, there are currently no screening and decontamination protocols for the handling of livestock. This research investigated current policies and procedures for monitoring and decontamination of livestock and companion animals, as well as testing pedestrian portal monitors and a newly designed livestock portal capable of radionuclide identification. It was discovered that only ten states addressed companion animals or livestock anywhere in their emergency planning. Of the ten, only North Carolina, Washington, and a Massachusetts K9 unit had detailed decontamination procedures to report for companion animals. None of the states included detailed procedures for livestock. To address livestock screening, three pedestrian portal monitoring systems were tested in the field and lab trials – the Johnson AM801, TSA TPM903A, and Ludlum 52-1-1. The systems were tested for position and count rate sensitivity with 1 and 5 µCi 137Cs sources placed on four locations on a steer. Factors such as operability and ease of use were also considered. All three systems would alarm when a 5 µCi 137Cs source was used and the occupancy sensor was triggered. The Johnson AM801 system was determined to be the most appropriate for use in livestock screening due to sensitive alarm algorithms, greater position discrimination with four detectors, and ease of adjustment for agricultural purposes. The last phase of this project included designing and constructing a portal system that included radionuclide identification capabilities. An array of six sodium iodide detectors was mounted on a panel and field-tested beside a cattle chute and in a walkway. The custom portal, the Bovine Screening Portal (BSP), observed increased count rates (>10σ) from a 5 µCi 137Cs source in live time. The BSP demonstrated better detection and localization of the source and spectral identification capabilities compared to the commercially available pedestrian systems.

Made available in DSpace on 2014-10-09T12:54:24Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:08:02Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:54:24Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:08:02Z (GMT). No. of bitstreams: 0 / O comércio de vegetais minimamente processados (VMP) tem crescido substancialmente nos últimos anos devido a sua conveniência, frescor e aparente salubridade. No entanto, o processamento mínimo não reduz as populações de microrganismos patogênicos para níveis seguros. A irradiação de alimentos é utilizada para estender a vida de prateleira e inativar patógenos presentes nos alimentos. Seu uso combinado com o processamento mínimo poderia aumentar a segurança e qualidade dos VMP. Dois diferentes métodos de detecção de alimentos irradiados, um biológico, o DEFT/APC, e outro bioquímico, o teste do cometa, foram aplicados a VMP com o objetivo de testar sua aplicabilidade na detecção do tratamento por radiação. O DEFT/APC é um método de varredura microbiológico baseado no uso da técnica de epifluorescência direta em filtro (DEFT) e da contagem padrão em placas (APC). O teste do cometa detecta o dano no DNA devido, por exemplo, a radiação ionizante. Amostras de acelga, agrião, alface, catalônia, couve, escarola, espinafre e repolho do comércio varejista foram irradiadas com 0,5kGy e 1,0kGy utilizando um irradiador de 60Co. O processamento por irradiação garantiu a redução de pelo menos dois ciclos logarítmicos nas populações de microrganismos aeróbios e psicrotróficos. Em geral, com o aumento das doses de radiação, as contagens DEFT se mantiveram similares independentemente do processamento por irradiação, enquanto as contagens APC diminuíram gradualmente. A diferença das duas contagens aumentou gradualmente com o incremento da dose em todas as amostras. Uma diferença entre o valor de DEFT e do APC maior a 2,0 log seria indicativa de que o VMP foi tratado por irradiação. O teste do cometa permitiu distinguir amostras não irradiadas das irradiadas, que mostraram diferentes tipos de cometas decorrentes da fragmentação do DNA. Tanto o método DEFT/APC quanto o teste do cometa foram satisfatoriamente utilizados como métodos de varredura para a detecção do tratamento por irradiação. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energéticas e Nucleares - IPEN/CNEN-SP

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Doctor of Philosophy / Department of Mechanical and Nuclear Engineering / Douglas S. McGregor / Strengthening the crystal lattice of lanthanide halides, which are brittle, anisotropic, ionic crystals may increase the availability and ruggedness of these scintillators for room-temperature γ-ray spectroscopy applications. Eight dopants for CeBr[subscript]3, including CaBr[subscript]2, SrBr[subscript]2, BaBr[subscript]2, ZrBr[subscript]4, HfBr[subscript]4, ZnBr[subscript]2, CdBr[subscript]2, and PbBr[subscript]2, were explored at two different doping levels, 500ppm and 1000ppm, in an effort to identify potential aliovalent strengthening agents which do not adversely affect scintillation performance. All dopants and doping levels exhibited improved ingot yields over the undoped case, indicating an improvement in the ease of crystal growth. Scintillation performance was gauged using four key metrics. Scintillation emission spectra or, rather, radioluminescence spectra were recorded using x-ray irradiation. Total light yield was estimated through pulse height comparison with bismuth germanate (BGO) scintillators. Scintillation kinetics were checked by measuring single interaction pulses directly output by a fast response PMT. Finally, light yield proportionality was measured using a Compton coincidence system. Samples from each ingot were harvested to benchmark their performance with the four metrics. Of the eight dopants explored, only BaBr[subscript]2 and PbBr[subscript]2 clearly altered scintillation spectral emission characteristics significantly. The remaining dopants, CaBr[subscript]2, SrBr[subscript]2, ZrBr[subscript]4, HfBr[subscript]4, CdBr[subscript]2 and ZnBr[subscript]2, altered scintillation performance to a lesser degree. No dopant appeared to affect light yield proportionality, nor did any drastically alter the light decay characteristics of CeBr[subscript]3. HfBr[subscript]4 and ZnBr[subscript]2-doped CeBr[subscript]3 exhibited the highest light yields, significantly higher than the undoped CeBr[subscript]3 samples tested. Finally, aliovalent doping appeared to greatly improve CeBr[subscript]3 ingot yields, regardless of the dopant, thus it is a promising method for improving crystal strength while not deleteriously affecting scintillation performance. HfBr[subscript]4 and ZnBr[subscript]2 both demonstrated high performance without any noticeable negative side-effects and are prime candidates for future study.

It has been shown that neutrons emitted from the same 252Cf fission event are preferentially detected within small angles of each other and at angles around 180 degrees. The distribution of this angular anisotropy is dependent upon the nuclide emitting the neutrons. Coincident neutrons can be detected from a shielded source, so a study of the angular anisotropy between coincident neutrons is useful for this context. This could allow for the dynamic determination of the ratio of the rate of (alpha,n) neutron production to the spontaneous fission neutron production (designated alpha) used in neutron coincidence counting for safeguards. This could also be used to identify neutron emitting isotopes in a homeland security application. An angular frequency distribution for coincident neutrons was produced via experiments using an array of cylindrical liquid scintillators and a 252Cf source. It was found, in accordance with previous experiments, that the angular frequency distribution peaks at small angles and at angles around 180 degrees. A Monte Carlo, physics-based simulation program was created to simulate the distribution of angles between neutrons from the same fission event from 252Cf and 240Pu sources. The resulting distributions were clearly distinguishable from each other. The code was benchmarked to measured results from a 252Cf source at Lawrence Livermore National Laboratory. Knowledge of the unique angular distributions of coincident neutrons from various fissioning sources is useful for identification and verification purposes. Another practical application of angular anisotropy information for coincident neutrons from a given source is determining the ratio of the (alpha,n) to spontaneous fission rates for a source undergoing neutron coincidence counting. The utility of this was verified by using measurements made by faculty and students of the University of Michigan Nuclear Engineering Department for a MOX fuel pin at the Joint Research Center in Ispra, Italy. Good agreement between the predicted and declared values for alpha was found.

This thesis presents a method for a small, inexpensive mobile robot equipped with a single high resolution scintillation detector to quickly survey an area and convey information about local sources of gamma radiation to a remote human operator. This is achieved by surrounding the detector with a lead sheath that blocks all gamma rays except those incident along the detector???s axial direction. A horizontal scan is performed by rotating the detector and a directional profile of gamma radiation is constructed. In addition a visual panorama of the local area is assembled using a camera mounted on the detector. A plot of the detector signal versus angle is then overlaid on top of the visual panorama and visible peaks clearly indicate the direction of local gamma radiation sources. Moreover, measuring the energy spectrum of gamma rays in each direction produces a 2D count frequency histogram where distinct peaks indicate the energy and direction of local gamma ray sources allowing the identification of different radio-isotopes.