<p><font face="Arial"> <p align="left">In this study, the capabilities of Neutron Radiography (NRad) and -Tomography (NTomo), as well as X-ray Radiography (XRad) to investigate chlorides and chlorides corrosion effects within steel reinforced laboratory concrete samples are practically explored. Capabilities of Scanning Electron Microscopy (SEM), Prompt Gamma Neutron Activation Analysis (PGNAA), Particle Induced X-ray Emission (PIXE), Small-Angle Neutron Scattering (SANS), Neutron Diffraction (NDIFF) and X-ray Diffraction (XDIFF) analytical techniques are also explored through review of literature.</p> </font></p>

<p><font face="Arial"> <p align="left">In this study, the capabilities of Neutron Radiography (NRad) and -Tomography (NTomo), as well as X-ray Radiography (XRad) to investigate chlorides and chlorides corrosion effects within steel reinforced laboratory concrete samples are practically explored. Capabilities of Scanning Electron Microscopy (SEM), Prompt Gamma Neutron Activation Analysis (PGNAA), Particle Induced X-ray Emission (PIXE), Small-Angle Neutron Scattering (SANS), Neutron Diffraction (NDIFF) and X-ray Diffraction (XDIFF) analytical techniques are also explored through review of literature.</p> </font></p>

Magister Scientiae - MSc / In this study, the capabilities of Neutron Radiography (NRad) and -Tomography (NTomo), as well as X-ray Radiography (XRad) to investigate chlorides and chlorides corrosion effects within steel reinforced laboratory concrete samples are practically explored. Capabilities of Scanning Electron Microscopy (SEM), Prompt Gamma Neutron Activation Analysis (PGNAA), Particle Induced X-ray Emission (PIXE), Small-Angle Neutron Scattering (SANS), Neutron Diffraction (NDIFF) and X-ray Diffraction (XDIFF) analytical techniques are also explored through review of literature.

No Brasil, atualmente só há um laboratório de calibração de monitores de radiação de nêutrons, sendo responsável pela guarda e manutenção do padrão brasileiro da fluência de nêutrons, localizado no Laboratório Nacional de Metrologia das Radiações Ionizantes (LNMRI), Rio de Janeiro, no Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, Rio de Janeiro, com uma demanda grande de serviços com esse tipo de radiação. Com o intuito de descentralizar a oferta de serviços de calibração, surgiu a necessidade da montagem de um segundo Laboratório de Calibração com Nêutrons (LCN), no IPEN. Nas situações práticas envolvendo a calibração de monitores de radiação de nêutrons, um dos problemas principais está relacionado à radiação espalhada, que pode variar dependendo das dimensões do laboratório usado nos procedimentos de calibração. No processo de caracterização do campo de radiação de nêutrons da fonte de 241AmBe, onde foi realizada a avaliação dos espectros, das energias, das taxas de fluência, das taxas de equivalente de dose ambiente [H*(10)] e do coeficiente de conversão de fluência em dose [h*&phi;(10)] em diferentes posições do LCN, utilizando o feixe completo. A influência da radiação espalhada foi determinada por meio de três técnicas: Métodos de Monte Carlo, de Ajuste Reduzido e do Cone de Sombra. Dos resultados obtidos por meio de simulação e experimentalmente foi possível obter a fração de espalhamento em diferentes distâncias fonte-detector. / In Brazil, there is currently only one calibration laboratory for neutron radiation monitors. It is responsible for the custody and maintenance of the Brazilian neutron fluence standard, located at the Laboratório Nacional de Metrologia das Radiações Ionizantes-LNMRI, Rio de Janeiro, at the Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, with a great demand of services with this type of radiation. In order to decentralize the calibration service offer, it was necessary to set up a second Neutron Calibration Laboratory (LCN), at IPEN. In practical situations involving the calibration of neutron radiation monitors, one of the main problems is related to scattered radiation, which may vary depending on the size of the laboratory used for the calibration procedures. In the process of characterization of the neutron radiation field of the 241AmBe source, the spectra, the energies, the fluence rate, the ambient dose equivalent rate and the conversion coefficient of fluence in dose at different positions of the LCN, were evaluated using the complete beam. The influence of the scattered radiation was determined by three techniques: Monte Carlo Method, the Reduced Adjustment Method and the Shade Cone Method. From the results obtained through simulation and experimentally, it was possible to obtain the scattering fraction at different source-detector distances.

No Brasil, atualmente só há um laboratório de calibração de monitores de radiação de nêutrons, sendo responsável pela guarda e manutenção do padrão brasileiro da fluência de nêutrons, localizado no Laboratório Nacional de Metrologia das Radiações Ionizantes (LNMRI), Rio de Janeiro, no Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, Rio de Janeiro, com uma demanda grande de serviços com esse tipo de radiação. Com o intuito de descentralizar a oferta de serviços de calibração, surgiu a necessidade da montagem de um segundo Laboratório de Calibração com Nêutrons (LCN), no IPEN. Nas situações práticas envolvendo a calibração de monitores de radiação de nêutrons, um dos problemas principais está relacionado à radiação espalhada, que pode variar dependendo das dimensões do laboratório usado nos procedimentos de calibração. No processo de caracterização do campo de radiação de nêutrons da fonte de 241AmBe, onde foi realizada a avaliação dos espectros, das energias, das taxas de fluência, das taxas de equivalente de dose ambiente [H*(10)] e do coeficiente de conversão de fluência em dose [h*&phi;(10)] em diferentes posições do LCN, utilizando o feixe completo. A influência da radiação espalhada foi determinada por meio de três técnicas: Métodos de Monte Carlo, de Ajuste Reduzido e do Cone de Sombra. Dos resultados obtidos por meio de simulação e experimentalmente foi possível obter a fração de espalhamento em diferentes distâncias fonte-detector. / In Brazil, there is currently only one calibration laboratory for neutron radiation monitors. It is responsible for the custody and maintenance of the Brazilian neutron fluence standard, located at the Laboratório Nacional de Metrologia das Radiações Ionizantes-LNMRI, Rio de Janeiro, at the Instituto de Radioproteção e Dosimetria, Comissão Nacional de Energia Nuclear, with a great demand of services with this type of radiation. In order to decentralize the calibration service offer, it was necessary to set up a second Neutron Calibration Laboratory (LCN), at IPEN. In practical situations involving the calibration of neutron radiation monitors, one of the main problems is related to scattered radiation, which may vary depending on the size of the laboratory used for the calibration procedures. In the process of characterization of the neutron radiation field of the 241AmBe source, the spectra, the energies, the fluence rate, the ambient dose equivalent rate and the conversion coefficient of fluence in dose at different positions of the LCN, were evaluated using the complete beam. The influence of the scattered radiation was determined by three techniques: Monte Carlo Method, the Reduced Adjustment Method and the Shade Cone Method. From the results obtained through simulation and experimentally, it was possible to obtain the scattering fraction at different source-detector distances.

In this thesis I will present an approach and apparatus for detecting and precisely characterizing any dose-dependent changes in the functional behaviour of a data converter in a neutron radiation environment. Depending on the data converter such changes could include shifts in the gain, offset, noise, or linearity of the device output. The approach leverages the neutron flux produced by an Americium-Beryllium radioisotope neutron source, and is meant to emulate the neutron environment near a Cm-244 source, as found in the sensor head of the APXS instrument. This method uses a relatively low dose rate (configurable by proximity to the source) which allows for long-term monitoring and characterization of parametric changes in device behaviour. It has the additional benefit of not requiring a reactor or accelerator, and can therefore run unattended when necessary. The prototype system, which is designed to allow the data converter to be operating during irradiation, uses LVDS signalling to drive and extract data from a minimal test board which is placed in proximity to the neutron source, and a Virtex-4 FPGA board to provide clock and power, and to perform signal processing. By separating the majority of the test equipment from the neutron environment, any radiation effects will be isolated to the DUT and a minimal set of supporting devices. The prototype design is presented here, along with initial characterization results and first test results on a commercial, off-the-shelf data converter. / Canadian Space Agency, Ontario Centres of Excellence, MacDonald, Dettwiler, and Associates

As the world's nuclear reactors approach the end of their originally planned lifetimes and seek license extensions, which would allow them to operate for another 20 years, accurate information regarding neutron radiation exposure is more important than ever. Structural components such as the reactor pressure vessel (RPV) become embrittled by neutron irradiation, reducing their capability to resist crack growth and increasing the risk of catastrophic failure. The current dosimetry approaches used in these high flux environments do not provide real-time information. Instead, radiation dose is calculated using computer simulations, which are checked against dose readings that are only available during refueling once every 1.5-2 years. These dose readings are also very expensive, requiring highly trained technicians to handle radioactive material and operate specialized characterization equipment. This dissertation describes the development of a novel neutron radiation dosimeter based on carbon nanotubes (CNTs) that not only provides accurate real-time dosimetry, but also does so at very low cost, without the need for complex instrumentation, highly trained operators, or handling of radioactive material. Furthermore, since this device is based on radiation damage rather than radioactivation, its readings are time-independent, which is beneficial for nuclear forensics. In addition to development of a novel dosimeter, this work also provides insight into the particularly under-investigated topic of the effects of neutron irradiation of carbon nanotubes. This work details the fabrication and characterization of carbon nanotube based neutron and gamma radiation dosimeters. They consist of a random network of CNTs, sealed under a layer of silicon dioxide, spanning the gap between two electrodes to form a conductive path. They were fabricated using conventional wafer processing techniques, making them intrinsically scalable and ready for mass production. Electrical properties were measured before and after irradiation at several doses, demonstrating a consistent repeatable trend that can be effectively used to measure dose. Changes to the microstructure were investigated using Raman spectroscopy, which confirmed that the changes to electrical properties are due to increasing defect concentration. The results outlined in this dissertation will have significant impacts on both the commercial nuclear industry and on the nanomaterials scientific community. The dosimeter design has been refined to the point where it is nearly ready to be deployed commercially. This device will significantly improve accuracy of RPV lifetime assessment while at the same time reducing costs. The insights into the behavior of CNTs in neutron and gamma radiation environments is of great interest to scientists and engineers studying these nanomaterials. / Ph. D.

No description available.

A method for measuring system-on-a-chip (SoC) cache upsets is presented and evaluated. In contrast to methods that predict cache contents through analysis or memory access patterns, this method uses system registers to read cache memories directly, thereby creating and checking golden copies to detect individual memory upsets during operation. The test method is driven by the device under test itself and does not require a user to set or know a priori the cache contents. A bare-metal implementation of this “direct golden method” on a Zynq UltraScale+ MPSoC logged upsets in the device’s data cache, data tag, and TLB RAM memories during a neutron radiation beam test. For each of these memories, this direct golden method yields cache upset bit cross sections, such as 7.115 × 10^−16 cm^2 for the data cache. Confidence intervals for these bit cross sections overlap such intervals for three other methods, supporting this method’s validity and candidacy for future use.

SRAM-based FPGAs provide valuable computation resources and reconfigurability; however, ionizing radiation can cause designs operating on these devices to fail. The sensitivity of an FPGA design to configuration upsets, or its SEU sensitivity, is an indication of a design's failure rate. SEU mitigation techniques can reduce the SEU sensitivity of FPGA designs in harsh radiation environments. The reliability benefits of these techniques must be determined before they can be used in mission-critical applications and can be determined by comparing the SEU sensitivity of an FPGA design with and without these techniques applied to it. Many approaches can be taken to evaluate the SEU sensitivity of an FPGA design. This work describes a low-cost easier-to-implement approach for evaluating the SEU sensitivity of an FPGA design. This approach uses additional logic resources on the same FPGA as the design under test to determine when the design has failed, or deviated from its specified behavior. Three SEU mitigation techniques were evaluated using this approach: triple modular redundancy (TMR), configuration scrubbing, and user-memory scrubbing. Significant reduction in SEU sensitivity is demonstrated through fault injection and radiation testing. Two LEON3 processors operating in lockstep are compared against each other using on-chip error detection logic on the same FPGA. The design SEU sensitivity is reduced by 27x when TMR and configuration scrubbing are applied, and by approximately 50x when TMR, configuration scrubbing, and user-memory scrubbing are applied together. Using this approach, an SEU sensitivity comparison is made of designs implemented on both an Altera Stratix V FPGA and a Xilinx Kintex 7 FPGA. Several instances of a finite state machine are compared against each other and a set of golden output vectors, all on the same FPGA. Instances of an AES cryptography core are chained together and the output of two chains are compared using on-chip error detection. Fault injection and neutron radiation testing reveal several similarities between the two FPGA architectures. SEU mitigation techniques reduce the SEU sensitivity of the two designs between 4x and 728x. Protecting on-chip functional error detection logic with TMR and duplication with compare (DWC) is compared. Fault injection results suggest that it is more favorable to protect on-chip functional error detection logic with DWC than it is to protect it with TMR for error detection.