<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>

In the standard theory of pulsar spin-up, a neutron star (NS) in a binary system accretes matter from its companion star; this serves to transfer angular momentum to the NS, increasing the spin frequency of the pulsar. Measurement of the orbital parameters and system geometry, and in particular the final system masses, thus provide important constraints for theories regarding binary evolution. We present results from an investigation of three binary pulsar systems. PSR J1802-2124 is in an intermediate-mass pulsar binary system with a massive white dwarf companion in a compact orbit with a period of 16.8 hours. We have per-formed timing analysis on almost five years of data in order to determine the amount of Shapiro delay experienced by the incoming pulsar signal as it traverses the potential well of the companion star on its way to Earth. We find the pulsar in this system to have a relatively low mass at 1.24 ± 0.11 M®, and the companion mass to be 0.79 ± 0.04111.).We argue that the full set of system properties indicates that the system underwent a common-envelope phase in its evolutionary history. The double pulsar system PSR 0737-3039A/B is a highly relativistic double neutron star (DNS) binary, with a 2.4-hour orbital period. The low mass of the second-formed NS, as well the low system eccentricity and proper motion, have suggested a different evolutionary scenario compared to other known DNS systems. We describe analysis of the pulse profile shape over six years of observations, and present the constraints this provides on the system geometry. We find the recycled pulsar in this system, PSR 0737-3039A,to have a low misalignment angle between its spin and orbital angular momentum axes, with a 95.4% upper limit of 14 °, assuming emission from both magnetic poles. This tight constraint lends credence to the idea that the supernova that formed the second pulsar was relatively symmetric, possibly involving electron captures onto an 0-Ne-Mg core. We have also conducted timing analysis of PSR J1756-2251 using four years of data, and have obtained tight constraints on the component masses and orbital parameters in this DNS system. We have measured four post-Keplerian timing parameters for this pulsar; the Shapiro delay s parameter, with a 5% measured uncertainty, is consistent at just above the la level with the predictions of general relativity. The pulsar in this system has a fairly typical NS mass of 1.312 ± O.017M®, and the companion NS to be relatively light, with a mass of 1.2581017 Mo. This, together with the somewhat low orbital eccentricity of this system (e 0.18), suggests a similar evolution to that of the double pulsar. We investigate this further, through a similar pulse profile analysis to that performed with PSR J0737-3039A, with the goal of constraining the geometry of this system.

Since the beginning of space exploration in last century, several kinds of devices from passive and active dosimeters to radiation environment monitors have been used to measure radiation levels onboard different space crafts and shuttles allowing the space community to identify and quantify space radiation. The recent construction of several laboratories on the International Space Station (ISS) has confirmed that prolonged duration space missions are now becoming standard practice and as such, the need to better understand the potential risk of space radiation to Astronaut’s health, has become a priority for long mission planner. The complex internal radiation environment created within the ISS is due to high-energy particle interactions within the ISS shielded environment. As a result, a large number of secondary particles, that pose specific health risks, are created. Neutrons are one important component of this mixed radiation field due to their high LET. Therefore, the assessment of the neutron dose contribution has become an important part of the safety and monitoring program onboard the ISS. The need to determine whether neutron dose measured externally to the human body give an accurate and conservative estimate of the dose received internally is of paramount importance for long term manned space missions. This thesis presents a part of an ongoing large research program on radiation monitoring on ISS called Matroshka-R Project that was established to analyze the radiation exposure levels onboard the ISS using different radiation instruments and a spherical phantom to simulate human body. Monte Carlo transport code was used to simulate the interaction of high energy protons and neutrons with the spherical phantom currently onboard ISS. A Monte Carlo model of the phantom has been built, and it consists of seven spherical layers presenting different depths of the simulated tissue. The phantom has been exposed to individual proton energies and to a spectrum of neutrons. The flux of the created neutrons inside the phantom has been calculated. The internal to external neutron flux ratio was calculated and compared to the experimental data, recently, measured on three separate expeditions of the ISS. The results from the calculations showed that the value of the neutron fluxes inside and outside the phantom is different from the data recently measured with bubble detectors. / UOIT

Possible fuel cycle scenarios for a helium-cooled, sub-critical, fast reactor with a fusion neutron source for the transmutation of spent nuclear fuel have been analyzed. The transmutation rate was set by the 3000MWth fission power output. The primary objective was to achieve greater than 90% burn of the transuranic (TRU) fuel obtained from spent nuclear fuel. A secondary objective was to examine the possibility of achieving this deep burn without reprocessing after initial fabrication of the TRU into coated particle TRISO fuel. Four sets of 5-batch fuel cycle scenarios, differing in the constraints imposed on the beginning of cycle (BOC) k-eff and the end of cycle (EOC) neutron source strength (characterized by the fusion neutron source power level), were evaluated. In scenario A, BOC k-eff was required to be 0.95 and EOC Pfus less than 200 MWth was required. In scenario B, the restriction was removed to allow less reactive BOC fuel loadings, while the 200 MW upper limit on EOC Pfus was retained. It was found that the primary objective of greater than 90% TRU burn-up could be achieved by repeatedly reprocessing the TRISO TRU fuel particles to remove fission products and add fresh TRU makeup at the end of each 5-batch burn cycle, without needing to increase the fusion neutron source power above 100 MWth when the BOC k-eff is restricted to 0.95. The secondary objective of obviating processing could only be accomplished when the restriction was removed and recycling was employed or when both EOC Pfus and BOC k-eff restrictions were removed in a single-pass deep burn fuel cycle. In scenario C, with both the BOC k-eff limit and the fusion power limit unrestricted, greater than 90% TRU burn-up was achieved without reprocessing the TRISO TRU fuel particles, which could then be buried intact in a high-level waste repository, but a neutron source rate of 3370 MWth was required. In scenario D, with only the BOC k-eff limit unrestricted, greater than 90% TRU burn-up was achieved without reprocessing by the continuous recycle of TRISO particles through the reactor.

Tissue equivalent proportional counters (TEPC) are used for medical and space activities whenever a combination of high and low LET (lineal energy transfer) radiations are present. With the frequency and duration of space activities increasing, exposure to fast heavy ions from galactic cosmic radiation and solar events is a major concern. The optimum detector geometry is spherical; to obtain an isotropic response, but simple spherical detectors have the disadvantage of a non-uniform electric field. In order to achieve a uniform electric field along the detector axis, spherical tissue equivalent proportional counters have been designed with different structures to modify the electric field. Some detectors use a cylindrical coil that is coaxial with the anode, but they are not reliable because of their sensitivity to microphonic noise and insufficient mechanical strength. In this work a new spherical TEPC was developed. The approach used was to divide the cathode in several rings with different thicknesses, and adjust the potential difference between each ring and the anode to produce an electric field that is nearly constant along the length of the anode. A-150 tissue equivalent plastic is used for the detector walls, the insulator material between the cathode rings is low density polyethylene, and the gas inside the detector is propane. The detector, along with the charge sensitive preamplifier, is encased in a stainless steel vacuum chamber. The gas gain was found to be 497.5 at 782 volts and the response to neutrons as a function of angle was constant ±7%. This spherical tissue equivalent proportional counter detector system will improve the accuracy of dosimetry in space, and as a result improve radiation safety for astronauts.

Radiation portal monitors are being deployed at border crossings throughout the world to prevent the smuggling of nuclear and radiological materials; however, a tension exists between security and the free-flow of commerce. Delays at ports-of-entry have major economic implications, so it is imperative to minimize portal monitor screening time. We have developed an algorithm to locate a radioactive source using a distributed array of detectors, specifically for use at border crossings. To locate the source, we formulated an optimization problem where the objective function describes the least-squares difference between the actual and predicted detector measurements. The predicted measurements are calculated by solving the 3-D deterministic neutron transport equation given an estimated source position. The source position is updated using the steepest descent method, where the gradient of the objective function with respect to the source position is calculated using adjoint transport calculations. If the objective function is smaller than a predetermined convergence criterion, then the source position has been identified. To test the algorithm, we first verified that the 3-D forward transport solver was working correctly by comparing to the code PARTISN (Parallel Time-Dependent SN). Then, we developed a baseline scenario to represent a typical border crossing. Test cases were run for various source positions within each vehicle and convergence criteria, which showed that the algorithm performed well in situations where we have perfect knowledge of parameters such as the material properties of the vehicles. We also ran a sensitivity analysis to determine how uncertainty in various parameters-the optical thickness of the vehicles, the fill level in the gas tank, the physical size of the vehicles, and the detector efficiencies-affects the results. We found that algorithm is most sensitive to the optical thickness of the vehicles. Finally, we tested the simplifying assumption of one energy group by using measurements obtained from MCNPX (Monte Carlo N-Particle Extended). These results showed that the one-energy-group assumption will not be sufficient if the code is deployed in a real-world scenario. While this work describes the application of the algorithm to a land border crossing, it has potential for use in a wide array of nuclear security problems.

A new set of thermal neutron detectors has been developed as a near term 3He tube replacement. The zinc oxide scintillator is an ultrafast scintillator which can be doped to have performance equal to or superior to 3He tubes. Originally investigated in the early 1950s, this room temperature semiconductor has been evaluated as a thermal neutron scintillator. Zinc oxide can be doped with different nuclei to tune the band gap, improve optical clarity, and improve the thermal neutron detection efficiency. The effects of various dopant effects on the scintillation properties, materials properties, and crystal growth parameters have been analyzed. Two different growth modalities were investigated: bulk melt grown materials as well as thin film scintillators grown by metalorganic chemical vapor deposition (MOCVD). MOCVD has shown significant advantages including precise thickness control, high dopant incorporation, and epitaxial coatings of neutron target nuclei. Detector designs were modeled and simulated to design an improved thermal neutron detector using doped ZnO layers, conformal coatings and light collection improvements including Bragg reflectors and photonic crystal structures. The detectors have been tested for crystalline quality by XRD and FTIR spectroscopy, for scintillation efficiency by photo-luminescence spectroscopy, and for neutron detection efficiency by alpha and neutron radiation tests. Lastly, a novel method for improving light collection efficiency has been investigated, the creation of a photonic crystal scintillator. Here, the flow of optical light photons is controlled through an engineered structure created with the scintillator materials. This work has resulted in a novel radiation detection material for the near term replacement of 3He tubes with performance characteristics equal to or superior to that of 3He.

L'étude structurale et magnétique de la partie riche en bismuth, 0,7 ≥ x ≥ 0,5, du système BixCa1-xMnO3 est présentée dans ce manuscrit. Les résultats des techniques de diffraction des rayons X, des neutrons, des électrons, de microscopie électronique en transmission haute résolution et de mesures des propriétés macroscopique ont été confrontés afin de produire une interprétation la plus juste possible expliquant les relations entre propriétés magnétique et structure. Des échantillons poly-cristallins et des monocristaux ont été synthétisé à cette fin. Le composé x = 0.5 semble à part. Un modèle de localisation des charges « unique » est présenté pour x = 0,55, 0,6 et 0,64. La localisation des charges se fait, non pas sur un site Mn, mais sur une entité MnOMn (polaron de Zener). Plusieurs modèles de structures magnétiques, dont le modèle de type CE, permettent de modéliser les diffractogrammes BT de ces composés.<br />Quand x augmente les couplages ferromagnétiques tendent à augmenter. Le composé Bi0.67Ca0.33MnO3 apparaît comme un composé charnière pour lequel la localisation des charges est déstabilisée. L'étude de son état magnétique BT a confirmé la coexistence d'un état verre de spin et d'un ordre magnétique à longue distance. L'origine de l'état verre de spins dans Bi0.67Ca0.33MnO3 est interprétée comme une dilution de domaines FM dans une matrice AFM induite par l'occupation aléatoire du site A par le Bi et le Ca. Bien que le composé Bi0.71Ca0.24MnO3 présente le même état BT, une surstructure nucléaire différente de type [111]p (proche de celle du multiferroïque BiMnO3) a été affinée. Un modèle de frustration magnétique a été proposé en se basant sur l'ordre orbitalaire affiné dans ce composé.

Dans les hydrures de phases de Laves AMn2Hy (A = Y ou terre rare magnétique), le réseau de l'hydrogène interagit fortement avec les réseaux magnétiques, en particulier avec celui topologiquement frustré du Mn. Nous avons étudié l'ordre magnétique par diffraction et diffusion inélastique de neutrons, et avons observé une énorme richesse de comportements magnétiques pilotés par la présence ou non du magnétisme de la terre rare, le type de substitutions dans le réseau frustré Mn, la concentration H et surtout l'état d'ordre du réseau de l'hydrogène. Ce travail a révélé de nouvelles phases magnétiques, qui combinent un très haut degré de désordre à des températures d'ordre élevées. La pression induit dans ces composés désordonnés des effets spectaculaires ségrégation chimique de l'hydrogène, transitions isostructurales ou encore stabilisation d'un nouveau type d'ordre magnétique à longue portée. Nous avons aussi effectué les premières mesures de diffraction de neutrons sous pression dans le système topologiquement frustré Tb2Ti207, qui présente un comportement liquide de spin, et observé l'apparition d'un ordre magnétique à longue portée.<br />Mots-clés : hydrures, frustration topologique, magnétisme, diffraction de neutrons, diffusion inélastique de neutrons, pression hydrostatique, liquide de spin.

Ce travail de thèse porte sur une protéine de la catalyse enzymatique : l'inhibiteur de la trypsine pancréatique bovine ou BPTI qui est un système modèle très étudié par différentes techniques mais peu par diffusion de neutrons. Il s'agit d'une petite protéine (58 résidus d'acides aminés, poids moléculaire de 6500 Da) qui possède une très grande stabilité puisqu'elle ne peut être dénaturée à des température inférieures à 95°C ou à des pressions inférieures à 14 kbar. Cette stabilité est due à la présence de trois ponts disulfures et de trois ponts salins. Nous avons étudié la structure et la dynamique de l'état natif et des états dénaturés par la température et par la pression, du BPTI, par la technique de diffusion de neutrons. La diffusion de neutrons aux petits angles nous a permis d'observer une augmentation du rayon de giration de la protéine en solution à 95°C et une réduction de ce rayon à 6000 bar. La forme ellipsoïdale de la molécule à l'état natif n'est pas modifiée entre 22°C et 95°C mais présente une augmentation du volume du BPTI. De plus, la forme du BPTI est modifiée depuis une forme ellipsoïdale dans l'état natif, vers une forme globulaire à 3000 bar et micellaire lorsque la pression atteint 5000 et 6000 bar. Des expériences complémentaires par spectroscopie infrarouge et UV-visible, en température et en pression, ont permis de confirmer ces résultats. La diffusion quasiélastique de neutrons a permis d'observer un effet antagoniste de la température et de la pression sur les mouvements globaux et sur la dynamique interne du BPTI en solution. L'augmentation de la température a pour effet d'induire des mouvements globaux et internes plus rapides tandis que l'augmentation de la pression induit un ralentissement de ces mouvements.