CANDU (CANada Deuterium Uranium) reactor utilizes Pressure Tube (PT) fuel channel design and heavy water as a coolant. Fuel channel annulus gas acts as an insulator to minimize heat losses from the coolant to the moderator. Since fuel bundles are continuously under high neutron fluxes, annulus gas nuclides undergo different nuclear transformations generating new composition of the gas that might have different physical properties which are undesirable for the annulus system. In addition, gas nuclides become radioactive and lead to an increase of the radioactive material inventory in the reactor and consequently to an increase of radiation levels. Pressure Tube Reactor (PTR) and Pressure Tube Supercritical Water Reactor (PT SCWR) fuel channel models have been developed in Monte Carlo N-Particle (MCNP) code. Neutron fluxes in the fuel channel annulus gas have been obtained by simulating different types of neutron sources in both PTR and PT SCWR fuel channels. Transmutation rates of annulus gases have been calculated for different gases (CO2, N2, Ar and Kr) at different pressures and temperatures in both fuel channels. The variation of the transmutation rates, neutron fluxes and gas densities in the annulus gas have been investigated in PTR and PT SCWR fuel channels at constant pressures and different temperatures. MCNP code along with NIST REFPROP [14] and other software tools have been used to conduct the calculations. / UOIT

L'hyperdéformation est une technique efficace pour transformer la microstructure des métaux en une structure de grain de taille inférieure au micron ou même en nanostructure (<100 nm). Cette très petite taille de grain confère d'excellentes propriétés mécaniques au matériau. Dans ce travail de thèse, deux techniques d'hyperdéformation récemment développées, appelées High Pressure Tube Twisting (HPTT) and Cyclic Expansion and Extrusion (CEE) ont été appliquées à température ambiante sur différents matériaux métalliques. La fragmentation de la microstructure ainsi que le développement de la texture cristallographique ont été analysés en détails par la diffraction d'électrons rétrodiffusés (EBSD), par microscopie électronique en transmission (TEM), par transmission Kikuchi diffraction (TKD) ainsi que par diffraction des rayons X (XRD). Le gradient de déformation de cisaillement dans l'épaisseur des tubes d'aluminium déformés par HPTT a été déterminé par une méthode de mesure locale du cisaillement. Ce gradient de cisaillement induit une hétérogénéité aussi bien de microstructure que de texture dans les échantillons d'aluminium et de magnésium purs ainsi que dans l'alliage Al-4%Mg en solution solide. La micro-dureté et la taille de grain dans différentes zones ont été mesurées et analysées en fonction du taux cisaillement local. Les tailles de grain limites atteintes de façon stationnaire pour ces différents matériaux produit par HPTT sont respectivement de 700 nm, 900 nm et 100 nm. L'évolution de texture du magnésium pur après HPTT jusqu'à un cisaillement de 16 a été simulée par cisaillement simple par le model auto-cohérent (VPSC), le résultat de simulation a montré de bons accords avec les mesures de texture obtenues par XRD. Sur la base des mesures de distribution de désorientation dans l'aluminium déformé par HPTT, une nouvelle technique de détermination du taux de cisaillement local dans les procédés d'hyper déformation a été proposée. Cette nouvelle technique a été appliquée sur deux échantillons d'aluminium produit par twist extrusion (TE) et par torsion à extrémités libres. Les échantillons d'aluminium et de cuivre ont été déformés intensément par CEE. Les évolutions de texture et de microstructures ont été mesurées par EBSD, montrant un gradient du centre à la périphérie des échantillons cylindriques. L'évolution de texture dans le cuivre déformé par CEE a été simulée par le modèle VPSC en utilisant un modèle de ligne de courant pour décrire la déformation dans le procédé. Les résultats de simulation confirment les caractéristiques de la texture expérimentale observées après CEE. Le comportement en traction du cuivre pré-déformé par grande déformation en torsion a ensuite été testé. En dépit du gradient de cisaillement existant dans la barre, une technique a été proposée pour obtenir la courbe contrainte-déformation pour ce type de matériau. / Severe plastic deformation (SPD) is an efficient technique to transform the microstructure of bulk metals into ultra fine grained structure with grain sizes less than 1 µm or even into nanostructure with nano-grains of less than 100 nm in diameter. The very small grain size attributes excellent mechanical properties to the material. In present thesis work, two recently developed SPD techniques, namely, High Pressure Tube Twisting (HPTT) and Cyclic Expansion and Extrusion (CEE) were performed on different metallic materials at room temperature. Details of fragmentation of microstructure and metallographic texture evolution were investigated by electron backscattered diffraction (EBSD), transmission electron microscopy (TEM), transmission kikuchi diffraction (TKD) and X-ray diffraction (XRD). Shear strain gradient across the thickness of the HPTT deformed Al tube sample was found by a local shear measurement method. This shear strain gradient induced the inhomogeneity of microstructure and texture in HPTT deformed pure Al, solid solution alloy Al-4%Mg and pure Mg. The microhardness and average grain size in different zones as a function of shear strain were measured. The limiting steady grain sizes in the steady state for these different materials produced by HPTT were 700 nm, 100 nm and 900 nm, respectively. The texture evolution of pure Mg in HPTT up to a shear strain of 16 was simulated in simple shear using the self-consistent (VPSC) polycrystal model and showed good agreements with the experimental results measured by XRD. Based on the measured disorientation distribution function in HPTT deformed Al, a new technique for the magnitude of local shear strain in SPD was proposed. This new technique was applied to a protrusion produced in twist extrusion (TE) and to an Al sample deformed in free-end torsion. Cu and pure Al samples were intensively deformed by the CEE SPD technique. The microstructure and texture evolutions were measured by EBSD, showing a gradient from the center-zone to the edge part of the rod sample. The texture evolution of CEE deformed Cu was simulated by the VPSC polycrystal model using a flow line function. The simulation results confirmed the experimental texture features observed in the CEE process. The tensile testing behavior of large strain torsion pre-processed Cu was examined. In spite of the shear strain gradient existing in the bar, a technique was proposed to obtain the tensile stress-strain curve of such gradient material.

Self-compacting concrete (SCC) offers rational and fast casting process since it merely has to be poured, or pumped, into the formwork without any compaction work needed. But this can be at the cost of high form pressure. However, reported results show that SCC can act thixotropically, i.e., build up a structure at rest, and this can reduce the form pressure considerably. Thus, in order to utilise the favourable possibilities to increase effectiveness without risking form collapses, the need arises for deeper and broader understanding of the mechanisms behind this thixotropic behaviour. Methodologies have been developed for the characterisation and measurement of the structural build-up at rest, both for the fluid (micro mortar) phase and the concrete itself. Hypotheses state that thixotropic mechanisms originate within the colloidal domain and, thus, motivate studies on the fluid phase comprising this domain. The stress-strain methodology is based on the hypothesis stating that the magnitude of the structure is represented by the maximum elastic stress the fresh material can withstand before the structure breaks. An instrumented steel tube is used to simulate various casting heights and rates. Results show that both micro mortar and SCC are thixotropic and this behaviour is influenced by every measure taken influencing the interparticle colloidal forces. The time-dependent structural build-up of SCC is a function of an irreversible structure (slump-loss) and a reversible, thixotropic structure. There is apparently a threshold value of the structural build-up necessary to reach before obtaining any significant form pressure reduction. Housing SCC´s, with W/C = 0.58, show low degree of structural build-up and pressure decrease while civil engineering SCC´s can show the opposite, but this often at the cost of slump-loss. Recommendations are presented and for the nearest future, suggesting a conservatism regarding design of formwork systems when SCC is used. If the behaviour of a SCC is known it should be used to optimise the formwork. If not, calculating with hydrostatic pressure should be done or the knowledge missing should be gained by using this methodology. A third option is given and this is to monitor the form pressure in real time using sensors. / QC 20100812

Probabilistic assessment and life cycle management of engineering components and systems in a nuclear power plant is intended to ensure safe and efficient operation of energy generation over its entire life. The CANDU reactor core consists of 380-480 pressure tubes, which are like miniature pressure vessels that contain natural uranium fuel. Pressure tubes operate under severe temperature and radiation conditions, which result in degradation with ageing. Presence of flaws in a pressure tube makes it vulnerable to delayed hydride cracking (DHC), which may lead to rupture or break-before-leak situation. Therefore, assessment of flaws in the pressure tubes is considered an integral part of a reactor core assessment program. The main objective of the thesis is to develop advanced probabilistic and mechanical stress field models for the assessment of flaws. The flaw assessment models used by the industries are based on deterministic upper/lower bound values for the variables and they ignore uncertainties associated with system parameters. In this thesis, explicit limit state equations are formulated and first order reliability method is employed for reliability computation, which is more efficient than simulation-based methods. A semi-probabilistic approach is adopted to develop an assessment model, which consists of a mechanics-based condition (or equation) involving partial factors that are calibrated to a specified reliability level. This approach is applied to develop models for DHC initiation and leak-before-break assessments. A novel feature of the proposed method is that it bridges the gap between a simple deterministic analysis and complex simulations, and it is amenable to practical applications. The nuclear power plant systems are not easily accessible for inspection and data collection due to exposure to high radiation. For this reason, small samples of pressure tubes are inspected at periodic intervals and small sample of data so collected are used as input to probabilistic analysis. The pressure tube flaw assessment is therefore confounded by large sampling uncertainties. Therefore, determination of adequate sample size is an important issue. In this thesis, a risk informed approach is proposed to define sample size requirement for flaw assessment. Notch-tip stress field is a key factor in any flaw assessment model. Traditionally, linear elastic fracture mechanics (LEFM) and its extension, serves the basis for determination of notch-tip stress field for elastic and elastic-perfectly-plastic material, respectively. However, the LEFM solution is based on small deformation theory and fixed crack geometry, which leads to singular stress and strain field at the crack-tip. The thesis presents new models for notch and crack induced stress fields based on the deformed geometry. In contrast with the classical solution based on small deformation theory, the proposed model uses the Cauchy's stress definition and boundary conditions which are coupled with the deformed geometry. This formulation also incorporates the rotation near the crack-tip, which leads to blunting and displacement of the crack-tip. The solution obtained based on the final deformed configuration yields a non-singular stress field at the crack-tip and a non-linear variation of stress concentration factor for both elastic and elastic-perfectly-plastic material. The proposed stress field formulation approach is applied to formulate an analytical model for estimating the threshold stress intensity factor (KIH) for DHC initiation. The analytical approach provides a relationship between KIH and temperature that is consistent with experimental results.

Probabilistic assessment and life cycle management of engineering components and systems in a nuclear power plant is intended to ensure safe and efficient operation of energy generation over its entire life. The CANDU reactor core consists of 380-480 pressure tubes, which are like miniature pressure vessels that contain natural uranium fuel. Pressure tubes operate under severe temperature and radiation conditions, which result in degradation with ageing. Presence of flaws in a pressure tube makes it vulnerable to delayed hydride cracking (DHC), which may lead to rupture or break-before-leak situation. Therefore, assessment of flaws in the pressure tubes is considered an integral part of a reactor core assessment program. The main objective of the thesis is to develop advanced probabilistic and mechanical stress field models for the assessment of flaws. The flaw assessment models used by the industries are based on deterministic upper/lower bound values for the variables and they ignore uncertainties associated with system parameters. In this thesis, explicit limit state equations are formulated and first order reliability method is employed for reliability computation, which is more efficient than simulation-based methods. A semi-probabilistic approach is adopted to develop an assessment model, which consists of a mechanics-based condition (or equation) involving partial factors that are calibrated to a specified reliability level. This approach is applied to develop models for DHC initiation and leak-before-break assessments. A novel feature of the proposed method is that it bridges the gap between a simple deterministic analysis and complex simulations, and it is amenable to practical applications. The nuclear power plant systems are not easily accessible for inspection and data collection due to exposure to high radiation. For this reason, small samples of pressure tubes are inspected at periodic intervals and small sample of data so collected are used as input to probabilistic analysis. The pressure tube flaw assessment is therefore confounded by large sampling uncertainties. Therefore, determination of adequate sample size is an important issue. In this thesis, a risk informed approach is proposed to define sample size requirement for flaw assessment. Notch-tip stress field is a key factor in any flaw assessment model. Traditionally, linear elastic fracture mechanics (LEFM) and its extension, serves the basis for determination of notch-tip stress field for elastic and elastic-perfectly-plastic material, respectively. However, the LEFM solution is based on small deformation theory and fixed crack geometry, which leads to singular stress and strain field at the crack-tip. The thesis presents new models for notch and crack induced stress fields based on the deformed geometry. In contrast with the classical solution based on small deformation theory, the proposed model uses the Cauchy's stress definition and boundary conditions which are coupled with the deformed geometry. This formulation also incorporates the rotation near the crack-tip, which leads to blunting and displacement of the crack-tip. The solution obtained based on the final deformed configuration yields a non-singular stress field at the crack-tip and a non-linear variation of stress concentration factor for both elastic and elastic-perfectly-plastic material. The proposed stress field formulation approach is applied to formulate an analytical model for estimating the threshold stress intensity factor (KIH) for DHC initiation. The analytical approach provides a relationship between KIH and temperature that is consistent with experimental results.