<p> A new technique has be~n developed for the measurement of fast neutron total cross-sections in the range 0.8 -> 3.0 MeV using the fast neutrons from a reactor. The method was used to obtain the cross-section of six elements in the 2s-1d shell. Various analytical techniques have been applied to measure the behavior of the average cross-sections and delineate the properties of the observed resonances. From these results the resonances are confirmed as examples of "doorway" states, and conclusions are drawn about the distributions of the parameters of these states. The average properties are related to nuclear models of the origin and characteristics of states of high excitation in the target nuclides.</p> / Thesis / Doctor of Philosophy (PhD)

No description available.

A heavily filtered fast neutron irradiation system (FNIS) was developed for a variety of applications, including the study of long-term health effects of fast neutrons by evaluating the biological mechanisms of damage in cultured cells and living animals such as rats or mice. This irradiation system includes an exposure cave made with a lead-bismuth alloy, a cave positioning system, a gamma and neutron monitoring system, a sample transfer system, and interchangeable filters. This system was installed in the irradiation cell of the Texas A&M University Nuclear Science Center Reactor (NSCR). By increasing the thickness of the lead-bismuth alloy, the neutron spectra were shifted into lower energies by the scattering interactions of fast neutrons with the alloy. It is possible, therefore, by changing the alloy thickness, to produce distinctly different dose weighted neutron spectra inside the exposure cave of the FNIS. The calculated neutron spectra showed close agreement with the results of activation foil measurements, unfolded by SAND-II close to the cell window. However, there was a considerable less agreement for locations far away from the cell window. Even though the magnitude of values such as neutron flux and tissue kerma rates in air differed, the weighted average neutron energies showed close agreement between the MCNP and SAND-II since the normalized neutron spectra were in a good agreement each other. A paired ion chamber system was constructed, one with a tissue equivalent plastic (A-150) and propane gas for total dose monitoring, and another with graphite and argon for photon dose monitoring. Using the pair of detectors, the neutron to gamma ratio can be inferred. With the 20 cm-thick FNIS, the absorbed dose rates of neutrons measured with the paired ion chamber method and calculated with the SAND-II results were 13.7 ?? 0.02 Gy/min and 15.5 Gy/min, respectively. The absorbed dose rate of photons and the gamma contribution to total dose were 6.7??10-1 ?? 1.3??10-1 Gy/min and 4.7%, respectively. However, the estimated gamma contribution to total dose varied between 3.6 % to 6.6 % as the assumed neutron sensitivity to the graphite detector was changed from 0.01 to 0.03.

Ce travail de thèse poursuit l’objectif d’une simulation numérique multiéchelle d’un assemblage de réacteur à neutrons rapides. Malgré la puissance croissante des ordinateurs, la CFD fine complète d’un tel système demeure extrêmement coûteuse dans un contexte de recherche et développement. Nous proposons alors, une fois déterminé le comportement thermohydraulique moyen de l’assemblage, de reconstruire localement l’information aux fines échelles, l’ensemble de la démarche requérant un temps de calcul bien moindre qu’une simulation de la totalité de la structure. La description à l’échelle moyenne est obtenue soit par le formalisme de prise de moyenne volumique en milieu poreux, soit via une approche alternative historiquement développée pour les assemblages de RNR-Na. Elle fournit des informations utilisées comme contraintes d’un sous-problème de raffinement d’échelle, par l’intermédiaire d’une technique de pénalisation des équations de conservation locales. Ce sous-problème exploite le caractère périodique de la structure en s’appuyant sur des conditions aux limites de périodicité des champs recherchés ou de leur déviation spatiale. Après validation des méthodologies sur des applications modèles, nous entreprenons leur mise en oeuvre sur des configurations « industrielles » qui démontrent la viabilité de cette approche multiéchelle. / The present work is devoted to a multiscale numerical simulation of an assembly of fast neutron reactor. In spite of the rapid growth of the computer power, the fine complete CFD of a such system remains out of reach in a context of research and development. After the determination of the thermalhydraulic behaviour of the assembly at the macroscopic scale, we propose to carry out a local reconstruction of the fine scale information. The complete approach will require a much lower CPU time than the CFD of the entire structure. The macroscale description is obtained using either the volume averaging formalism in porous media, or an alternative modeling historically developed for the study of fast neutron reactor assemblies. It provides some information used as constraint of a downscaling problem, through a penalization technique of the local conservation equations. This problem lean on the periodic nature of the structure by integrating periodic boundary conditions for the required microscale fields or their spatial deviation. After validating the methodologies on some model applications, we undertake to perform them on “industrial” configurations which demonstrate the viability of this multiscale approach.

Cette thèse contribue au remplacement du revêtement de Stellite 6 utilisé aux zones de frottement dans le circuit primaire du réacteur à neutron rapide. Elle comprend trois parties : 1) Une étude bibliographique afin de présider au choix des matériaux de remplacement et du procédé de dépôt. 2) Une étude paramétrique en vue d’obtenir des dépôts sains (bonne adhésion avec le substrat, peu de porosité, absence de fissure, dilution faible). 3) Une étude du comportement tribologique des dépôts réalisée pour deux valeurs de température. Ces essais tribologique ont été réalisés sous atmosphère inerte afin d’évaluer la résistance à l’usure des matériaux choisis sans l’influence d’une éventuelle couche d’oxydation. De l’étude bibliographique il ressort les choix suivants mis en oeuvre dans notre étude : * le procédé projection laser qui présente des avantages tels que :- Bonne adhésion (métallurgique)- Vitesse de refroidissement élevée- Taux de dilution faible- Large plage paramétrique *deux alliages base nickel : le Colmonoy-52 et le Tribaloy-700. Ces alliages présentent un bon comportement tribologique à sec et sont déposables par laser.Pour la partie obtention d’un dépôt sain, tout d’abord nous avons caractérisé la poudre métallique. Ensuite, une recherche paramétrique a été conduite afin de disposer d’un jeu de paramètres qui permette d’obtenir un dépôt sain de Stellite 6 (référence), de Colmonoy-52 et de Tribaloy-700. A cette occasion, les relations entre trois paramètres principaux du procédé de projection laser (puissance du faisceau laser, vitesse de balayage de la surface, débit de poudre) ont été investigués en relation avec la microstructure et la composition chimique finale du dépôt.Lors de l’étude tribologique, un tribomètre de type pion-disque a été utilisé et les essais de frottement ont été réalisés sous atmosphère d’argon, à température ambiante et à 200°C. Les mécanismes d’usure ont été identifiés pour les 3 matériaux et leur contre pièce (bille en AISI 316L). Les volumes usés ont quant à eux été analysés en fonction de la charge appliquée et l’effet de la température. / This thesis contributes to the replacement of the coating of Stellite 6 which is used in friction areas for the primary circuit of the reactor fast neutron.It contains three parts:1) A literature review for selecting the materials and the deposition process2) A parametric study to get healthy deposits (good adhesion with the substrate, little porosity, no cracks, low dilution)3) A study wear behavior of deposits obtained, at high temperature (200°C) under an atmosphere inert gas, to determine the wear resistance of materials selected without the influence of an eventual oxidation layer.From the literature review, it appears the following choices implemented in our study : * the method laser cladding with advantages such as: - Good adhesion (metallurgical) - High cooling speed - Low dilution rate - Wide parametric range * two nickel-based alloys: Colmonoy-52 and Tribaloy-700. These alloys have good dry wear behavior and could be deposited by the laser. In the manufacturing part of the healthy deposit, firstly, we characterized the metal powder. Then, a parametric study was performed to look for a good parametric range that makes us getting a healthy deposit of Stellite 6 (reference) of Colmonoy-52 and Tribaloy-700. In this case, relationships among three main process parameters laser cladding (laser beam power, surface scanning speed, rate of powder) with the microstructure and chemical composition of the deposit are studied. In study the wear behavior, a pin-on-disc type of tribological was used and tests were carried out in argon at room temperature and 200°C. We investigated the wear mechanism of the best deposition of Stellite 6, Colmonoy-52 and Tribaloy-700. The wear resistance of these materials were thourghly compared.

Dynamic flow of material has been studied using fast neutron radiography (FNR) and positron emission particle tracking (PEPT). A new fast neutron imaging system was commissioned at The South African Nuclear Energy Corporation, Pretoria, as part of this study, although FNR measurements were ultimately performed at PhysikalischTechnische Bundesanstalt (PTB), Braunschweig. The PEPT studies were undertaken at the PEPT Cape Town facility located at iThemba LABS, Cape Town. The steady state motion of media, within a laboratory-scale tumbling mill, was studied for a range of speed and media mixes, using both FNR and PEPT. Several operational parameters were derived from the data, which could be related to potential improvements to the milling efficiency. The blending of FNR and PEPT data for the study of steady state flow, was explored for the first time. In addition, the flow of water through porous media was studied using FNR, which enabled the determination of the hydraulic conductivity, and hence intrinsic permeability, of the media within the column. The potential of using FNR, without or without PEPT, for the study of material in motion is discussed.

Thesis (MSc)--Stellenbosch University, 2012. / ENGLISH ABSTRACT: Nine 100x100x600 mm3 plastic scintillators, formerly built for the neutron time of ight measurements at iThemba LABS, were refurbished. The position resolution of these detectors was determined using muon cosmic rays and coincident measurement techniques. Average position resolution of 4.28 cm (FWHM) was found. In order to predict the time spectrum of the large-volume detector Monte Carlo simulations have been performed. These simulations aimed at anticipating the separation of statistical neutrons, prompt gamma rays and uncorrelated gamma rays from the fast neutrons emitted in the reaction of interest. One of the neutron detectors was tested using fast neutrons from the 232Th( ,xn) reaction at 42 MeV. Statistical neutrons from fusion evaporation reactions were produced in 152Sm(12C,xn) fusion evaporation reaction. Coincidences between neutrons and gamma rays were successfully identi ed. Prompt gamma rays and uncorrelated gamma rays were also identi ed. / AFRIKAANSE OPSOMMING: Nege 100x100x600 mm3 plastiese scintillators, wat aanvanklik gebou was vir neutron vlugtyds meetings by iThemba LABS, was hernu. Die posisie resolusie van die detektore was bepaal deurmiddel van muon kosmiese straling en koïnsidensie meet tegnieke. Posisie resolusie van 4.28 cm (FWHM) was verkry. Monte Carlo simulasies is gebruik om die posisie resolusie van'n groot volume detektor te voorspel. Hierdie simulasies is daarop gemik om onderskeid te maak tussen statistiese neutrone, gelyktydige gamma strale en ongekorreleerde gamma strale vanaf vinnige neutrone in die reaksie van belang uitgestraal word. Een neutron detektor was getoets deur gebruik te maak van vinnige neutrone wat uit die reaksie 232Th( ,xn) by 42 MeV ontstaan. Statistiese neutrone vanaf splitsings verdampingsreaksies, gelyktydige gamma strale en ongekorreleerde gamma strale was geidenti seer. Statistiese neutrone van samesmelting verdamping reaksies was geproduseer in die reaksie 152Sm(12C,xn). Toeval tussen neutrone en gamma strale was suksesvol geïdenti seer, gevra gamma strale en ongekorreleerd gamma strale was ook geïdenti seer.

Two measurements have been made, addressing gaps in knowledge for 235U(n,f) and 238U(n,f). The energy distribution for prompt fission neutrons is not well-understood below 1 MeV in 235U(n,f). To measure the 235U(n,f) prompt fission neutron distribution, a pulsed neutron beam at the WNR facility in Los Alamos National Laboratory was directed onto a 235U target with neutron detectors placed 1 m from the target. These neutron detectors were designed specifically for this experiment and employed a unique geometry of scintillating plastic material that was designed to reject backgrounds. Fission fragments were detected using an avalanche counter. Coincidences between fission fragment production and neutron detector events were analyzed, using a double time-of-flight technique to determine the energy of the prompt fission neutrons. A separate measurement was made, investigating the neutron-induced fission cross section for 238U(n,f). This measurement also used the pulsed neutron beam at the WNR facility. The neutron flux was normalized to the well-known hydrogen standard and the fission rate was observed for beam neutrons in the energy range of 130-300 MeV. Using an extrapolation technique, the energy dependence of the cross section was determined. These new data filled a sparsely populated energy region that was not well-studied and were measured relative to the hydrogen standard, unlike the majority of available data. These data can be used to constrain the fission cross section, which is considered a nuclear reaction standard.

Ce travail de thèse porte sur le développement de techniques de spectroscopie neutronique dans les champs de rayonnement mixte pour des applications liées aux réacteurs de recherche à neutrons rapides, en particulier l’installation MASURCA.La première partie est consacrée à l'étude des configurations expérimentales spéciales de MASURCA dans lesquelles un canal radial est construit pour extraire un faisceau continu de neutrons d'énergie intermédiaires et rapides, adaptable à différents besoins. Exploiter MASURCA en tant qu'installation de faisceau de neutrons ouvrirait de nouvelles possibilités d'expériences telles que des expériences de protection et de transport de neutrons rapides, la production de champs neutroniques standards (de référence), le développement et étalonnage de systèmes de détection des neutrons rapides, etc.La deuxième partie de la thèse est dédiée au développement d’une capacité de spectrométrie neutronique rapide pour la caractérisation en ligne de la distribution d'énergie neutronique. Différents types de détecteurs sont comparés. Le meilleur compromis pour ce spectromètre est un système combinant des compteurs proportionnels et des scintillateurs organiques. Ce système est capable de couvrir le domaine énergétique entre 10 keV et 10 MeV. Le scintillateur organique sélectionné est un monocristal de stilbène obtenu par un procédé “solution-grown” développé récemment. Au bilan, on conclut qu'un spectromètre à neutrons basé sur le stilbène de type “solution-grown” serait adapté à une utilisation dans MASURCA et dans d'autres champs de rayonnement mixte et qu'il serait plus performant que les systèmes de détection traditionnels. / This doctoral thesis work is focused on the development of neutron spectroscopy techniques in mixed radiations fields for fast research reactor applications, especially for the MASURCA facility.The first part of the thesis is dedicated to the study of special MASURCA configurations in which a radial channel is built to extract a continuous beam of intermediate-to-fast energy neutrons, tailorable to meet different needs. Operating MASURCA as a neutron beam facility would open up new possibilities of experiments, such as fast neutron attenuation and shielding experiments; measurements in standard (reference) fast neutron fields, development and calibration of fast neutron detection systems etc.The second part of the thesis is dedicated to the development of fast neutron spectrometric capabilities for the on-line characterization of the neutron energy distribution. Different candidate detector systems are compared. A “best compromise” spectrometer is shown to be a system combining proportional counters and organic scintillators. Such a system would be able to cover the neutron energy domain between 10 keV and 10 MeV. The selected organic scintillator is a stilbene single crystal obtained by a recently developed solution-grown process. Overall, it is concluded that a neutron spectrometer based on a solution-grown stilbene detector would be suitable for use in MASURCA and in other mixed radiations fields, and would perform better than traditional detector systems.

No description available.