No description available.

<p>High power fusion plasmas produced in the world’s largest facility for magnetic confinement experiments (JET), have been studied using the neutron emission measured with the magnetic proton recoil (MPR) spectrometer. The MPR has been used to observe plasmas since 1996 including those of deuterium-tritium leading to several fusion records and corresponding observational achievements of neutron emission spectroscopy. Noteworthy are novel studies of the complex states of fuel ions arising through plasma heating by neutral beam (NB) injection and radio frequency (RF) power.</p><p>This thesis concerns the analysis of MPR data on the neutron emission from NB heated discharges alone and in combination with RF. A main objective of these studies has been the effect of supra-thermal fuel ion reactions on the fusion power as compared to the basic thermal component. The analysis was based on dedicated models to describe the velocity distributions of the ion population under the influence of the NB and RF heating in a parametric form allowing trial neutron spectra to be calculated and fitted to the data to select the kinetic state of the fuel ions that best described the MPR observations.</p><p>Spectral signatures of different underlying plasma states and phenomena were identified and results from up to five different ion reaction contributions to the fusion power were demonstrated besides the global plasma features of toroidal rotation. Moreover, the thesis presents examples of derived detailed plasma information from MPR data such as the kinetic energy densities for the thermal and supra-thermal parts of the fuel ion population as well as the synergetic coupling of RF power to the fast ions from NB injection. The results constitute a stepping-stone for neutron emission spectroscopy as a main diagnostic for ITER and other future fusion experiments on thermonuclear ignition.</p>

High power fusion plasmas produced in the world’s largest facility for magnetic confinement experiments (JET), have been studied using the neutron emission measured with the magnetic proton recoil (MPR) spectrometer. The MPR has been used to observe plasmas since 1996 including those of deuterium-tritium leading to several fusion records and corresponding observational achievements of neutron emission spectroscopy. Noteworthy are novel studies of the complex states of fuel ions arising through plasma heating by neutral beam (NB) injection and radio frequency (RF) power. This thesis concerns the analysis of MPR data on the neutron emission from NB heated discharges alone and in combination with RF. A main objective of these studies has been the effect of supra-thermal fuel ion reactions on the fusion power as compared to the basic thermal component. The analysis was based on dedicated models to describe the velocity distributions of the ion population under the influence of the NB and RF heating in a parametric form allowing trial neutron spectra to be calculated and fitted to the data to select the kinetic state of the fuel ions that best described the MPR observations. Spectral signatures of different underlying plasma states and phenomena were identified and results from up to five different ion reaction contributions to the fusion power were demonstrated besides the global plasma features of toroidal rotation. Moreover, the thesis presents examples of derived detailed plasma information from MPR data such as the kinetic energy densities for the thermal and supra-thermal parts of the fuel ion population as well as the synergetic coupling of RF power to the fast ions from NB injection. The results constitute a stepping-stone for neutron emission spectroscopy as a main diagnostic for ITER and other future fusion experiments on thermonuclear ignition.

No abstract provided. / Thesis / Master of Science (MSc) / Scope and contents: The probability of fission as a function of primary fragment velocities has been obtained by removing the neutron emission and instrumental dispersions from the velocities determined by Stein with time-of-flight techniques for the thermal neutron fission of u235. Each velocity was increased by 0.69% to make the average kinetic energy per fission agree with the calorimetric value of 167.1 Mev. Excitation energy distributions were obtained by using the primary fragment masses given by Cameron and assuming that the most probable charge distribution for a given mass ratio i s that which leads to the greatest energy release. Evaporation theory was used to determine the number of prompt neutrons emitted. When the excitation energy is divided equally between the fragments and a nuclear temperature of 0.59 Mev is used, the average number of neutrons emitted is 2.95 per fission.

L'objectif de cette thèse est d'explorer les mécanismes d'émission des neutrons émis lors du processus de la fission. En particulier, la question ouverte de l'existence d'une anisotropie dynamique dans le centre de masse des fragments de fission et/ou de la possibilité d'une émission de neutrons de scission est explorée. La thèse débute par une introduction aux concepts théoriques permettant de décrire les processus de fission et les mécanismes d'émission de neutrons. La nécessité de concevoir une méthode d'analyse appropriée pour caractériser des mécanismes très subtiles est discutée, en insistant sur l'importance de maîtriser les biais expérimentaux. Le travail effectué a exigé un effort important de simulation, à travers le développement d'une procédure Monte Carlo pour décrire la fission spontanée du 252Cf, ainsi qu'une modélisation du dispositif expérimental de l'expérience CORA3.Nous proposons pour la première fois une approche simultanée et indépendante des deux mécanismes, émission de scission et anisotropie dynamique, ainsi que des valeurs quantitatives d'anisotropie et d'émission de scission mesurées expérimentalement. / The subject of this thesis is to explore the neutron emission mechanisms in the fission process. In particular a long standing open question, the existence of a dynamical anisotropy in the centre of mass of the fission fragments and/or a possible scission neutron emission is explored. The thesis starts with an overview of the theoretical concepts on the fission process and on the neutron emission mechanisms. Also the necessity to conceive an appropriate analysis method is stressed when a very subtle mechanism is studied as various approximations and/or experimental biases not completely handled can hide the physical phenomena. In the presented work a huge effort was required to write a Monte Carlo procedure based on a coherent model for the spontaneous fission of 252Cf and to couple it with the devices exploited in the CORA3 experiment.

No description available.

Made available in DSpace on 2014-10-09T12:42:16Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:21Z (GMT). No. of bitstreams: 0 / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:54:05Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:02Z (GMT). No. of bitstreams: 1 12444.pdf: 2861377 bytes, checksum: f197a83330e61c5fa6654676c3363a7f (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Fisica, Universidade de Sao Paulo - IF/USP

Made available in DSpace on 2014-10-09T12:42:16Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:05:21Z (GMT). No. of bitstreams: 0 / Doses absorvidas e doses efetivas podem ser calculadas utilizando códigos computacionais de transporte de radiação. A qualidade desses cálculos depende dos dados nucleares, no entanto, são raras as informações sobre as diferenças nas doses causadas por diferentes bibliotecas. O objetivo desse estudo é comparar os valores de dose (absorvida e efetiva) obtidos utilizando diferentes bibliotecas de dados nucleares devido a uma fonte externa de nêutrons na faixa de 10-11 a 20 MeV. As bibliotecas de dados nucleares são: JENDL 4.0, JEFF 3.1.1 e ENDF/B-VII.0. Cálculos de doses foram realizados utilizando o código MCNPX considerando o modelo antropomórfico da ICRP-110. As diferenças nos valores das doses absorvidas utilizando as bibliotecas JEFF 3.1.1 e a ENDF/B.VII são pequenas, em torno de 1%, porém os resultados obtidos com a JENDL 4.0 apresentam diferenças de até 85 % compara aos resultados da ENDF/B-VII.0 e JEFF 3.1.1. Diferenças nas doses efetivas são em torno de 1,5% entre ENDF/B-VII.0 e JEFF 3.1.1, e 11 % entre ENDF/B-VII.0 e JENDL 4.0. / Dissertação (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN-CNEN/SP

Made available in DSpace on 2014-10-09T12:54:05Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:09:02Z (GMT). No. of bitstreams: 1 12444.pdf: 2861377 bytes, checksum: f197a83330e61c5fa6654676c3363a7f (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Fisica, Universidade de Sao Paulo - IF/USP