O objetivo dessa dissertação foi analisar a influência de possíveis reações de fusão nuclear quando elementos leves, definidos como alvos são adicionados ao combustível nuclear. A energia cinética dos produtos de fissão, na concepção desse estudo, é utilizada para vencer a repulsão elétrica entre os núcleos. Para esse trabalho foram considerados a adição de hidrogênio, deutério, lítio e berílio em fração mássica de 0,30. A escolha desses elementos foi realizada através da análise da energia de ligação, do número atômico e das seções de choque experimentais de fusão. A avaliação da fusão nuclear foi realizada via principio da incerteza, pois não há um modelo que pudesse cobrir um grande número de reações possíveis. A probabilidade de reação foi aproximada como uma função da probabilidade de um produto de fissão encontrar determinado elemento leve. Adicionalmente foram calculados os tempos de freamento eletrônico para os produtos de fissão com isso verificou-se que a escala de freamento não representa limitação para a fusão. A principal alteração, devido à adição dos alvos, foi na distribuição dos tempos de meia vida dos produtos de fissão, na direção de maiores tempos. A alteração nessa grandeza indica que é possível reduzir a atividade média do rejeito nuclear, em especial o de alto nível de radioatividade, tornando sua manipulação mais segura. Os alvos de hidrogênio e lítio apresentaram os melhores resultados para o aumento do tempo de meia vida médio dos produtos de fissão, conseguindo altera-la em média duas ordens de grandeza. Outras alterações, que não foram alvo desse estudo, são esperadas devido à inserção desses alvos, como por exemplo, na cinética. / The objective of this dissertation was to analyze the influence of possible nuclear fusion reactions when light elements, defined as targets are added to the nuclear fuel. The kinetic energy of the fission products, in the conception of this study, is used to overcome the electrical repulsion between the nuclei. For this work were considered the addition of hydrogen, deuterium, lithium and beryllium in mass fraction of 0.30. The choice of these elements was performed by analyzing the binding energy, the atomic number and experimental fusion cross sections. The assessment of fusion was performed via the uncertainty principle, since there is no model that could cover a large number of possible reactions. The probability of reaction was approximated as a function of the probability of fission product find a particular light element. Additionally times were calculated for the electronic stopping fission products where was found that scale of stopping does not impose limits on fusion. The main change due to the addition of the targets was the distribution of halflives of the fission products, towards longer times. The change in this magnitude indicates that it is possible to reduce the average activity of the nuclear waste, in particular the high level of radioactivity, making handling safer. The targets of hydrogen and lithium showed the best results for increasing the half-life of the average fission products, managing change a on the average of two orders of magnitude. Other modifications, which were not discussed in this study, are expected due to the insertion of these targets, e.g. kinetics.

Made available in DSpace on 2014-10-09T12:31:15Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:31Z (GMT). No. of bitstreams: 1 01361.pdf: 1522307 bytes, checksum: b74e8b9a7d0ad61777cccfdf600d06b8 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:31:22Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:21Z (GMT). No. of bitstreams: 1 01384.pdf: 2416793 bytes, checksum: d7f6d04662fa58ed263bcc98f6c2bb7c (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

O objetivo dessa dissertação foi analisar a influência de possíveis reações de fusão nuclear quando elementos leves, definidos como alvos são adicionados ao combustível nuclear. A energia cinética dos produtos de fissão, na concepção desse estudo, é utilizada para vencer a repulsão elétrica entre os núcleos. Para esse trabalho foram considerados a adição de hidrogênio, deutério, lítio e berílio em fração mássica de 0,30. A escolha desses elementos foi realizada através da análise da energia de ligação, do número atômico e das seções de choque experimentais de fusão. A avaliação da fusão nuclear foi realizada via principio da incerteza, pois não há um modelo que pudesse cobrir um grande número de reações possíveis. A probabilidade de reação foi aproximada como uma função da probabilidade de um produto de fissão encontrar determinado elemento leve. Adicionalmente foram calculados os tempos de freamento eletrônico para os produtos de fissão com isso verificou-se que a escala de freamento não representa limitação para a fusão. A principal alteração, devido à adição dos alvos, foi na distribuição dos tempos de meia vida dos produtos de fissão, na direção de maiores tempos. A alteração nessa grandeza indica que é possível reduzir a atividade média do rejeito nuclear, em especial o de alto nível de radioatividade, tornando sua manipulação mais segura. Os alvos de hidrogênio e lítio apresentaram os melhores resultados para o aumento do tempo de meia vida médio dos produtos de fissão, conseguindo altera-la em média duas ordens de grandeza. Outras alterações, que não foram alvo desse estudo, são esperadas devido à inserção desses alvos, como por exemplo, na cinética. / The objective of this dissertation was to analyze the influence of possible nuclear fusion reactions when light elements, defined as targets are added to the nuclear fuel. The kinetic energy of the fission products, in the conception of this study, is used to overcome the electrical repulsion between the nuclei. For this work were considered the addition of hydrogen, deuterium, lithium and beryllium in mass fraction of 0.30. The choice of these elements was performed by analyzing the binding energy, the atomic number and experimental fusion cross sections. The assessment of fusion was performed via the uncertainty principle, since there is no model that could cover a large number of possible reactions. The probability of reaction was approximated as a function of the probability of fission product find a particular light element. Additionally times were calculated for the electronic stopping fission products where was found that scale of stopping does not impose limits on fusion. The main change due to the addition of the targets was the distribution of halflives of the fission products, towards longer times. The change in this magnitude indicates that it is possible to reduce the average activity of the nuclear waste, in particular the high level of radioactivity, making handling safer. The targets of hydrogen and lithium showed the best results for increasing the half-life of the average fission products, managing change a on the average of two orders of magnitude. Other modifications, which were not discussed in this study, are expected due to the insertion of these targets, e.g. kinetics.

Made available in DSpace on 2014-10-09T12:31:15Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T13:59:31Z (GMT). No. of bitstreams: 1 01361.pdf: 1522307 bytes, checksum: b74e8b9a7d0ad61777cccfdf600d06b8 (MD5) / Dissertacao (Mestrado) / IPEN/D / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Made available in DSpace on 2014-10-09T12:31:22Z (GMT). No. of bitstreams: 0 / Made available in DSpace on 2014-10-09T14:00:21Z (GMT). No. of bitstreams: 1 01384.pdf: 2416793 bytes, checksum: d7f6d04662fa58ed263bcc98f6c2bb7c (MD5) / Tese (Doutoramento) / IPEN/T / Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP

Dans le cadre de la vérification du Traité d'Interdiction Complète des Essais nucléaires (TICE), la mesure des traces de produits de fission dans l'environnement est fondamentale. Ces mesures sont des indicateurs indéniables du caractère nucléaire d'une explosion. Afin d'améliorer ses capacités de mesures, le CEA/DAM-Ile de France s'est équipé d'un nouveau spectromètre de surface. Ce spectromètre, baptisé GAMMA3, est équipé de trois détecteurs au germanium, de deux détecteurs au silicium (intégrés à une cellule de mesure des gaz, la PIPSBox) et d'un blindage optimisé. Ce blindage permet de diminuer très fortement les interférences dues au flux de muons, neutrons ou photons environnementaux. Le bruit de fond radiologique au sein de l'enceinte de mesure est parmi les plus bas rencontrés dans le domaine. Cet ensemble de détecteurs à hautes résolutions énergétiques permet d'optimiser la mesure d'un échantillon suivant son activité, sa géométrie ou sa nature. En particulier, un gaz noble sera mesuré en coïncidence photon/électron, un échantillon actif sera mesuré en coïncidence photon/photon, et un échantillon faiblement actif sera mesuré avec un fort rendement de détection. En combinant ces deux points, les Activités Minimales Détectables requises pour un laboratoire expert du TICE sont atteintes très rapidement. En particulier, elles sont obtenues en 5h pour le 140-Ba (24 mBq), en 6h30 pour les 131m/133m-Xe (5 mBq) et en 7h15 pour le 133-Xe (5mBq) contre les 6 jours réglementaires. / For the verification of the Comprehensive nuclear Test Ban Treaty (CTBT), the measurement of fission products trace levels in the environment is fundamental. Such measurement is a key indicator of a nuclear explosion. For constant amelioration of these measurements, the CEA/DAM-Ile de France has developed and installed a new dedicated surface spectrometer. Named GAMMA3, it is equipped with three germanium detectors, two silicon detectors (integrated in a dedicated gas cell, the PIPSBox) and includes an optimized shielding.This shielding reduces greatly the interference of environmental photons, muons and neutrons with the detectors. The residual radiological background measured inside the shielding is the community’s lowest for a surface laboratory. This set of high energy resolution detectors allows the operator to optimize a measurement according to the sample geometry, activity or nature. More precisely, a radioactive noble gas can be measured by photon/electron coincidence, an active sample can be measured by photon/photon coincidence, and a low-active sample can be measured in a high-efficiency configuration. Combining optimized shielding and optimized measurement, Minimum Detectable Activities required for CTBT certification are obtained quickly. Specifically, MDA is reached in 5 hours for 140-Ba (24 mBq), in 6h30 hours for 131m/133m-Xe (5 mBq) and in 7h15 for 133-Xe (5 mBq), when CTBT requirement is in 6 days.

Pour augmenter les performances des barres de combustible nucléaire, les mécanismes de relâchement des produits de fission (H2, He, Kr, Xe) doivent être étudiés. Ainsi, le département d’étude du combustible du CEA Cadarache a décidé d’améliorer son dispositif expérimental consacré au recuit thermique des combustibles irradiés (MERARG II). La première partie de ce mémoire s'adresse à la mesure du relâchement de gaz de fission de combustibles irradiés et soumis à des transitoire thermiques. Le choix de l'appareil s'est porté sur un analyseur de type filtre quadripolaire du fait des performances requises par le cahier des charges, une identification isotopique du Kr et Xe et des masses 4 et 2 u à la ppm. C'est un spectromètre commercial de type Residual Gaz Analyser, monté dans une enceinte à vide de très faible volume qui a nécessité des adaptations à la ligne de l'expérience MERARG II. Les performances (résolution, sensibilité, vitesse de balayage) du spectromètre ont été évaluées. Le spectromètre calibré est en cours d’installation sur une réplique en zone « froide » de MERARG II.La seconde partie de la thèse concerne des travaux de recherche sur l’adaptation à l’analyse des faibles masses d’un mode opératoire appliqué à un piège à ions RF 3D utilisant un mode par Transformé de Fourier. Nous étudions plus précisément un dispositif d’injection des ions et son mode opératoire afin d’obtenir les distributions en positions et vitesses des ions confinables. La connaissance de ces conditions initiales et de leur dispersion est importante car elles conditionnent la dynamique du signal détecté (la hauteur de la raie) et sa fluctuation, respectivement. / In order to increase fuel rod performances, the basic mechanisms that promote gas (i.e. He, H2, Kr and Xe) release from irradiated nuclear fuels must be studied. In this context, the CEA fuel study department at Cadarache decided to improve its experimental facility devoted to fuel behaviour under thermal transient by modifying the existing annealing device, called MERARG-II.The first part of this dissertation adresses the fuel gas release monitoring from irradiated fuel during thermal transient. The device choice leads to a quadrupole mass filter as mass analyser according to the specification requirement, i.e. isotopic identification of Xe, Kr and masses at 4 and 2 u. It is commercialized Residual Gas Analyser, mounted in a small-volume vacuum chamber requiring adaptations to be connected to the MERARG II line. The resolution and sensitivity of the mass spectrometer have been evaluated. The calibrated device is being installed in MERARG II replica.The second part of this dissertation relates adaptation to low-mass analysis of an RF 3D ion trap operated a Fourier Transform mode. Theoretically, using this operating mode, the lower the mass, the higher the resolution. More particularly, an ion injection device and its operating mode are studied in order to gain position and velocity distributions of confinable ions. The knowledge of these initial conditions is of a great concern as they fix the signal dynamic (peak height) and the signal fluctuation, respectively. This feasibility study, using simulation, allows us to obtain the optimal values of trap operating condition for 1-6 u mass injection and confinement with high resolution.

Independent yield distributions of high-energy neutron-induced fission are of importance to achieve a good understanding of fission. Even though the mass and charge yield distributions of thermal neutron-induced fission are well known, there are few experimental data for high-energy neutron-induced fission. In addition to basic research on the fission process, independent yield distributions of high-energy neutron-induced fission play a key role in the development of Generation IV fast nuclear reactors. To facilitate measurements of independent fission yields of high-energy neutron-induced fission, a dedicated ion guide and a proton-neutron converter were developed and put to use in experiments at the isotope separator facility IGISOL in Jyväskylä. In parallel, a simulation model of the system was developed in order to optimize the collecting efficiency of fission products in the ion guide. The model uses the Monte Carlo code MCNPX to simulate the neutron production, the fission model code GEF to simulate the fission process, and GEANT4 for ion transportation. In order to benchmark the simulation model, metal foils were inserted in the ion guide with the purpose of collecting fission products. At the same time, nickel, cobalt and indium foils were located between the pn-converter and the ion guide to record the neutron flux from the pn-converter. After the beam was turned off, and after several days of cooling, g-ray spectroscopy measurements of the foils were conducted using a well shielded HPGe detector. Based on the identified g-ray transitions in the spectroscopy data, the productions of corresponding fission products and neutron activation products were calculated, and then used to benchmark the transportation and collection of fission products, as well as neutron production, in the simulations. The conclusion from the benchmark is that the transportation of fission products in the helium gas, as simulated by GEANT4, agrees very well with the measurement, while the transportation of fission products in the uranium targets agrees with the measurement within 10%. The neutron flux at the high-energy part of the neutron spectrum is overestimated by about 40%.Thanks to the benchmark it has been shown that the predictive power of the model is satisfactory and sufficient for the purpose of modeling the ion guide. Furthermore, the parameters involved in the simulations, such as neutron production, distance between the neutron source and the ion guide, volume of the ion guide and so on, play an important role in the optimization of the setup. However, the lower than expected fission rate suggests that the optimization on these parameters may not be enough to achieve a sufficiently high intensity of fission products, especially for nuclei far from the stability line. To achieve a sufficiently high intensity, an electric field guidance, similar to the RF structure of the CARIBU gas catcher presented in G.Savard et al. Nucl. Inst. Meth. B, 376: 246, 2016, to collect fission products is considered.

When a pressurized water reactor is operated for a sufficiently long period of time, a small number of fuel rods will develop ruptures in their claddings. These defects will leak volatile fission products into the primary coolant, including radioactive iodine. During steady-state operation of the reactor a low level iodine activity is thus present in the coolant. Initiation of a down-power or up-power transient will result in a rapid climb in the activity of the iodine which peaks at a level much higher than the initial activity. After this time the activity levels out and then slowly begins to decay back to a new steady-state level. This phenomenon is termed "iodine spiking.” A physical model of this process is sought for explanatory and predictive purposes. A FORTRAN code is developed that solves a system of differential equations which describe the production and removal of iodine in the fuel, gap region, and primary coolant. As much physics as possible is employed but some complicated diffusion processes have led to the utilization of certain parametric results obtained from empirical data. Actual PWR spiking data is also employed for comparison and adjustment of the model. It is the goal of this project to be able to utilize the model for predictive analysis· during actual PWR operation so that a better understanding of iodine spiking behavior can be obtained. / Master of Science