Boschetti, Facundo N. (2013) Diseño conceptual de reactor de investigación con combustible con hidrógeno. / Conceptual Design of Research Reactor with Hydrogenated Fuel. Proyecto Integrador Ingeniería Nuclear, Universidad Nacional de Cuyo, Instituto Balseiro.
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Resumen en español
La experiencia reunida a partir de los combustibles TRIGA® y la correcta interpretación de su mecanismo de pérdida de moderación conforme aumenta la temperatura del mismo, permite considerar la posibilidad de emplear hidruro de zirconio como moderador en elementos combustible de diseño tipo placa para reactores de investigación. En este trabajo se presentan distintos diseños de combustibles MTR, procediéndose a analizar en cada caso la relación entre las dimensiones características de los mismos y la de las distintas variables en juego con el obje-tivo de obtener coeficientes de potencia y temperatura en el combustible semejantes a los presentes en los diseños TRIGA®. Se procedió asimismo a efectuar un detallado estudio de los materiales y combustibles nucleares involucrados en los diseños propuestos de forma tal de poder distinguir fortalezas y debilidades en cada uno de ellos, más allá de los resultados a nivel de cálculo de celda relativo a sus respectivos coeficientes. Para poder llevar a cabo los análisis previos se debió validar la línea de cálculo neutrónica Condor-Citvap, con-juntamente con la biblioteca de secciones eficaces HELIOS. Esto requirió la reproducción de configuraciones críticas y experiencias de incremento de potencia en un reactor TRIGA®. La información reunida al respecto demuestra la necesidad de aunar esfuerzos en la correcta determinación de las secciones eficaces microscópi-cas del hidrógeno y zirconio en la estructura cristalina del hidruro correspondiente. Finalmente los estudios preliminares realizados en el presente trabajo muestran la potencial capacidad de obtener coeficientes de reactividad como los planteados previamente, con diseños compatibles con las geo-metrías y dimensiones de los combustibles tipo placa actuales. Las tendencias presentes han llevado a analizar la posibilidad de emplear combustibles monolíticos a base de uranio-molibdeno más allá de los combustibles dispersos a base de siliciuro de uranio; los resultados empleando esta primer aleación (U-Mo) han sido de par-ticular interés no solo desde el punto de vista de lo que a coeficientes de reactividad le compete sino también desde el punto de vista de la apertura de nuevos caminos en lo que concierne a fabricación de elementos combustibles para reactores MTR.
Resumen en inglés
The experience gathered from TRIGA ® fuel elements and the correct interpretation of their mechanism of loss of moderation as the temperature increases, allows us to consider the possibility of using zirconium hydride as moderator in the design of plate-type fuel elements for research reactors. In this paper we present different designs of MTR fuels, analyzing in each case the relationship between the characteristic dimensions of them and that of the different variables involved, in order to get power and fuel temperature reactivity coefficients similar to those present in TRIGA ® designs. A detailed study of nuclear fuels and materials involved in the proposed fuel elements was made, with the goal of distinguish strengths and weaknesses in each of them coming from this area, instead of studying only their respective coefficients that result from a cell calculation. To carry out the studies it was necessary to validate previously Condor-Citvap neutron calculation line, in con-junction with the library of cross sections HELIOS. This required the reproduction of critical configurations and experiences of power increase coming from a TRIGA® reactor. The information collected demonstrates the necessity of making an effort in the correct determination of the microscopic cross sections of hydrogen and zirconium in the crystal structure of the zirconium hydride. Finally, preliminary studies in this paper show the potential ability to obtain reactivity coefficients such as those coming from TRIGA® experience, with designs compatible with the geometries and dimensions of the current plate-type fuels. Present trends have led to analyze the possibility of using fuels based on monolithic molybdenum uranium beyond dispersed uranium silicide fuels; results using this first alloy (U-Mo) have been of particular interest, not only from the point of view of reactivity coefficients but also from the point of view of the initiation of new paths in regard to manufacturing MTR fuel elements.
| Tipo de objeto: | Tesis (Proyecto Integrador Ingeniería Nuclear) |
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| Palabras Clave: | Zirconium hydrides; Hidruros de circonio; Research reactors; Reactores de investigación; Materials; Materiales; Fuels; Combustibles; MTR reactor; Reactor MTR; Plate-type fuel element; Combustible tipo placa |
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| Materias: | Ingeniería nuclear Ingeniería nuclear > Componentes y consideraciones de diseño de reactores |
| Divisiones: | INVAP |
| Código ID: | 427 |
| Depositado Por: | Marisa G. Velazco Aldao |
| Depositado En: | 11 Mar 2014 14:22 |
| Última Modificación: | 11 Mar 2014 14:22 |
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