Análisis y desarrollo de recubrimientos electrodepositados de CR sobre ZRY-4 para combustibles de tecnología avanzada (ATF)
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Comisión Nacional de Energía Atómica. Gerencia de Área Académica. Gerencia Instituto de Tecnología Nuclear Dan Beninson
Universidad Nacional San Martin. Instituto de Tecnología Nuclear Dan Beninson
Universidad Nacional San Martin. Instituto de Tecnología Nuclear Dan Beninson
Resumen
En el año 2011 un terremoto seguido de un tsunami en Japón derivó en el accidente de la central nuclear de Fukushima Daiichi. Esto causó que el interés internacional se oriente a investigar variaciones que se puedan realizar en los combustibles para mejorar su funcionalidad en caso de un evento de este tipo. Estas investigaciones se orientan principalmente en las vainas y pastillas combustibles. Las aleaciones de circonio han sido extensamente utilizadas como material de las vainas combustible en reactores nucleares. Esto se debe a su baja absorción de neutrones térmicos, a la excelente resistencia a la corrosión y a la capacidad de mantener sus propiedades mecánicas estables en condiciones de elevada temperatura. Si bien, el Zry – 4 es la aleación más ampliamente utilizada en reactores de agua presurizada (PWR), se ha reportado que las vainas de Zry – 4 pueden experimentar fallas como consecuencia de la corrosión, produciendo una reducción en la vida útil de la vaina combustible. En caso de accidentes como un LOCA (perdida de refrigerante), la elevada temperatura acelera el proceso de corrosión de la aleación, promoviendo reacciones de formación de hidrógeno altamente exotérmicas, dando lugar a un exceso de calor, que junto con la producción de hidrógeno puede dañar el combustible y el núcleo del reactor, presentando un escenario de difícil control. A partir de esto, uno de los objetivos de las investigaciones, se ha dirigido hacia el estudio de nuevos materiales que inducen mejoras en las vainas combustibles. La clave de estos desarrollos es aumentar la resistencia a la corrosión en altas temperaturas de este tipo de aleaciones por medio de diferentes técnicas, a partir de estos avances y como consecuencia del accidente ocurrido en Fukushima, los nuevos estudios evolucionaron hacia el análisis de materiales para combustibles que cumplieran la condición de ser más tolerantes en situaciones de accidentes, denominándose a estos Accident Tolerant Fuel (ATF), actualmente denominados Combustibles de Tecnología Avanzada. En este trabajo, se estudia la influencia de recubrimientos electrodepositados sobre una superficie de Zry–4 y su comportamiento frente a la acción corrosiva en medio ácido. Esos recubrimientos fueron caracterizados por microscopía electrónica de barrido (SEM), donde se analizó la morfología y las fases presentes en los films, formados por electroquímica en diferentes condiciones a fin de determinar su espesor y su influencia en la resistencia a la corrosión
In 2011, an earthquake followed by a tsunami in Japan led to the accident at the Fukushima Daiichi nuclear power plant. This caused international interest to focus on research into variations that could be made in fuels, to improve their functionality in the event of this kind. This research is mainly focused on fuel cladding and fuel pellets. Zirconium alloys have been extensively used as fuel cladding material in nuclear reactors. This is due to their low thermal neutron absorption, excellent corrosion resistance and ability to maintain their stable mechanical properties under elevated temperature conditions. Although Zry-4 is the most widely used alloy in pressurized water reactors (PWRs), it has been reported that Zry-4 cladding can experience failures as a result of corrosion, leading to a reduction in fuel cladding life. In case of accidents, such as a LOCA (loss of coolant accident) the high temperature accelerates the corrosion process of the alloy, promoting highly exothermic hydrogen formation reactions, resulting in excess heat, which together with hydrogen production can damage the fuel and the reactor core, presenting a scenario that is difficult to control. As a result, one of the research objectives has been directed towards the study of new materials that induce improvements in fuel cladding. The key of these developments is to increase the high temperature corrosion resistance of this type of alloys by means of different techniques. From these advances and as a consequence of the Fukushima accident, new studies evolved towards the analysis of materials for fuels, that fulfill the condition of being more tolerant in accident situations, being called Accident Tolerant Fuel (ATF), currently known as Advanced Technology Fuels. In this work, the aim was to study the influence of electrodeposited coatings on a Zry-4 surface and its behavior against corrosive action in acid medium. These coatings were characterized by scanning electron microscopy (SEM), where the morphology and the phases present in the films, formed by
In 2011, an earthquake followed by a tsunami in Japan led to the accident at the Fukushima Daiichi nuclear power plant. This caused international interest to focus on research into variations that could be made in fuels, to improve their functionality in the event of this kind. This research is mainly focused on fuel cladding and fuel pellets. Zirconium alloys have been extensively used as fuel cladding material in nuclear reactors. This is due to their low thermal neutron absorption, excellent corrosion resistance and ability to maintain their stable mechanical properties under elevated temperature conditions. Although Zry-4 is the most widely used alloy in pressurized water reactors (PWRs), it has been reported that Zry-4 cladding can experience failures as a result of corrosion, leading to a reduction in fuel cladding life. In case of accidents, such as a LOCA (loss of coolant accident) the high temperature accelerates the corrosion process of the alloy, promoting highly exothermic hydrogen formation reactions, resulting in excess heat, which together with hydrogen production can damage the fuel and the reactor core, presenting a scenario that is difficult to control. As a result, one of the research objectives has been directed towards the study of new materials that induce improvements in fuel cladding. The key of these developments is to increase the high temperature corrosion resistance of this type of alloys by means of different techniques. From these advances and as a consequence of the Fukushima accident, new studies evolved towards the analysis of materials for fuels, that fulfill the condition of being more tolerant in accident situations, being called Accident Tolerant Fuel (ATF), currently known as Advanced Technology Fuels. In this work, the aim was to study the influence of electrodeposited coatings on a Zry-4 surface and its behavior against corrosive action in acid medium. These coatings were characterized by scanning electron microscopy (SEM), where the morphology and the phases present in the films, formed by
