Reprocessed fuels in a PWR SMR based on NuScale
[EN] This work evaluated reprocessed fuels in a core model based on a NuScale, a PWR Small Modular Reactor (SMR). With a model starting from the equilibrium core, this work suggests the replacement of fresh UO2 fuel with reprocessed fuels. It evaluated two types of reprocessed fuels: spiked with tho...
| Autores: | , , , , , , , |
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| Tipo de recurso: | artículo |
| Fecha de publicación: | 2025 |
| País: | España |
| Institución: | Universitat Politècnica de València (UPV) |
| Repositorio: | RiuNet. Repositorio Institucional de la Universitat Politécnica de Valéncia |
| Idioma: | inglés |
| OAI Identifier: | oai:riunet.upv.es:10251/219980 |
| Acceso en línea: | https://riunet.upv.es/handle/10251/219980 |
| Access Level: | acceso embargado |
| Palabra clave: | SMR PWR Burnup simulation Power distribution Reprocessed fuel GANEX 01.- Erradicar la pobreza en todas sus formas en todo el mundo 13.- Tomar medidas urgentes para combatir el cambio climático y sus efectos |
| Sumario: | [EN] This work evaluated reprocessed fuels in a core model based on a NuScale, a PWR Small Modular Reactor (SMR). With a model starting from the equilibrium core, this work suggests the replacement of fresh UO2 fuel with reprocessed fuels. It evaluated two types of reprocessed fuels: spiked with thorium and spiked with depleted U (0.2%). The main aim is to analyze the core burnup process with reprocessed fuels inserted in some assemblies and analyze the depleted spent fuel composition, multiplication factor during burnup, power distribution, leakage, and core activity. The core was modeled and simulated using the MC code SERPENT 2.2.1. As expected, the activity values for the models with reprocessed fuels are higher. The model with thorium has the highest activity and leakage. The keff s during burnup are higher for reprocessed fuels, which could lead to an extension of the burnup. The change in power distribution is minimal. It is necessary to advance the evaluation of reprocessed fuels to ensure a better destination for radioactive waste, as well as a better destination for depleted uranium. This material has shown promising results in reprocessed fuel analysis. |
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