Neutronic study of ELECTRA using reprocessed fuel and depleted uranium

The present work simulates the European Lead Cooled Training Reactor (ELECTRA), focusing on studying the neutronic parameters of a small fast nuclear reactor. The goal is to evaluate the possibility of incinerating minor actinides and the potential for energy production from 238U. The simulations co...

وصف كامل

التفاصيل البيبلوغرافية
الحاوية / القاعدة:Brazilian Journal of Radiation Sciences
المؤلفون الرئيسيون: Clarysson Alberto Mello da silva, Paola Machado de Almeida, Claubia Claubia Pereira
التنسيق: مقال
اللغة:الإنجليزية
منشور في: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2025-04-01
الموضوعات:
الوصول للمادة أونلاين:https://bjrs.org.br/revista/index.php/REVISTA/article/view/2677
الوصف
الملخص:The present work simulates the European Lead Cooled Training Reactor (ELECTRA), focusing on studying the neutronic parameters of a small fast nuclear reactor. The goal is to evaluate the possibility of incinerating minor actinides and the potential for energy production from 238U. The simulations consider the following scenarios: depleted uranium mixed with the reprocessed fuel, and individual fuel rods containing only depleted uranium positioned at different locations within the reactor core. The results show that the use of reprocessed fuels could contribute to the reduction of minor actinides, while the use of depleted uranium reduces reactor criticality by acting as a neutron absorber. Most uranium nuclides do not undergo fission during burnup, which increases their isotopic concentration.
تدمد:2319-0612