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http://hdl.handle.net/1843/56885| Tipo: | Artigo de Periódico |
| Título: | Neutronic evaluation of candu-6 core using reprocessed fuels |
| Autor(es): | Clarysson Alberto Mello da Silva Carlos Eduardo Velasquez Cabrera Michel Cleberson Bernardo de Almeida Rochkhudon Batista de Faria Claubia Pereira Bezerra Lima |
| Resumen: | The spent fuel from a PWR still contains some amount of fissile materials depending on their initial enrichment and the burnup. Thus, spent fuel from PWRs containing about 1.5% of fissile material could be used as fuel for CANDU reactors after some fission products are removed from it. Thus, an important proposal is the DUPIC cycle, where spent fuels from a PWR are packaged into a CANDU fuel bundle using mechanical reprocessing but without the need of chemical reprocessing. When it is refueled with reprocessed fuel, the reactivity of the system increases, and this behavior may affect the safety parameters of the reactor. Therefore, this work studies the neutronic parameters of two reprocessing fuel techniques: AIROX and OREOX, which are evaluated for two different cores configuration. The first one considers heavy water as a moderator and coolant. The second one considers heavy water and light water as moderator and coolant, respectively. These studies evaluate the core behavior based on the different number of reprocessed fuels channels and compare them with the reference core. To perform the simulation, MCNPX was used to calculate the effective multiplication factor, void reactivity coefficient, and neutron flux, which were evaluated at steady state condition for the different cases. The results show that the presence of parasitic absorbers in the reprocessed fuels hardens the neutron spectrum. This behavior provokes an increase in the core reactivity, and in the void reactivity coefficient. Among these parameters, the use of light water reduces the core reactivity but does not improve the void reactivity coefficient. |
| Asunto: | Reatores nucleares |
| Idioma: | por |
| País: | Brasil |
| Editor: | Universidade Federal de Minas Gerais |
| Sigla da Institución: | UFMG |
| Departamento: | ENG - DEPARTAMENTO DE ENGENHARIA NUCLEAR |
| Tipo de acceso: | Acesso Aberto |
| Identificador DOI: | https://doi.org/10.15392/bjrs.v8i3.1219 |
| URI: | http://hdl.handle.net/1843/56885 |
| Fecha del documento: | 2020 |
| metadata.dc.url.externa: | https://www.bjrs.org.br/revista/index.php/REVISTA/article/view/1219 |
| metadata.dc.relation.ispartof: | Brazilian Journal of Radiation Sciences |
| Aparece en las colecciones: | Artigo de Periódico |
archivos asociados a este elemento:
| archivo | Descripción | Tamaño | Formato | |
|---|---|---|---|---|
| Neutronic evaluation of CANDU-6 core using reprocessed fuels.pdf | 715.1 kB | Adobe PDF | Visualizar/Abrir |
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