Preliminary neutronic study of the S-PRISM fast reactor

Waste management is a challenge currently faced by nuclear energy worldwide. Most nuclear power plants operate in a once-through cycle and all spent nuclear fuel is stored in long term. Fast reactors can recycle 96% of the material in spent nuclear fuel of thermal reactors, reducing drastically the...

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Main Author: João Manoel Losada Moreira
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2021-02-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/1580
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author João Manoel Losada Moreira
author_facet João Manoel Losada Moreira
author_sort João Manoel Losada Moreira
collection DOAJ
description Waste management is a challenge currently faced by nuclear energy worldwide. Most nuclear power plants operate in a once-through cycle and all spent nuclear fuel is stored in long term. Fast reactors can recycle 96% of the material in spent nuclear fuel of thermal reactors, reducing drastically the time required to store the waste. The S-PRISM reactor is a modular, pool-type sodium-cooled fast reactor that can operate with a variety of fuel types. In this study, the advantages presented by fast reactors were briefly discussed and a preliminary analysis of the fuel pin cells was made. It was found that the isothermal coefficient of reactivity was lower than a regular PWR's, with neutron leakage playing a major role instead of coolant or doppler expansion. The k∞ showed decrease for the driver pin and increase for the blanket pin during burnup; opposite behavior was observed for the conversion ratio. No results for pin analysis were found in literature for comparison. As the simulations were carried out separately instead of in a system, the results are not representative of the whole core behavior but must be seen as a path to understand the different types of pin influence in the system.
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publisher Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
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spelling doaj-art-9b9802d3b83d4bdeb9445796b7fddfa12025-08-20T02:39:21ZengBrazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)Brazilian Journal of Radiation Sciences2319-06122021-02-0183A (Suppl.)10.15392/bjrs.v8i3A.15801233Preliminary neutronic study of the S-PRISM fast reactorJoão Manoel Losada Moreira0Programa de Pós-graduação em Energia Universidade Federal do ABCWaste management is a challenge currently faced by nuclear energy worldwide. Most nuclear power plants operate in a once-through cycle and all spent nuclear fuel is stored in long term. Fast reactors can recycle 96% of the material in spent nuclear fuel of thermal reactors, reducing drastically the time required to store the waste. The S-PRISM reactor is a modular, pool-type sodium-cooled fast reactor that can operate with a variety of fuel types. In this study, the advantages presented by fast reactors were briefly discussed and a preliminary analysis of the fuel pin cells was made. It was found that the isothermal coefficient of reactivity was lower than a regular PWR's, with neutron leakage playing a major role instead of coolant or doppler expansion. The k∞ showed decrease for the driver pin and increase for the blanket pin during burnup; opposite behavior was observed for the conversion ratio. No results for pin analysis were found in literature for comparison. As the simulations were carried out separately instead of in a system, the results are not representative of the whole core behavior but must be seen as a path to understand the different types of pin influence in the system.https://bjrs.org.br/revista/index.php/REVISTA/article/view/1580s-prismfast reactorneutronic
spellingShingle João Manoel Losada Moreira
Preliminary neutronic study of the S-PRISM fast reactor
Brazilian Journal of Radiation Sciences
s-prism
fast reactor
neutronic
title Preliminary neutronic study of the S-PRISM fast reactor
title_full Preliminary neutronic study of the S-PRISM fast reactor
title_fullStr Preliminary neutronic study of the S-PRISM fast reactor
title_full_unstemmed Preliminary neutronic study of the S-PRISM fast reactor
title_short Preliminary neutronic study of the S-PRISM fast reactor
title_sort preliminary neutronic study of the s prism fast reactor
topic s-prism
fast reactor
neutronic
url https://bjrs.org.br/revista/index.php/REVISTA/article/view/1580
work_keys_str_mv AT joaomanoellosadamoreira preliminaryneutronicstudyofthesprismfastreactor