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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| Language: | English |
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Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR)
2021-02-01
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| Series: | Brazilian Journal of Radiation Sciences |
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| 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. |
| format | Article |
| id | doaj-art-9b9802d3b83d4bdeb9445796b7fddfa1 |
| institution | DOAJ |
| issn | 2319-0612 |
| language | English |
| publishDate | 2021-02-01 |
| publisher | Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) |
| record_format | Article |
| series | Brazilian Journal of Radiation Sciences |
| 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 |