Abstract
Neutronic behavior of mixed UN-PuN nitride fuel in substitution of the mixed oxide U O{sub 2} - Pu O{sub 2} for fast reactors is discussed with focus on Super Phenix I. Characteristics parameters of both cores are calculated and compared and the results presented show a great advantage for the nitride fuel, pointing out a larger performance of fuel elements in the core and an effective reduction of reactivity loss during the cycle. (author).
Citation Formats
Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de.
Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos.
Brazil: N. p.,
1991.
Web.
Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, & Brito Aghina, L.O. de.
Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos.
Brazil.
Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de.
1991.
"Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos."
Brazil.
@misc{etde_10108842,
title = {Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos}
author = {Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de}
abstractNote = {Neutronic behavior of mixed UN-PuN nitride fuel in substitution of the mixed oxide U O{sub 2} - Pu O{sub 2} for fast reactors is discussed with focus on Super Phenix I. Characteristics parameters of both cores are calculated and compared and the results presented show a great advantage for the nitride fuel, pointing out a larger performance of fuel elements in the core and an effective reduction of reactivity loss during the cycle. (author).}
place = {Brazil}
year = {1991}
month = {Aug}
}
title = {Neutronic analysis concerning the utilization of mixed U N-Pu N nitride fuel for fast reactors; Analise neutronica concernente a utilizacao de combustivel nitreto de uranio/plutonio em reatores a neutrons rapidos}
author = {Renke, C A.C., Batista, J L, Waintraub, M, Santos Bastos, W dos, and Brito Aghina, L.O. de}
abstractNote = {Neutronic behavior of mixed UN-PuN nitride fuel in substitution of the mixed oxide U O{sub 2} - Pu O{sub 2} for fast reactors is discussed with focus on Super Phenix I. Characteristics parameters of both cores are calculated and compared and the results presented show a great advantage for the nitride fuel, pointing out a larger performance of fuel elements in the core and an effective reduction of reactivity loss during the cycle. (author).}
place = {Brazil}
year = {1991}
month = {Aug}
}