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Silva, Clarysson Alberto Mello da
13  Ergebnisse:
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1

Overview of Fourth Generation Reactors Studied at the Unive..:

Silva, Clarysson Alberto Mello da ; Macedo, Anderson Altair Pinheiro de ; Gilberti, Maurício...
Brazilian Journal of Radiation Sciences.  12 (2024)  1 - p. e2419 , 2024
Link: https://doi.org/10.15392..
 
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2

Macroscopic cross section generation with WIMS-ANL for a PW:

Aruquipa Coloma, Wilmer ; Patrícia Amélia de Lima Reis ; Clarysson Alberto Mello da Silva.
Brazilian Journal of Radiation Sciences.  10 (2022)  3A - p. , 2022
Link: https://doi.org/10.15392..
 
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3

A Criticality and depletion analysis of the European Lead-C..:

Pereira Oliveira, Ana Luiza ; Mello da Silva, Clarysson Alberto
Brazilian Journal of Radiation Sciences.  10 (2022)  3A - p. , 2022
Link: https://doi.org/10.15392..
 
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4

A Criticality and depletion analysis of the European Lead-C..:

Ana Luiza Pereira Oliveira ; Clarysson Alberto Mello da Silva
https://bjrs.org.br/revista/index.php/REVISTA/article/view/1940.  , 2022
Link: https://doi.org/10.15392..
 
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5

Macroscopic cross section generation with WIMS-ANL for a PW:

Wilmer Aruquipa Coloma ; Patrícia Amélia de Lima Reis ; Clarysson Alberto Mello da Silva.
https://bjrs.org.br/revista/index.php/REVISTA/article/view/1948.  , 2022
Link: https://doi.org/10.15392..
 
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6

Neutronic Evaluation of MSBR System Using MCNP Code:

Clarysson Alberto Mello da Silva ; Alana Lima Vieira ; Isabella Resende Magalhães.
https://bjrs.org.br/revista/index.php/REVISTA/article/view/1261.  , 2021
Link: https://doi.org/10.15392..
 
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7

Neutronic evaluation of CANDU-6 core using reprocessed fuel:

Clarysson Alberto Mello da Silva ; Carlos Eduardo Velasquez Cabrera ; Michel Cleberson Bernardo de Almeida..
https://bjrs.org.br/revista/index.php/REVISTA/article/view/1219.  , 2020
Link: https://doi.org/10.15392..
 
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8

A methodology to a DB-MHR fuel recharge evaluation—A basic ..:

da Silva, Clarysson Alberto M. ; Pereira, Claubia ; Veloso, M.A.F..
Nuclear Engineering and Design.  248 (2012)  - p. 117-125 , 2012
Link: https://doi.org/10.1016/..
 
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9

Neutronic assessment of IPR-R1 TRIGA using Serpent 2.1.32 c..:

Melo, Jõao P.C. ; Chaves, Lucas V.G. ; Magalh̃aes, Maria E.V....
Nuclear Engineering and Design.  424 (2024)  - p. 113204 , 2024
Link: https://doi.org/10.1016/..
 
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10

A neutronic evaluation of the (Pu–U) and (Am–Pu–U) insertio..:

Costa, Antonella Lombardi ; Pereira, Cláubia ; Veloso, Maria Auxiliadora Fortini.
Annals of Nuclear Energy.  36 (2009)  1 - p. 1-6 , 2009
Link: https://doi.org/10.1016/..
 
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11

Neutronic evaluation of a small lead-cooled nuclear reactor..:

da Silva, Clarysson A.M. ; Oliveira, Natália G.P.L. ; Umezu, Ivan K...
Nuclear Engineering and Design.  417 (2024)  - p. 112796 , 2024
Link: https://doi.org/10.1016/..
 
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12

Time Series Analysis for BWR Stability Studies:

Coloma, Wilmer A. ; Costa, Antonella L. ; Pereira, Claubia.
Nuclear Technology.  206 (2019)  4 - p. 554-564 , 2019
Link: https://doi.org/10.1080/..
 
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13

MCNP5 modeling of the IPR-R1 TRIGA reactor for criticality ..:

da Silva, Clarysson A.M. ; Pereira, Claubia ; Guerra, Bruno T....
Nuclear Engineering and Design.  241 (2011)  12 - p. 4989-4993 , 2011
Link: https://doi.org/10.1016/..
 
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