Neutronic evaluation of a small lead-cooled nuclear reactor as an actinides burner by da Silva, Clarysson A.M., Oliveira, Natália G.P.L., Umezu, Ivan K., Costa, Antonella L., Pereira, Claubia

Get full text

Neutronic assessment of IPR-R1 TRIGA using Serpent 2.1.32 code by Melo, Jõao P.C., Chaves, Lucas V.G., Magalh̃aes, Maria E.V., Oliveira, Natália G.P.L., Costa, Antonella L., Castro, Victor F., Veloso, Maria A.F., Silva, Clarysson A.M. da, Pereira, Claubia

Get full text

Neutronic analysis of CANDU fuel bundle with reprocessed fuel by de Almeida, Michel C.B., de Faria, Rochkhudson B., da Silva, Clarysson A.M.

Get full text

Neutronic and thermal hydraulic analysis of a PWR fuel assembly using uranium mononitride by Silva, Raphael H.M., de Souza, Wallen F., da Silva, Clarysson A.M., Reis, Patrícia A.L., Costa, Antonella L.

Get full text

Time Series Analysis for BWR Stability Studies by Coloma, Wilmer A., Costa, Antonella L., Pereira, Claubia, da Silva, Clarysson A. M.

Get full text

Valuation of Power Oscillations in a BWR After Control Rod Banks Withdrawal Events by Costa, A L, Pereira, C, da Silva, C A M, Veloso, M A F

Get full text

MCNP5 modeling of the IPR-R1 TRIGA reactor for criticality calculation and reactivity determination by da Silva, Clarysson A.M., Pereira, Claubia, Guerra, Bruno T., Veloso, Maria Auxiliadora F., Costa, Antonella L., Dalle, Hugo M., Menezes, Maria Ângela de B.C.

Get full text

A neutronic evaluation of the (Pu–U) and (Am–Pu–U) insertion in a typical fuel of Angra-I by Costa, Antonella Lombardi, Pereira, Cláubia, Veloso, Maria Auxiliadora Fortini, Silva, Clarysson A.M. da

Get full text

Valuation of power oscillations in a BWR after control rod banks withdrawal events by Costa, Antonella L, Pereira, Claubia, da Silva, Clarysson A M, Veloso, Maria Auxiliadora F

Request full text