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Molten Salts as stripping media for radioactive superficial decontamination

LAINETTI, PAULO E. de O.; EUROPEAN NUCLEAR CONFERENCE 2010 (2014)

Use o thorium in the generation IV monten salt reactors and perspectives for Brazil

SENEDA, JOSE A.; LAINETTI, PAULO E.O. (2014)

Use pf thorium in the generation IV Molten Salt reactors and perspectives for Brazil

SENEDA, JOSE A.; LAINETTI, PAULO E.O.; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 11th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 18th; MEETING ON NUCLEAR INDUSTRY, 3rd (Sao Paulo: ABEN, 2013, 2014)

Potential advantages of molten salt reactor for merchant ship propulsion

FREITAS NETO, LUIZ G. de; FREIRE, LUCIANO O.; SANTOS, ADIMIR dos; ANDRADE, DELVONEI A. de (2021)

Molten salts as stripping media for radioactive superficial decontamination

LAINETTI, PAULO E. de O. (2016)

Estudo tecnologico do reprocessamento eletroquimico de combustiveis de uranio em meio de cloretos fundidos

FERNANDES, DAMARIS (2002)

Potential advantages of molten salt reactor for merchant ship propulsion

FREITAS NETO, LUIZ G.; FREIRE, LUCIANO O.; SANTOS, ADIMIR dos; ANDRADE, DELVONEI A. de; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2020)

Development of a new process for radioactive decontamination of painted carbon steel structures by molten salt stripping

LAINETTI, PAULO E.O.; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 9th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 16th; MEETING ON NUCLEAR INDUSTRY, 1st (Sao Paulo: ABEN, 2009, 2014)

Thorium and lithium in Brazil

OLIVEIRA, GLAUCIA A.C. de; LAINETTI, PAULO E.O.; BUSTILLOS, JOSE O.W.V.; PIRANI, DEBORA A.; BERGAMASCHI, VANDERLEI S.; FERREIRA, JOAO C.; SENEDA, JOSE A.; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE (Associa????o Brasileira de Energia Nuclear, 2020)

Monten salt oxidation as technique for decommissioning-selection of flow melting point salt mixtures

LAINETTI, PAULO E.O.; GARCIA, VITOR F.; BENVEGNU, GUILHERME; INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE; MEETING ON NUCLEAR APPLICATIONS, 11th; MEETING ON REACTOR PHYSICS AND THERMAL HYDRAULICS, 18th; MEETING ON NUCLEAR INDUSTRY, 3rd (Sao Paulo: ABEN, 2013, 2014)

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Molten Salts as stripping media for radioactive superficial decontamination

Use o thorium in the generation IV monten salt reactors and perspectives for Brazil

Use pf thorium in the generation IV Molten Salt reactors and perspectives for Brazil

Potential advantages of molten salt reactor for merchant ship propulsion

Molten salts as stripping media for radioactive superficial decontamination

Estudo tecnologico do reprocessamento eletroquimico de combustiveis de uranio em meio de cloretos fundidos

Potential advantages of molten salt reactor for merchant ship propulsion

Development of a new process for radioactive decontamination of painted carbon steel structures by molten salt stripping

Thorium and lithium in Brazil

Monten salt oxidation as technique for decommissioning-selection of flow melting point salt mixtures