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Graphite moderated 252Cf source
(Universidad Autónoma Metropolitana, 2014-04)
The Thorium molten salt reactor is an attractive and affordable nuclear power option for
developing countries with insufficient infrastructure and limited technological
capability. In the aim of personnel training and ...
Neutron flux intercomparison and ex-core neutron detector optimization in a SMR reactor using MCNP6 code and MAVRIC sequence
(Associa????o Brasileira de Energia Nuclear, 2020)
Assessment of potential risk and radiological impact of accidental release from the ARGONAUT reactor
(Associa????o Brasileira de Energia Nuclear, 2020)