Evaluation of the thermal neutron flux in samples of Al–Au...

Nuclear Engineering and Design 2014 / 07 Vol. 273

Evaluation of the thermal neutron flux in samples of Al–Au alloy irradiated in the carrousel channels of the TRIGA MARK I IPR-R1 reactor using MCNP code

Salomé, J.A.D., Guerra, B.T., Pereira, C., de Menezes, M.Â.B.C., da Silva, C.A.M., Dalle, H.M.
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Volume:
273
Language:
english
Journal:
Nuclear Engineering and Design
DOI:
10.1016/j.nucengdes.2014.03.020
Date:
July, 2014
File:
PDF, 2.37 MB
english, 2014
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