Abstract
A 14 MeV neutron generator producing a steady-state neutron flux not less than 10/sup 13/ n cm/sup -2/ sec/sup -1/ in a volume not less than 500 cubic centimetre has been considered by the European Community as a neutron source (SORGENTINA) to provide significant materials data for the technological program of fusion research. Such a neutron generator will use mixed deuterium and tritium accelerated ion beam striking a solid target. The method to evaluate the neutron flux, the related irradiation volume and the beam characteristics of the generator to achieve this neutron flux are presented in this work.
Citation Formats
Pillon, M.
Beam power calculation for SORGENTINA neutron generator.
Italy: N. p.,
1991.
Web.
Pillon, M.
Beam power calculation for SORGENTINA neutron generator.
Italy.
Pillon, M.
1991.
"Beam power calculation for SORGENTINA neutron generator."
Italy.
@misc{etde_10131732,
title = {Beam power calculation for SORGENTINA neutron generator}
author = {Pillon, M}
abstractNote = {A 14 MeV neutron generator producing a steady-state neutron flux not less than 10/sup 13/ n cm/sup -2/ sec/sup -1/ in a volume not less than 500 cubic centimetre has been considered by the European Community as a neutron source (SORGENTINA) to provide significant materials data for the technological program of fusion research. Such a neutron generator will use mixed deuterium and tritium accelerated ion beam striking a solid target. The method to evaluate the neutron flux, the related irradiation volume and the beam characteristics of the generator to achieve this neutron flux are presented in this work.}
place = {Italy}
year = {1991}
month = {Apr}
}
title = {Beam power calculation for SORGENTINA neutron generator}
author = {Pillon, M}
abstractNote = {A 14 MeV neutron generator producing a steady-state neutron flux not less than 10/sup 13/ n cm/sup -2/ sec/sup -1/ in a volume not less than 500 cubic centimetre has been considered by the European Community as a neutron source (SORGENTINA) to provide significant materials data for the technological program of fusion research. Such a neutron generator will use mixed deuterium and tritium accelerated ion beam striking a solid target. The method to evaluate the neutron flux, the related irradiation volume and the beam characteristics of the generator to achieve this neutron flux are presented in this work.}
place = {Italy}
year = {1991}
month = {Apr}
}