The TRADE experiment, to be performed at the TRIGA nuclear reactor of the ENEA Casaccia Centre (Rome, Italy) consists in the coupling of an external proton accelerator to a spallation target to be installed in the central channel of the reactor kept in a sub-critical configuration. TRADE is meant to represent a major demonstration step of the Accelerator-Driven-Systems concept. Monte Carlo calculations are needed for the radiation transport analysis of various aspects of the experiment. The Monte Carlo general purpose codes MCNPX and FLUKA have been applied, among other issues, to the analysis of the shielding configuration of the beam transport line and to the assessment of the radioactivity induced by the impact of the 140 MeV proton beam with the target. In the shielding analysis the dose rates due to the proton beam leakage along the transport line have been calculated for points beyond the barytic concrete shields. Various leakage angles with respect to the beam axis have been considered. The analysis of the induced radioactivity has involved the calculation of the type and amount of the residual nuclei produced by the spallation process within the tantalum target and of the evolution of such nuclei. The results obtained with MCNPX and FLUKA are compared and discussed.

Comparison between the Monte Carlo codes mcnpx and fluka within the framework of calculations for the trade experiment

Petrovich, C.;
2005

Abstract

The TRADE experiment, to be performed at the TRIGA nuclear reactor of the ENEA Casaccia Centre (Rome, Italy) consists in the coupling of an external proton accelerator to a spallation target to be installed in the central channel of the reactor kept in a sub-critical configuration. TRADE is meant to represent a major demonstration step of the Accelerator-Driven-Systems concept. Monte Carlo calculations are needed for the radiation transport analysis of various aspects of the experiment. The Monte Carlo general purpose codes MCNPX and FLUKA have been applied, among other issues, to the analysis of the shielding configuration of the beam transport line and to the assessment of the radioactivity induced by the impact of the 140 MeV proton beam with the target. In the shielding analysis the dose rates due to the proton beam leakage along the transport line have been calculated for points beyond the barytic concrete shields. Various leakage angles with respect to the beam axis have been considered. The analysis of the induced radioactivity has involved the calculation of the type and amount of the residual nuclei produced by the spallation process within the tantalum target and of the evolution of such nuclei. The results obtained with MCNPX and FLUKA are compared and discussed.
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/5719
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