A conceptual design and performance studies for a collimated neutron flux monitor and neutron spectrometer for the Divertor Tokamak Test (DTT) facility are presented. This study is based on the single-null divertor configuration and for “Half Power” and “Full power” scenarios with 15 MW of negative-ion NBI, 29 MW of ECH and 3 MW of ICRF heating with a maximum neutron yield of 1.5×1017 s−1. Fast ion distributions (both from auxiliary heating systems and fusion born) have been simulated in TRANSP/NUBEAM and the corresponding neutron energy spectra have been calculated using DRESS. Synthetic diagnostics have been implemented to determine the neutron fluxes and spectra at the detector location. Neutron emissivity profiles, plasma position, core ion temperature and the ratio of thermal and non-thermal D ion populations can be obtained with good accuracy and time resolution.

Cecconello, M., Conroy, S., Ericsson, G., Eriksson, J., Hjalmarsson, A., Sperduti, A., et al. (2021). Conceptual design of a collimated neutron flux monitor and spectrometer for DTT. FUSION ENGINEERING AND DESIGN, 167 [10.1016/j.fusengdes.2021.112382].

Conceptual design of a collimated neutron flux monitor and spectrometer for DTT

Casiraghi I.;
2021

Abstract

A conceptual design and performance studies for a collimated neutron flux monitor and neutron spectrometer for the Divertor Tokamak Test (DTT) facility are presented. This study is based on the single-null divertor configuration and for “Half Power” and “Full power” scenarios with 15 MW of negative-ion NBI, 29 MW of ECH and 3 MW of ICRF heating with a maximum neutron yield of 1.5×1017 s−1. Fast ion distributions (both from auxiliary heating systems and fusion born) have been simulated in TRANSP/NUBEAM and the corresponding neutron energy spectra have been calculated using DRESS. Synthetic diagnostics have been implemented to determine the neutron fluxes and spectra at the detector location. Neutron emissivity profiles, plasma position, core ion temperature and the ratio of thermal and non-thermal D ion populations can be obtained with good accuracy and time resolution.
Articolo in rivista - Articolo scientifico
DRESS; DTT; Neutron spectrometer; Radial neutron camera; TRANSP/NUBEAM; Triton burnup;
English
26-feb-2021
2021
167
112382
none
Cecconello, M., Conroy, S., Ericsson, G., Eriksson, J., Hjalmarsson, A., Sperduti, A., et al. (2021). Conceptual design of a collimated neutron flux monitor and spectrometer for DTT. FUSION ENGINEERING AND DESIGN, 167 [10.1016/j.fusengdes.2021.112382].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10281/329629
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