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

Cecconello M.; Conroy S.; Ericsson G.; Eriksson J.; Hjalmarsson A.; Sperduti A.; Casiraghi I.; Mantica P.; Vincenzi P.; Bolzonella T.; Agostinetti P.; Villari R.

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.

ID 450173
DOI 10.1016/j.fusengdes.2021.112382
PRODUCT TYPE Journal Article
LAST UPDATE 2022-03-30T14:29:05Z
TITLE Implementation of activities described in the Roadmap to Fusion during Horizon 2020 through a Joint programme of the members of the EUROfusion consortium