An intensive integrated modelling work of the main scenarios of the new Divertor Tokamak Test (DTT) facility with a single null divertor configuration has been performed using first principle quasi-linear transport models, in support of the design of the device and of the definition of its scientific work programme. First results of this integrated modelling work on DTT (R 0 = 2.14 m, a = 0.65 m) are presented here along with outcome of the gyrokinetic simulations used to validate the reduced models in the DTT range of parameters. As a result of this work, the heating mix has been defined, the size of device has been increased to R 0 = 2.19 m and a = 0.70 m, the use of pellets for fuelling has been recommended and reference profiles for diagnostic design, estimates of neutron yields and fast particle losses have been made available.

First principle-based multi-channel integrated modelling in support of the design of the Divertor Tokamak Test facility / Casiraghi, I., Mantica, P., Koechl, F., Ambrosino, R., Baiocchi, B., Castaldo, A., Citrin, J., Dicorato, M., Frassinetti, L., Mariani, A., Vincenzi, P., Agostinetti, P., Aucone, L., Balbinot, L., Ceccuzzi, S., Figini, L., Granucci, G., Innocente, P., Johnson, T., Nystrom, H., et al.. - In: NUCLEAR FUSION. - ISSN 0029-5515. - 61:11(2021), p. 116068. [10.1088/1741-4326/ac21b9]

First principle-based multi-channel integrated modelling in support of the design of the Divertor Tokamak Test facility

Ambrosino R.;Castaldo A.;
2021

Abstract

An intensive integrated modelling work of the main scenarios of the new Divertor Tokamak Test (DTT) facility with a single null divertor configuration has been performed using first principle quasi-linear transport models, in support of the design of the device and of the definition of its scientific work programme. First results of this integrated modelling work on DTT (R 0 = 2.14 m, a = 0.65 m) are presented here along with outcome of the gyrokinetic simulations used to validate the reduced models in the DTT range of parameters. As a result of this work, the heating mix has been defined, the size of device has been increased to R 0 = 2.19 m and a = 0.70 m, the use of pellets for fuelling has been recommended and reference profiles for diagnostic design, estimates of neutron yields and fast particle losses have been made available.
2021
First principle-based multi-channel integrated modelling in support of the design of the Divertor Tokamak Test facility / Casiraghi, I., Mantica, P., Koechl, F., Ambrosino, R., Baiocchi, B., Castaldo, A., Citrin, J., Dicorato, M., Frassinetti, L., Mariani, A., Vincenzi, P., Agostinetti, P., Aucone, L., Balbinot, L., Ceccuzzi, S., Figini, L., Granucci, G., Innocente, P., Johnson, T., Nystrom, H., et al.. - In: NUCLEAR FUSION. - ISSN 0029-5515. - 61:11(2021), p. 116068. [10.1088/1741-4326/ac21b9]
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11588/876084
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