<abstract xmlns="http://www.w3.org/1999/xhtml"><p>The conceptual design activities for the DEMOnstration reactor (DEMO) – the prototype fusion power plant – are conducted in Europe by the EUROfusion Consortium. In 2015, three design concepts of the DEMO toroidal field (TF) coil were proposed by Swiss Plasma Center (EPFL-SPC, PSI Villigen), Italian National Agency for New Technologies (ENEA Frascati), and Atomic Energy and Alternative Energies Commission (CEA Cadarache). The proposed conductor designs were subjected to complete mechanical, electromagnetic, and thermal-hydraulic analyses. The present study is focused on the thermal-hydraulic analysis of the candidate conductor designs using simplified models. It includes (a) hydraulic analysis, (b) heat removal analysis, and (c) assessment of the maximum temperature and the maximum pressure in each conductor during quench. The performed analysis, aimed at verification whether the proposed design concepts fulfil the established acceptance criteria, provides the information for further improvements of the coil and conductors design.</p></abstract>

The conceptual design activities for the DEMOnstration reactor (DEMO) – the prototype fusion power plant – are conducted in Europe by the EUROfusion Consortium. In 2015, three design concepts of the DEMO toroidal field (TF) coil were proposed by Swiss Plasma Center (EPFL-SPC, PSI Villigen), Italian National Agency for New Technologies (ENEA Frascati), and Atomic Energy and Alternative Energies Commission (CEA Cadarache). The proposed conductor designs were subjected to complete mechanical, electromagnetic, and thermal-hydraulic analyses. The present study is focused on the thermal-hydraulic analysis of the candidate conductor designs using simplified models. It includes (a) hydraulic analysis, (b) heat removal analysis, and (c) assessment of the maximum temperature and the maximum pressure in each conductor during quench. The performed analysis, aimed at verification whether the proposed design concepts fulfil the established acceptance criteria, provides the information for further improvements of the coil and conductors design.

Thermal-hydraulic analysis of LTS cables for the DEMO TF coil using simplified models

Faculty of Mechanical Engineering and Mechatronics, West Pomeranian University of Technology, Szczecin, 19 Piastów Ave., 70-310 Szczecin,

Nukleonika

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

The conceptual design activities for the DEMOnstration reactor (DEMO) – the prototype fusion power plant – are conducted in Europe by the EUROfusion...

Thermal-hydraulic analysis of LTS cables for the DEMO TF coil using simplified models

Publicado en línea: 04 mar 2017

Páginas: 23 - 28

Recibido: 10 jun 2016

Aceptado: 08 nov 2016

DOI: https://doi.org/10.1515/nuka-2017-0004

Palabras clave
DEMO, tokamak, low superconductors, toroidal field coil, thermal-hydraulic analysis

© 2017 Monika Lewandowska et al., published by De Gruyter Open

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

Thermal-hydraulic analysis of LTS cables for the DEMO TF coil using simplified models

Publicado en línea: 04 mar 2017

Páginas: 23 - 28

Recibido: 10 jun 2016

Aceptado: 08 nov 2016

DOI: https://doi.org/10.1515/nuka-2017-0004

Palabras claveDEMO, tokamak, low superconductors, toroidal field coil, thermal-hydraulic analysis

© 2017 Monika Lewandowska et al., published by De Gruyter Open

This work is licensed under the Creative Commons Attribution-NonCommercial-NoDerivatives 3.0 License.

Palabras clave
DEMO, tokamak, low superconductors, toroidal field coil, thermal-hydraulic analysis