Development of a thermal diagnostic system for the SPARC tokamak.


Journal

The Review of scientific instruments
ISSN: 1089-7623
Titre abrégé: Rev Sci Instrum
Pays: United States
ID NLM: 0405571

Informations de publication

Date de publication:
01 Oct 2024
Historique:
received: 17 05 2024
accepted: 11 09 2024
medline: 1 10 2024
pubmed: 1 10 2024
entrez: 1 10 2024
Statut: ppublish

Résumé

The SPARC tokamak will have scrape-off layer parallel heat fluxes on the order of GW/m2. Managing power exhaust of this magnitude will be mandatory for a reactor-scale device. To enable this mission, a thermal diagnostic suite will be deployed to measure the in-vessel structural temperatures to ensure they do not exceed their design limits and to determine the spatial distribution and magnitude of energy deposited onto the first wall. Thermocouples and fiber Bragg gratings have been selected for their environmental compatibility and proven useful on other fusion devices. High-density thermocouple arrays in the divertor will have two spring-loaded thermocouples per divertor target tile, which are being used as calorimeters, and will look to resolve the temperature distribution within the tile due to a swept or static strike point. All systems will need to survive the vacuum vessel bake, set at a minimum plasma facing surface temperature of 350 °C, which presents a particularly challenging environment for the fiber-based subsystem. Along with this temperature design requirement, all the materials in the primary vacuum need to be ultra-high vacuum compatible, able to handle the expected neutron and gamma radiation, as well as tritium exposure, all of which restrict material options. Finally, due to the expected activated environment in SPARC, there will be little chance to replace defective sensors, so system resilience is ensured through toroidal redundancy, probe material selection, and mitigating the impact of common-mode failures. Initial testing of sensors show that intershot structural measurements are sufficiently captured with the raw output, but intrashot measurements of the plasma facing material requires model-based interpretive tools.

Identifiants

pubmed: 39352237
pii: 3314784
doi: 10.1063/5.0219565
pii:
doi:

Types de publication

Journal Article

Langues

eng

Sous-ensembles de citation

IM

Informations de copyright

© 2024 Author(s). Published under an exclusive license by AIP Publishing.

Auteurs

M O Hanson (MO)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

A Q Kuang (AQ)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

R Kulchy (R)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

M Lagieski (M)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

T Looby (T)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

C E Myers (CE)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

J Brettingen (J)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

K H C Chan (KHC)

Stanford University, Standford, California 94305, USA.

E Fox-Widdows (E)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

A Fritsch (A)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

T Henderson (T)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

C Lafleur (C)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

R Li (R)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

S McKanas (S)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

J Pentecost (J)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

M Quinn (M)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

M L Reinke (ML)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

A van Overbeeke-Costello (A)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

J Witham (J)

Commonwealth Fusion Systems, Devens, Massachusetts 01434, USA.

Classifications MeSH