Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma
Abstract
Any device to succeed ITER and demonstrate successful engineering implementation of a first wall and tritium generation will require very extensive instrumentation of the device components. Measurements of slow and fast movements of components, strains and stresses on them, temperatures and fluid flow parameters will all be necessary. While it is hoped that the physics of the plasma will become fully known during the life of such a device (enabling a major reduction in the complexity of plasma diagnostics) qualification of the engineered components will be the primary output of the operation. Survival of the first wall for long-pulse full-power operational periods, breeding sufficient tritium to maintain operation, reliable behavior of coils and the auxiliary systems of fueling, heating and remote maintenance equipment, must all be demonstrated. In conclusion, this paper puts together a preliminary estimate of the instrumentation that will be necessary to meet this requirement for a specific example of a tokamak design.
- Authors:
-
[1];
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- ITER Organization, St. Paul Lez Durance (France)
- Publication Date:
- Research Org.:
- Princeton Plasma Physics Lab. (PPPL), Princeton, NJ (United States)
- Sponsoring Org.:
- USDOE
- OSTI Identifier:
- 1616945
- Alternate Identifier(s):
- OSTI ID: 1668771
- Grant/Contract Number:
- AC02-09CH11466
- Resource Type:
- Accepted Manuscript
- Journal Name:
- Fusion Engineering and Design
- Additional Journal Information:
- Journal Volume: 153; Journal Issue: C; Journal ID: ISSN 0920-3796
- Publisher:
- Elsevier
- Country of Publication:
- United States
- Language:
- English
- Subject:
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; Instrumentation; Tokamaks; Burning plasmas; Radiation impact
Citation Formats
Young, K. M., and Sadakov, Sergey. Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma. United States: N. p., 2020.
Web. doi:10.1016/j.fusengdes.2020.111457.
Young, K. M., & Sadakov, Sergey. Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma. United States. https://doi.org/10.1016/j.fusengdes.2020.111457
Young, K. M., and Sadakov, Sergey. Wed .
"Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma". United States. https://doi.org/10.1016/j.fusengdes.2020.111457. https://www.osti.gov/servlets/purl/1616945.
@article{osti_1616945,
title = {Non-plasma diagnostic instrumentation for a next-step tokamak with a burning plasma},
author = {Young, K. M. and Sadakov, Sergey},
abstractNote = {Any device to succeed ITER and demonstrate successful engineering implementation of a first wall and tritium generation will require very extensive instrumentation of the device components. Measurements of slow and fast movements of components, strains and stresses on them, temperatures and fluid flow parameters will all be necessary. While it is hoped that the physics of the plasma will become fully known during the life of such a device (enabling a major reduction in the complexity of plasma diagnostics) qualification of the engineered components will be the primary output of the operation. Survival of the first wall for long-pulse full-power operational periods, breeding sufficient tritium to maintain operation, reliable behavior of coils and the auxiliary systems of fueling, heating and remote maintenance equipment, must all be demonstrated. In conclusion, this paper puts together a preliminary estimate of the instrumentation that will be necessary to meet this requirement for a specific example of a tokamak design.},
doi = {10.1016/j.fusengdes.2020.111457},
journal = {Fusion Engineering and Design},
number = C,
volume = 153,
place = {United States},
year = {Wed Jan 15 00:00:00 EST 2020},
month = {Wed Jan 15 00:00:00 EST 2020}
}
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