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MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions

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MAST Upgrade Divertor Facility : A Test Bed for Novel Divertor Solutions. / Morris, A. W.; Harrison, J. R.; Kirk, A.; Lipschultz, B.; Militello, F.; Moulton, D.; Walkden, N. R.

In: IEEE transactions on plasma science, Vol. 46, No. 5, 08.05.2018, p. 1217-1226.

Research output: Contribution to journalArticlepeer-review

Harvard

Morris, AW, Harrison, JR, Kirk, A, Lipschultz, B, Militello, F, Moulton, D & Walkden, NR 2018, 'MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions', IEEE transactions on plasma science, vol. 46, no. 5, pp. 1217-1226. https://doi.org/10.1109/TPS.2018.2815283

APA

Morris, A. W., Harrison, J. R., Kirk, A., Lipschultz, B., Militello, F., Moulton, D., & Walkden, N. R. (2018). MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions. IEEE transactions on plasma science, 46(5), 1217-1226. https://doi.org/10.1109/TPS.2018.2815283

Vancouver

Morris AW, Harrison JR, Kirk A, Lipschultz B, Militello F, Moulton D et al. MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions. IEEE transactions on plasma science. 2018 May 8;46(5):1217-1226. https://doi.org/10.1109/TPS.2018.2815283

Author

Morris, A. W. ; Harrison, J. R. ; Kirk, A. ; Lipschultz, B. ; Militello, F. ; Moulton, D. ; Walkden, N. R. / MAST Upgrade Divertor Facility : A Test Bed for Novel Divertor Solutions. In: IEEE transactions on plasma science. 2018 ; Vol. 46, No. 5. pp. 1217-1226.

Bibtex - Download

@article{9f59d1c1456d4542acdea84439554b3d,
title = "MAST Upgrade Divertor Facility: A Test Bed for Novel Divertor Solutions",
abstract = "The challenge of integrated exhaust consistent with the other requirements in DEMO and power plant class tokamaks (ITER-like and alternative DEMOs, Fusion Nuclear Science Facility approaches) is well-known and the exhaust solution is likely to be fundamental to the design and operating scenarios chosen. Strategies have been proposed such as high main plasma radiation, but improved solutions are sought and will require revised research methodologies. While no facility can address all the challenges, the new MAST Upgrade tokamak enables exploration of a wide range of divertor plasma aspects in a single device and their relation with the core plasma (e.g., access to H-mode) and in particular the development of fundamental understanding and new ideas. It has a unique combination of closed divertor, capability of a wide range of configurations from conventional to long leg (including Super-X), and fully symmetric double null (plasma and divertor structures). To extrapolate to DEMO and power plant scale devices where full integrated tests in advance are not feasible yet different physics mechanisms may dominate, theory-based models are likely to be essential for confident performance prediction, optimization, and a ``qualification' of the concept. Development and validation of such models is at the heart of the program around MAST Upgrade. Amongst the many areas to be explored, there will be a strong focus on the closely coupled topics of plasma detachment and cross-field transport mechanisms (e.g., plasma filaments), key ingredients of effective and reliable protection of the plasma-facing components at DEMO scale.",
keywords = "Impurities, Legged locomotion, Magnetic cores, Optimization, Physics, Plasmas, Power generation, Divertor, fusion reactor design, plasma exhaust, plasma filaments, super-x, tokamak devices., tokamak devices",
author = "Morris, {A. W.} and Harrison, {J. R.} and A. Kirk and B. Lipschultz and F. Militello and D. Moulton and Walkden, {N. R.}",
note = "{\textcopyright} 2018 Crown Copyright. This is an author-produced version of the published paper. Uploaded in accordance with the publisher{\textquoteright}s self-archiving policy. Further copying may not be permitted; contact the publisher for details.",
year = "2018",
month = may,
day = "8",
doi = "10.1109/TPS.2018.2815283",
language = "English",
volume = "46",
pages = "1217--1226",
journal = "IEEE transactions on plasma science",
issn = "0093-3813",
publisher = "Institute of Electrical and Electronics Engineers Inc.",
number = "5",

}

RIS (suitable for import to EndNote) - Download

TY - JOUR

T1 - MAST Upgrade Divertor Facility

T2 - A Test Bed for Novel Divertor Solutions

AU - Morris, A. W.

AU - Harrison, J. R.

AU - Kirk, A.

AU - Lipschultz, B.

AU - Militello, F.

AU - Moulton, D.

AU - Walkden, N. R.

N1 - © 2018 Crown Copyright. This is an author-produced version of the published paper. Uploaded in accordance with the publisher’s self-archiving policy. Further copying may not be permitted; contact the publisher for details.

PY - 2018/5/8

Y1 - 2018/5/8

N2 - The challenge of integrated exhaust consistent with the other requirements in DEMO and power plant class tokamaks (ITER-like and alternative DEMOs, Fusion Nuclear Science Facility approaches) is well-known and the exhaust solution is likely to be fundamental to the design and operating scenarios chosen. Strategies have been proposed such as high main plasma radiation, but improved solutions are sought and will require revised research methodologies. While no facility can address all the challenges, the new MAST Upgrade tokamak enables exploration of a wide range of divertor plasma aspects in a single device and their relation with the core plasma (e.g., access to H-mode) and in particular the development of fundamental understanding and new ideas. It has a unique combination of closed divertor, capability of a wide range of configurations from conventional to long leg (including Super-X), and fully symmetric double null (plasma and divertor structures). To extrapolate to DEMO and power plant scale devices where full integrated tests in advance are not feasible yet different physics mechanisms may dominate, theory-based models are likely to be essential for confident performance prediction, optimization, and a ``qualification' of the concept. Development and validation of such models is at the heart of the program around MAST Upgrade. Amongst the many areas to be explored, there will be a strong focus on the closely coupled topics of plasma detachment and cross-field transport mechanisms (e.g., plasma filaments), key ingredients of effective and reliable protection of the plasma-facing components at DEMO scale.

AB - The challenge of integrated exhaust consistent with the other requirements in DEMO and power plant class tokamaks (ITER-like and alternative DEMOs, Fusion Nuclear Science Facility approaches) is well-known and the exhaust solution is likely to be fundamental to the design and operating scenarios chosen. Strategies have been proposed such as high main plasma radiation, but improved solutions are sought and will require revised research methodologies. While no facility can address all the challenges, the new MAST Upgrade tokamak enables exploration of a wide range of divertor plasma aspects in a single device and their relation with the core plasma (e.g., access to H-mode) and in particular the development of fundamental understanding and new ideas. It has a unique combination of closed divertor, capability of a wide range of configurations from conventional to long leg (including Super-X), and fully symmetric double null (plasma and divertor structures). To extrapolate to DEMO and power plant scale devices where full integrated tests in advance are not feasible yet different physics mechanisms may dominate, theory-based models are likely to be essential for confident performance prediction, optimization, and a ``qualification' of the concept. Development and validation of such models is at the heart of the program around MAST Upgrade. Amongst the many areas to be explored, there will be a strong focus on the closely coupled topics of plasma detachment and cross-field transport mechanisms (e.g., plasma filaments), key ingredients of effective and reliable protection of the plasma-facing components at DEMO scale.

KW - Impurities

KW - Legged locomotion

KW - Magnetic cores

KW - Optimization

KW - Physics

KW - Plasmas

KW - Power generation

KW - Divertor

KW - fusion reactor design

KW - plasma exhaust

KW - plasma filaments

KW - super-x

KW - tokamak devices.

KW - tokamak devices

UR - http://www.scopus.com/inward/record.url?scp=85045742163&partnerID=8YFLogxK

U2 - 10.1109/TPS.2018.2815283

DO - 10.1109/TPS.2018.2815283

M3 - Article

VL - 46

SP - 1217

EP - 1226

JO - IEEE transactions on plasma science

JF - IEEE transactions on plasma science

SN - 0093-3813

IS - 5

ER -