Design and R&D for the C-MOD outer divertor upgrade

Soren Harrison; Rui Vieira; Bruce Lipschultz; Robert Ellis; Dan Karnes; Peter Titus; Lihua Zhou; Han Zhang; William Beck

doi:10.13182/FST13-A18089

Design and R&D for the C-MOD outer divertor upgrade

Soren Harrison, Rui Vieira, Bruce Lipschultz, Robert Ellis, Dan Karnes, Peter Titus, Lihua Zhou, Han Zhang, William Beck

PPPL Engineering

Research output: Contribution to journal › Article › peer-review

5 Scopus citations

Abstract

Operational requirements and research considerations make a high-temperature, toroidally continuous outer divertor an important upgrade to the Alcator C-Mod tokamak. Leading edge melting of tiles, non-uniform heat loads, large electromagnetic forces, and localized impurity sources limit the performance of bulk plasmas. These issues can be addressed by the installation of a well-aligned, toroidally continuous outer divertor. Additionally, future long pulse operation will cause the temperature of the outer divertor to reach bulk temperatures as high as 500 - 600 ^°C. This future operational requirement combined with the strong temperature dependence of plasma surface interactions (especially fuel retention), makes a controllable, high-temperature outer divertor desirable and necessary. The motivation, criteria, design, and R&D for the upgrade are discussed below.

Original language	English (US)
Pages (from-to)	277-281
Number of pages	5
Journal	Fusion Science and Technology
Volume	64
Issue number	2
DOIs	https://doi.org/10.13182/FST13-A18089
State	Published - Aug 2013

All Science Journal Classification (ASJC) codes

Civil and Structural Engineering
Nuclear and High Energy Physics
Nuclear Energy and Engineering
General Materials Science
Mechanical Engineering

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abstract = "Operational requirements and research considerations make a high-temperature, toroidally continuous outer divertor an important upgrade to the Alcator C-Mod tokamak. Leading edge melting of tiles, non-uniform heat loads, large electromagnetic forces, and localized impurity sources limit the performance of bulk plasmas. These issues can be addressed by the installation of a well-aligned, toroidally continuous outer divertor. Additionally, future long pulse operation will cause the temperature of the outer divertor to reach bulk temperatures as high as 500 - 600 °C. This future operational requirement combined with the strong temperature dependence of plasma surface interactions (especially fuel retention), makes a controllable, high-temperature outer divertor desirable and necessary. The motivation, criteria, design, and R\&D for the upgrade are discussed below.",

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AU - Harrison, Soren

AU - Vieira, Rui

AU - Lipschultz, Bruce

AU - Ellis, Robert

AU - Karnes, Dan

AU - Titus, Peter

AU - Zhou, Lihua

AU - Zhang, Han

AU - Beck, William

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AB - Operational requirements and research considerations make a high-temperature, toroidally continuous outer divertor an important upgrade to the Alcator C-Mod tokamak. Leading edge melting of tiles, non-uniform heat loads, large electromagnetic forces, and localized impurity sources limit the performance of bulk plasmas. These issues can be addressed by the installation of a well-aligned, toroidally continuous outer divertor. Additionally, future long pulse operation will cause the temperature of the outer divertor to reach bulk temperatures as high as 500 - 600 °C. This future operational requirement combined with the strong temperature dependence of plasma surface interactions (especially fuel retention), makes a controllable, high-temperature outer divertor desirable and necessary. The motivation, criteria, design, and R&D for the upgrade are discussed below.

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Design and R&D for the C-MOD outer divertor upgrade

Abstract

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