Broadening of the Divertor Heat Flux Profile in High Confinement Tokamak Fusion Plasmas with Edge Pedestals Limited by Turbulence in DIII-D-Reference-Cited by-同舟云学术

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Broadening of the Divertor Heat Flux Profile in High Confinement Tokamak Fusion Plasmas with Edge Pedestals Limited by Turbulence in DIII-D

Published:2024-06-07 Issue:23 Volume:132 Page:
ISSN:0031-9007
Container-title:Physical Review Letters
language:en
Short-container-title:Phys. Rev. Lett.

Author:

Ernst D. R.¹^ORCID,Bortolon A.²^ORCID,Chang C. S.²^ORCID,Ku S.²^ORCID,Scotti F.³^ORCID,Wang H. Q.⁴^ORCID,Yan Z.⁵^ORCID,Chen Jie⁶^ORCID,Chrystal C.⁴^ORCID,Glass F.⁴^ORCID,Haskey S.²^ORCID,Hood R.⁷^ORCID,Khabanov F.⁵^ORCID,Laggner F.⁸^ORCID,Lasnier C.³^ORCID,McKee G. R.⁵^ORCID,Rhodes T. L.⁶^ORCID,Truong D.⁷^ORCID,Watkins J.⁷

Affiliation:

1. Massachusetts Institute of Technology

2. Princeton University Plasma Physics Laboratory

3. Lawrence Livermore National Laboratory

4. General Atomics

5. University of Wisconsin

6. University of California

7. Sandia National Laboratory

8. North Carolina State University

Funder

U.S. Department of Energy

National Energy Research Scientific Computing Center

Lawrence Berkeley National Laboratory

Office of Science

Publisher

American Physical Society (APS)

Link

http://harvest.aps.org/v2/journals/articles/10.1103/PhysRevLett.132.235102/fulltext

Reference25 articles.

1. Analysis of a multi-machine database on divertor heat fluxes

2. Scaling of the tokamak near the scrape-off layer H-mode power width and implications for ITER

3. Heuristic drift-based model of the power scrape-off width in low-gas-puff H-mode tokamaks

4. The beam emission spectroscopy diagnostic on the DIII-D tokamak

5. Gyrokinetic projection of the divertor heat-flux width from present tokamaks to ITER

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1. Role of turbulent separatrix tangle in the improvement of the integrated pedestal and heat exhaust issue for stationary-operation tokamak fusion reactors;Nuclear Fusion;2024-04-16

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