The Joint European Torus (JET) pumped divertor results and their significance for the International Thermonuclear Experimental Reactor (ITER)

Journal Article · Wed May 01 04:00:00 EDT 1996 · Physics of Plasmas

DOI:https://doi.org/10.1063/1.872028· OSTI ID:280173

Watkins, M L ^[1]

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1. JET Joint Undertaking, Abingdon, Oxon, OX14 3EA (United Kingdom)

The effectiveness of the pumped divertor during the 1994/95 experimental campaign of the Joint European Torus (JET) [P.-H. Rebut, R. J. Bickerton, and B. E. Keen, Nucl. Fusion {bold 25}, 1011 (1985)] has allowed the pursuit of a broad-based research program that is highly relevant to the International Thermonuclear Experimental Reactor (ITER) [K. Tomabechi and the ITER Team, Nucl. Fusion {bold 31}, 1135 (1991)]. High-performance hot-ion discharges with high confinement (H-modes) free of edge localized modes (ELMs) have set a JET record neutron rate in deuterium, but are limited by various magnetohydrodynamic (MHD) phenomena to {beta}{sub {ital N}}{lt}1.8, where {beta}{sub {ital N}}={beta}/({ital I}/{ital aB}), {beta} is the ratio of the plasma pressure to the toroidal field pressure, {ital I} is the plasma current, {ital B} is the toroidal field, and {ital a} is the horizontal minor radius of the plasma. Quasi-steady-state ELMy H-modes have also been studied at high power, high current, and high {beta}. The underlying energy transport exhibits a gyro-Bohm dependence that is lost close to the H-mode threshold and at high {beta}. ELMy H-modes with detached divertor plasmas and radiative power exhaust (the operating regime foreseen for ITER) reduce the power loading to the targets, but at the expense of main plasma confinement and purity. Beryllium has been compared with carbon fiber composite as a divertor target material and melting has been induced at ITER reference off-normal heat loads, but only a moderate degree of self-protection of the beryllium target was found. {copyright} {ital 1996 American Institute of Physics.}

• OSTI ID: 280173
• Journal Information: Physics of Plasmas, Journal Name: Physics of Plasmas Journal Issue: 5 Vol. 3; ISSN PHPAEN; ISSN 1070-664X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
BERYLLIUM
DEUTERIUM
DIVERTORS
H-MODE PLASMA CONFINEMENT
HIGH-BETA PLASMA
ITER TOKAMAK
JET TOKAMAK
PERFORMANCE
THERMONUCLEAR REACTORS