Implications of steady-state operation on divertor design

Journal Article · Tue Dec 31 04:00:00 EST 1996 · Fusion Technology

OSTI ID:447393

Sevier, D L; Reis, E E; Baxi, C B; Silke, G W; Wong, C P.C. ^[1]; Hill, D N ^[2]

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1. General Atomics, San Diego, CA (United States)
2. Lawrence Livermore National Lab., San Diego, CA (United States)

As fusion experiments progress towards long pulse or steady state operation, plasma facing components are undergoing a significant change in their design. This change represents the transition from inertially cooled pulsed systems to steady state designs of significant power handling capacity. A limited number of Plasma Facing Component (PFC) systems are in operation or planning to address this steady state challenge at low heat flux. However in most divertor designs components are required to operate at heat fluxes at 5 MW/m{sup 2} or above. The need for data in this area has resulted in a significant amount of thermal/hydraulic and thermal fatigue testing being done on prototypical elements. Short pulse design solutions are not adequate for longer pulse experiments and the areas of thermal design, structural design, material selection, maintainability, and lifetime prediction are undergoing significant changes. A prudent engineering approach will guide us through the transitional phase of divertor design to steady-state power plant components. This paper reviews the design implications in this transition to steady state machines and the status of the community efforts to meet evolving design requirements. 54 refs., 5 figs., 2 tabs.

• DOE Contract Number: AC03-89ER51114
• OSTI ID: 447393
• Report Number(s): CONF-9606116--
• Journal Information: Fusion Technology, Journal Name: Fusion Technology Journal Issue: 3 Vol. 30; ISSN 0748-1896; ISSN FUSTE8
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DESIGN
DEUTERIUM
DIVERTORS
EROSION
HEAT FLUX
ITER TOKAMAK
LIMITERS
NUMERICAL DATA
PLASMA IMPURITIES
REMOTE HANDLING
THERMAL FATIGUE
THERMAL TESTING
TRITIUM