Proceedings of the Japan-US Workshop P-92 on plasma material interaction/high heat flux data needs for the next step ignition and steady state devices

Conference · Fri May 01 00:00:00 EDT 1987

OSTI ID:5972743

Miyahara, Akira; Wilson, K L ^[1]

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1. eds.

The Japan-US workshop on ''Plasma Material Interaction/High Heat Flux Data Needs for the Next Step Ignition and Steady State Devices,'' was held at Institute of Plasma Physics, Nagoya University, on January 26-30, 1987. The primary objective of this workshop was to answer the question, ''Are existing carbon materials (graphites and carbon-carbon composites) feasible for the CIT-experiment or not.'' The approach to this question needs a definition of how reference materials for CIT are to be selected out of existing materials. Most papers in this report deals with this question by testing different types of graphite as first wall material for thermonuclear devices. 42 individual reports were cataloged separately.

• Research Organization: Nagoya Univ. (Japan). Inst. of Plasma Physics; Department of Energy, Washington, DC (USA). Office of Fusion Energy
• OSTI ID: 5972743
• Report Number(s): IPPJ-AM-50; CONF-870185-; ON: DE87013568
• Resource Relation: Conference: Japan/US workshop P-92 on plasma material interaction/high heat flux data needs for the next step ignition and steady state devices, Nagoya, Japan, 26 Jan 1987; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
36 MATERIALS SCIENCE
GRAPHITE
MATERIALS TESTING
CHEMICAL PROPERTIES
EROSION
EXPERIMENTAL DATA
FIRST WALL
FRACTURE PROPERTIES
HYDROGEN
LEADING ABSTRACT
LIMITERS
PHYSICAL PROPERTIES
TOKAMAK TYPE REACTORS
TRAPPING
ABSTRACTS
CARBON
DATA
DOCUMENT TYPES
ELEMENTAL MINERALS
ELEMENTS
INFORMATION
MECHANICAL PROPERTIES
MINERALS
NONMETALS
NUMERICAL DATA
TESTING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
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