Ratcheting problems of the U. S. International Thermonuclear Experimental Reactor

Journal Article · Wed Jan 01 04:00:00 EST 1992 · Fusion Technology; (United States)

OSTI ID:5688902

Majumdar, S ^[1]

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1. Argonne National Lab., Materials and Components Technology Div., Argonne, IL (US)

This paper reports that because of the presence of high cyclic thermal stress, coolant pressure-induced primary stress, and disruption-induced high cyclic primary stress, ratcheting (i.e., incremental accumulation of plastic strain) in the first wall poses a serious challenge to the designers of the U.S. International Thermonuclear Experimental Reactor (ITER). Existing design tools, such as the Bree diagram in the American Society of Mechanical Engineers Boiler and Pressure Vessels Code, are not directly applicable to the U.S. ITER because of important differences in geometry and loading modes. Available alternative models for ratcheting are discussed, and new Bree diagrams, which are more relevant for fusion reactor applications, are proposed.

• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5688902
• Journal Information: Fusion Technology; (United States), Journal Name: Fusion Technology; (United States) Vol. 21:1; ISSN 0748-1896; ISSN FUSTE
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700410 -- Specific Fusion Devices & Experiments-- (1992-)
700420* -- Fusion Technology-- Plasma-Facing Components-- (1992-)
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BOILERS
COMPUTER CODES
CONTAINERS
COOLANTS
DEFORMATION
DESIGN
DEVELOPED COUNTRIES
EXPERIMENTAL REACTORS
FIRST WALL
GEOMETRY
MATHEMATICAL MODELS
MATHEMATICS
MECHANICAL PROPERTIES
NORTH AMERICA
PLASTICITY
PRESSURE VESSELS
RATCHETING
REACTORS
RESEARCH AND TEST REACTORS
STRAINS
STRESSES
THERMAL CYCLING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
USA