Ratcheting problems of the U. S. International Thermonuclear Experimental Reactor
- 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), Vol. 21:1; ISSN 0748-1896
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
THERMONUCLEAR REACTORS
RATCHETING
BOILERS
COMPUTER CODES
COOLANTS
DESIGN
EXPERIMENTAL REACTORS
FIRST WALL
GEOMETRY
MATHEMATICAL MODELS
PLASTICITY
PRESSURE VESSELS
STRAINS
STRESSES
THERMAL CYCLING
USA
CONTAINERS
DEFORMATION
DEVELOPED COUNTRIES
MATHEMATICS
MECHANICAL PROPERTIES
NORTH AMERICA
REACTORS
RESEARCH AND TEST REACTORS
THERMONUCLEAR REACTOR WALLS
700420* - Fusion Technology- Plasma-Facing Components- (1992-)
990200 - Mathematics & Computers
700410 - Specific Fusion Devices & Experiments- (1992-)