Fusion-component lifetime analysis
A one-dimensional computer code has been developed to examine the lifetime of first-wall and impurity-control components. The code incorporates the operating and design parameters, the material characteristics, and the appropriate failure criteria for the individual components. The major emphasis of the modeling effort has been to calculate the temperature-stress-strain-radiation effects history of a component so that the synergystic effects between sputtering erosion, swelling, creep, fatigue, and crack growth can be examined. The general forms of the property equations are the same for all materials in order to provide the greatest flexibility for materials selection in the code. The individual coefficients within the equations are different for each material. The code is capable of determining the behavior of a plate, composed of either a single or dual material structure, that is either totally constrained or constrained from bending but not from expansion. The code has been utilized to analyze the first walls for FED/INTOR and DEMO and to analyze the limiter for FED/INTOR.
- Publication Date:
- OSTI Identifier:
- Report Number(s):
- DOE Contract Number:
- Resource Type:
- Technical Report
- Research Org:
- Argonne National Lab., IL (USA)
- Country of Publication:
- United States
- 70 PLASMA PHYSICS AND FUSION TECHNOLOGY; FIRST WALL; LIFETIME; PHYSICAL RADIATION EFFECTS; LIMITERS; COMPUTER CODES; CRACKS; CREEP; EROSION; FAILURES; FATIGUE; IMPURITIES; ONE-DIMENSIONAL CALCULATIONS; SPUTTERING; STRAINS; STRESSES; SWELLING; MECHANICAL PROPERTIES; RADIATION EFFECTS; THERMONUCLEAR REACTOR WALLS 700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
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