Lifetime analysis of fusion reactor components
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 modelling 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 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.
- Research Organization:
- Argonne National Lab., 9700 South Cass Ave., Argonne, IL 60439
- OSTI ID:
- 6263756
- Report Number(s):
- CONF-830406-; TRN: 85-002355
- Journal Information:
- Nucl. Technol./Fusion; (United States), Vol. 4:2; Conference: 5. topical meeting on technology of fusion energy, Knoxville, TN, USA, 26 Apr 1983
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
FIRST WALL
THERMONUCLEAR REACTOR MATERIALS
COMPUTERIZED SIMULATION
MATERIALS TESTING
PHYSICAL RADIATION EFFECTS
SERVICE LIFE
COMPUTER CODES
CRACK PROPAGATION
CREEP
EROSION
FAILURES
FATIGUE
INTOR TOKAMAK
ONE-DIMENSIONAL CALCULATIONS
PLATES
SPUTTERING
SWELLING
TEMPERATURE EFFECTS
THERMAL STRESSES
THERMONUCLEAR REACTORS
MATERIALS
MECHANICAL PROPERTIES
RADIATION EFFECTS
SIMULATION
STRESSES
TESTING
THERMONUCLEAR REACTOR WALLS
TOKAMAK TYPE REACTORS
700201* - Fusion Power Plant Technology- Blanket Engineering
700209 - Fusion Power Plant Technology- Component Development & Materials Testing