Code development and analysis program. FRACAS-II: a subcode for the mechanical analysis of nuclear reactor fuel rods. [BWR; PWR]
The report describes the FRACAS-II computer code which performs the mechanical analysis of the fuel and cladding in the FRAP (Fuel Rod Analysis Program) fuel rod codes. At each loadstep, FRACAS-II obtains a complete elastic-plastic-creep solution for the stresses, strains, and displacements in both the fuel and the cladding. Both axial and radial cracks are permitted, and the crack depths are determined as part of the solution. Stress-driven, time-dependent hot-pressing in the fuel is included. A preliminary plastic anisotropy model based on Hill's theory has been included. Based on a finite difference scheme, FRACAS-II uses a matrix sweeping technique to obtain a discontinuous solution which is valid in both the fuel and the cladding when pellet cladding mechanical interaction takes place. Generalized plane strain is assumed, and while the fuel and the cladding are in contact, no axial slip is permitted at their interface. All material properties may be arbitrary functions of position, and arbitrary (work-hardening) stress-strain relations may be prescribed. Both transient and secondary creep calculations are performed. The capabilities of the code are illustrated in an example problem.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6561336
- Report Number(s):
- CDAP-TR-78-038; TRN: 79-001818
- Country of Publication:
- United States
- Language:
- English
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BWR TYPE REACTORS
FUEL RODS
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F CODES
STRESS ANALYSIS
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FUEL-CLADDING INTERACTIONS
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REACTOR COMPONENTS
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Light-Water Moderated
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210200 - Power Reactors
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