COVE1; creep collapse for oval fuel pin tube. [CDC6600; FORTRAN IV]
Technical Report
·
OSTI ID:6488672
COVE1 is a time-dependent incremental creep collapse code that estimates the change in ovality of a fuel pin cladding tube. Application is intended primarily for tubes manufactured from zircaloy. Therefore, provision is made for the effects of anisotropy in the Prandtl-Reuss flow equations for inelastic incremental deformations by using the P and R strain ratio coefficients. The creep deformation is computed in terms of the length of the collapse zone and includes the effects of changes in temperatures, system pressure, fill gas pressure, and neutron flux levels.CDC6600; FORTRAN IV; SCOPE 3.4.2; 135K (octal) storage is required for execution.
- Research Organization:
- Pacific Northwest Lab., Richland, WA (USA)
- OSTI ID:
- 6488672
- Report Number(s):
- ANL/NESC-817; ON: DE83048817
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ALLOYS
ANISOTROPY
C CODES
CDC COMPUTERS
CLADDING
COMPUTER CODES
COMPUTERS
CREEP
DEFORMATION
DEPOSITION
FORTRAN
FUEL ELEMENTS
FUEL PINS
MECHANICAL PROPERTIES
NEUTRON FLUX
PRESSURE DEPENDENCE
PROGRAMMING LANGUAGES
RADIATION FLUX
REACTOR COMPONENTS
RELAXATION
STRAINS
STRESS ANALYSIS
STRESS RELAXATION
SURFACE COATING
TEMPERATURE DEPENDENCE
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ALLOYS
ANISOTROPY
C CODES
CDC COMPUTERS
CLADDING
COMPUTER CODES
COMPUTERS
CREEP
DEFORMATION
DEPOSITION
FORTRAN
FUEL ELEMENTS
FUEL PINS
MECHANICAL PROPERTIES
NEUTRON FLUX
PRESSURE DEPENDENCE
PROGRAMMING LANGUAGES
RADIATION FLUX
REACTOR COMPONENTS
RELAXATION
STRAINS
STRESS ANALYSIS
STRESS RELAXATION
SURFACE COATING
TEMPERATURE DEPENDENCE
TIN ALLOYS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS