LIFE3; mixed-oxide fuel element performance. [IBM370; CDC7600; FORTRAN IV]
Technical Report
·
OSTI ID:6343078
The LIFE3 computer code was developed to calculate the thermal and mechanical response of mixed-oxide fuel elements in a fast-reactor environment. It incorporates a one-dimensional, steady-state heat-transfer analysis and a finite-strain-theory structural analysis based on generalized plane strain and the method of successive elastic solutions. An incremental approach is used so that temperatures, stresses, and strains can be calculated during any specified history of reactor power cycling. Fuel-cladding and sodium-cladding chemical attack is treated by a cladding wastage model. Up to six axial sections are allowed to account for axial variations in power and coolant temperature. Fuel restructuring; migration of fabricated and swelling porosities; fuel and cladding thermal expansion, elasticity, swelling, and creep; fission-gas release; and fuel cracking, crack healing, and hot pressing are included in the analysis. LIFE3 is the reference ERDA code for calculating the performance of fast breeder reactor fuel elements under normal operating conditions, including power cycling.IBM370;CDC7600; FORTRAN IV; OS/370 (IBM370), SCOPE 2.1 (CDC7600); 325K bytes of memory (IBM370/195) and 125,000 (octal) words (CDC7600) with one scratch file and one file for restart information, in addition to the system input and output units.
- Research Organization:
- Argonne National Lab., IL (USA)
- OSTI ID:
- 6343078
- Report Number(s):
- ANL/NESC-460R; ON: DE83048460
- 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
CHEMICAL REACTIONS
COMPUTER CODES
CRACKING
CREEP
DECOMPOSITION
DEFORMATION
ENERGY TRANSFER
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
FUELS
HEAT TRANSFER
HOT PRESSING
L CODES
MATERIALS WORKING
MECHANICAL PROPERTIES
MIXED OXIDE FUELS
PERFORMANCE
PHYSICAL PROPERTIES
POROSITY
PRESSING
PYROLYSIS
REACTOR COMPONENTS
REACTORS
SOLID FUELS
STEADY-STATE CONDITIONS
STRESSES
SWELLING
TEMPERATURE DISTRIBUTION
THERMAL CONDUCTIVITY
THERMOCHEMICAL PROCESSES
THERMODYNAMIC PROPERTIES
220300* -- Nuclear Reactor Technology-- Fuel Elements
CHEMICAL REACTIONS
COMPUTER CODES
CRACKING
CREEP
DECOMPOSITION
DEFORMATION
ENERGY TRANSFER
EPITHERMAL REACTORS
FABRICATION
FAST REACTORS
FUEL ELEMENTS
FUEL-CLADDING INTERACTIONS
FUELS
HEAT TRANSFER
HOT PRESSING
L CODES
MATERIALS WORKING
MECHANICAL PROPERTIES
MIXED OXIDE FUELS
PERFORMANCE
PHYSICAL PROPERTIES
POROSITY
PRESSING
PYROLYSIS
REACTOR COMPONENTS
REACTORS
SOLID FUELS
STEADY-STATE CONDITIONS
STRESSES
SWELLING
TEMPERATURE DISTRIBUTION
THERMAL CONDUCTIVITY
THERMOCHEMICAL PROCESSES
THERMODYNAMIC PROPERTIES