FRAP-T5: a computer code for the transient analysis of oxide fuel rods
The Fuel Rod Analysis Program - Transient (FRAP-T5) is a FORTRAN IV computer code that calculates the transient response of light water reactor fuel rods during hypothesized accidents such as a loss-of-coolant accident or a power-cooling mismatch. The code calculates the temperature, pressure, deformation, and failure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include: (a) heat conduction, (b) elastic--plastic fuel and cladding deformation, (c) fuel-cladding mechanical interaction, (d) fission gas release, (e) transient fuel rod gas pressure, (f) heat transfer between fuel and cladding, (g) cladding oxidation, (h) cladding annealing, and (i) heat transfer from cladding to coolant. The code contains all the needed material properties, water properties, and heat transfer correlations. The code includes a user's option that automatically provides a detailed uncertainty analysis of code calculated response parameters. FRAP-T5 is programmed on the CDC 7600 computer and is structured to enable direct linkage to a thermal-hydraulic code for transient analysis.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6042488
- Report Number(s):
- NUREG/CR-0840; TREE-1281; TRN: 79-016983
- Country of Publication:
- United States
- Language:
- English
Similar Records
FRAP-S2: a computer code for the steady state analysis of oxide fuel rods
FRAPCON2; FRAP-S3; FRAP-S1; steady state analysis oxide fuel rods. [CDC CYBER175,176; CDC7600; IBM360,370; FORTRAN IV (CDC CYBER175,176 and CDC7600), FORTRAN IV (85%) and BAL (15%) (IBM360)]
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR ACCIDENTS
COMPUTER CODES
F CODES
FUEL ELEMENT FAILURE
MATHEMATICAL MODELS
PWR TYPE REACTORS
CDC COMPUTERS
FUEL RODS
HEAT TRANSFER
TRANSIENTS
ACCIDENTS
COMPUTERS
ENERGY TRANSFER
FUEL ELEMENTS
REACTOR COMPONENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding