FRAPCON2/VIM5B. Fuel Rod Thermal-Mechanical Behavior
- EG and G Idaho Inc., Idaho Falls, ID (United States)
- Pacific Northwest Lab., Richland, WA (United States)
FRAPCON2/V1M5B is the most recent in the FRAPCON series of fuel rod response modeling programs. The FRAPCON series, like the earlier FRAP-S and GAPCON-THERMAL codes, is designed to predict the steady-state long-term burnup response of oxide fuel rods in light water reactors (LWRs). In addition, these codes generate the initial conditions for transient fuel rod analysis by the FRAP-T6 or thermal-hydraulic analysis programs. The FRAPCON2 programs calculate 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 heat conduction through the fuel and cladding, cladding elastic and plastic deformation, fuel-cladding mechanical interaction, fission gas release, fuel rod internal gas pressure, heat transfer between fuel and cladding, cladding oxidation, and heat transfer from cladding to coolant. Material properties, water properties, and heat transfer correlation data are included.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Office of Nuclear Regulatory Research
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 139279
- Report Number(s):
- ESTSC/NRC/R-000042C017600; NESC-694
- Resource Relation:
- Other Information: DN: The FRAPCON2/V1M5B Edition B transmittal tape is written in a format that can be read on non-CDC machines.; PBD: 1 Apr 1988
- Country of Publication:
- United States
- Language:
- English
Similar Records
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)]
FRAPCON-2: a computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods. Technical report
Related Subjects
COMPUTERS
INFORMATION SCIENCE
MANAGEMENT
LAW
MISCELLANEOUS
22 NUCLEAR REACTOR TECHNOLOGY
42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES
F CODES
FUEL RODS
BURNUP
HEAT TRANSFER
HYDRAULICS
RESPONSE FUNCTIONS
TEMPERATURE DEPENDENCE
PRESSURE DEPENDENCE
REACTOR SAFETY
MECHANICAL PROPERTIES
STEADY-STATE CONDITIONS
WATER COOLED REACTORS
COMPUTER PROGRAM DOCUMENTATION