FIGRO: FORTRAN-IV digital computer program for the analysis of fuel swelling and calculation of temperature in bulk-oxide cylindrical fuel elements (LWBR Development Program)
Technical Report
·
OSTI ID:6742227
FIGRO is a FORTRAN-IV program for the analysis of fuel volume swelling and the calculation of temperatures in bulk-oxide cylindrical fuel elements. The fuel pellet may be solid, annular, or contain two radial zones. Oxide fuel thermal conductivity is a function of temperature, depletion, and porosity; fuel swelling is a function of temperature, depletion, internal hydrostatic pressure, and fissioning rate. As a boundary condition for the heat conduction equation, either the clad surface flux or the temperature at the inside radius of the fuel may be specified. Two sample problems are presented as test cases for the program deck and to exhibit the features of the input and output. (NSA 21: 14116)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6742227
- Report Number(s):
- WAPD-TM-618
- Country of Publication:
- United States
- Language:
- English
Similar Records
FIGRO; LWBR fuel swelling temperature study. [CDC6600; FORTRAN IV]
FIGRO (addendum II): a CDC-6600 computer program for the analysis of fuel swelling and calculation of temperature in bulk-oxide cylindrical fuel elements (LWBR Development Program)
FIGRO (addendum): a CDC-6600 computer program for the analysis of fuel swelling and calculation of temperature in bulk-oxide cylindrical fuel elements (LWBR Development Program)
Technical Report
·
·
OSTI ID:6742227
+7 more
FIGRO (addendum II): a CDC-6600 computer program for the analysis of fuel swelling and calculation of temperature in bulk-oxide cylindrical fuel elements (LWBR Development Program)
Technical Report
·
Wed Apr 01 00:00:00 EST 1970
·
OSTI ID:6742227
FIGRO (addendum): a CDC-6600 computer program for the analysis of fuel swelling and calculation of temperature in bulk-oxide cylindrical fuel elements (LWBR Development Program)
Technical Report
·
Sun Oct 01 00:00:00 EDT 1967
·
OSTI ID:6742227
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTER CODES
F CODES
FUEL ELEMENTS
SWELLING
TEMPERATURE DISTRIBUTION
LWBR TYPE REACTORS
FORTRAN
TEMPERATURE EFFECTS
THERMAL CONDUCTIVITY
BREEDER REACTORS
PHYSICAL PROPERTIES
PROGRAMMING LANGUAGES
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* - Power Reactors
Breeding
COMPUTER CODES
F CODES
FUEL ELEMENTS
SWELLING
TEMPERATURE DISTRIBUTION
LWBR TYPE REACTORS
FORTRAN
TEMPERATURE EFFECTS
THERMAL CONDUCTIVITY
BREEDER REACTORS
PHYSICAL PROPERTIES
PROGRAMMING LANGUAGES
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
THERMODYNAMIC PROPERTIES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210500* - Power Reactors
Breeding