TOODEE: A two-dimensional, time-dependent heat conduction program

Technical Report · Mon Jan 01 00:00:00 EST 1990

OSTI ID:7038614

Sackett, B J; Ambrosek, R G

TOODEE is a two-dimensional, time-dependent heat conduction computer program written in FORTRAN. This program is suitable for investigating general transient and/or steady-state problems. Typical of (but not limited to) the type of problems for which the program has been used are the calculation of temperature distributions in reactor fuel elements during power excursions. The mesh for the program is formed by variably spaced orthogonal curves in either slab or cylindrical geometry. The cylindrical geometry may be either axisymmetric, with space variables R-Z, or polar, with space variables R-{theta}. Conditions to be specified independently at each boundary are either surface temperatures or heat transfer coefficients and either exterior temperatures of flow rates. Materials and coolant properties required in the program are evaluated from FORTRAN arithmetic functions supplied by the user. These properties may be time and/or temperature dependent. In addition, nonisotropic thermal conductivities and expansion coefficients may be defined. Phase changes are permitted in all materials except coolants. 6 refs.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 7038614
• Report Number(s): EGG-NE-8863; ON: DE90009631
• Resource Relation: Other Information: As originally compiled by John A. McClure
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
T CODES
THERMAL CONDUCTION
FORTRAN
HEAT TRANSFER
REACTORS
SURFACE PROPERTIES
SURFACES
TEMPERATURE DISTRIBUTION
THERMAL CONDUCTIVITY
TIME DEPENDENCE
TWO-DIMENSIONAL CALCULATIONS
COMPUTER CODES
ENERGY TRANSFER
PHYSICAL PROPERTIES
PROGRAMMING LANGUAGES
THERMODYNAMIC PROPERTIES
220100* - Nuclear Reactor Technology- Theory & Calculation
990200 - Mathematics & Computers