LION4; LION; three-dimensional temperature distribution program. [CDC6600,7600; UNIVAC1108; IBM360,370; FORTRAN IV and ASCENT (CDC6600,7600), FORTRAN IV (UNIVAC1108A,B and IBM360,370)]
LION4 is a computer program for calculating one-, two-, or three-dimensional transient and steady-state temperature distributions in reactor and reactor plant components. It is used primarily for thermal-structural analyses. It utilizes finite difference techniques with first-order forward difference integration and is capable of handling a wide variety of bounding conditions. Heat transfer situations accommodated include forced and free convection in both reduced and fully-automated temperature dependent forms, coolant flow effects, a limited thermal radiation capability, a stationary or stagnant fluid gap, a dual dependency (temperature difference and temperature level) heat transfer, an alternative heat transfer mode comparison and selection facility combined with heat flux direction sensor, and any form of time-dependent boundary temperatures. The program, which handles time and space dependent internal heat generation, can also provide temperature dependent material properties with limited non-isotropic properties. User-oriented capabilities available include temperature means with various weightings and a complete heat flow rate surveillance system.CDC6600,7600;UNIVAC1108;IBM360,370; FORTRAN IV and ASCENT (CDC6600,7600), FORTRAN IV (UNIVAC1108A,B and IBM360,370); SCOPE (CDC6600,7600), EXEC8 (UNIVAC1108A,B), OS/360,370 (IBM360,370); The CDC6600 version plotter routine LAPL4 is used to produce the input required by the associated CalComp plotter for graphical output. The IBM360 version requires 350K for execution and one additional input/output unit besides the standard units.
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, NY (USA)
- OSTI ID:
- 6488803
- Report Number(s):
- ANL/NESC-299R; ON: DE83048299
- Country of Publication:
- United States
- Language:
- English
Similar Records
FLASH6; FLASH4; fully-implicit transient simulation. [IBM360,370; CDC6600,7600; FORTRAN IV]
QMESH; RENUM; self-organizing mesh generation. [CDC6600; IBM360,370/195; FORTRAN IV]
Related Subjects
COMPUTER CODES
L CODES
REACTORS
TEMPERATURE DISTRIBUTION
FLUID FLOW
HEAT TRANSFER
LIQUIDS
THERMAL CONDUCTIVITY
THREE-DIMENSIONAL CALCULATIONS
VAPORS
ENERGY TRANSFER
FLUIDS
GASES
PHYSICAL PROPERTIES
THERMODYNAMIC PROPERTIES
220200* - Nuclear Reactor Technology- Components & Accessories