FORE2; fast reactor excursion calculations. [GE635; IBM360; FORTRAN IV]

Technical Report ·

OSTI ID:6343538

Fowler, T B; Tobias, M L; Fox, J N; Lawler, B E; Butz, H R

FORE2 is a coupled thermal hydraulics-point kinetics digital computer code designed to calculate significant reactor parameters under steady-state conditions, or as functions of time during transients. The transients may result from a programmed reactivity insertion or a power change. Variable inlet coolant flow rate and temperature are considered. The code calculates the reactor power, the individual reactivity feedbacks, and the temperature of coolant, cladding, fuel, structure, and additional material for up to seven axial positions in three channel types which represent radial zones of the reactor. The heat of fusion, accompanying fuel melting, the liquid metal voiding reactivity, and the spatial and the time variation of the fuel cladding gap coefficient due to changes in gap size are considered.GE635;IBM360; FORTRAN IV; GECOS (GE635), OS/360 (IBM360); 3 files and 40K memory (GE635).

• Research Organization: General Electric Co., Sunnyvale, CA (USA). Advanced Products Operation
• OSTI ID: 6343538
• Report Number(s): ANL/NESC-174; ON: DE83048174
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
ACCIDENTS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLANTS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXCURSIONS
F CODES
FAST REACTORS
FEEDBACK
FLUID FLOW
FLUID MECHANICS
FUELS
HEAT TRANSFER
HYDRAULICS
KINETICS
MECHANICS
POWER DISTRIBUTION
REACTOR ACCIDENTS
REACTOR KINETICS
REACTORS
THERMODYNAMICS