CAT--AN IBM 704 PROGRAM FOR COOLANT ACTUATED TRANSIENTS IN AN OPEN-LATTICE CORE

Technical Report · Mon Feb 01 04:00:00 EST 1960

OSTI ID:4182132

Tong, L S; Cunningham, J P; Bournia, A; Stephenson, R R; Newman, M B

Thc CAT (Coolant Actuated Transients) Code was developed for using an IBM-704 Electronic Data Processing Machine to calculate the coolant actuated transients in a reactor core during a loss of coolant flow accident. The fuel geometry is an open lattice of identical vertical cylindrical rods uniformly spaced and the coolant flows parallel to them. For purposes of analysis, two types of channels are defined: one is the "hot channels" which are assumed few in number and to which the hot channel factors are applied, and the other is the "normal channels" which are effectively infinite in number. Thus the flow in the normal channels is not influenced by any flow redistribution from the hot channels. Because the opening between the rods connecting the hot and normal channels is much larger than the cross sectional flow area of the channel, the radial pressure gradient is considered negligible in comparison with the axial pressure gradient. The coolant flow rate in the hot channel is determined stepwise by equalizing the pressure drops of the small axial sections of the hot channels and the normal channels. (auth)

• Research Organization: Westinghouse Electric Corp. Atomic Power Dept., Pittsburgh
• NSA Number: NSA-14-011333
• OSTI ID: 4182132
• Report Number(s): YAEC-145
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
COMPUTERS
COOLANT LOOPS
COOLANTS
CYLINDERS
FLUID FLOW
FUEL ELEMENTS
LOSSES
POWER PLANTS
PROGRAMMING
REACTIVITY
REACTOR CORE
REACTOR TECHNOLOGY
TRANSIENTS