FLOT-1: flow transient analysis of a pressurized water reactor during flow coastdown (LWBR Development Program)

Technical Report · Mon Apr 01 00:00:00 EST 1968

OSTI ID:6741552

Fuls, G M

A description of the FLOT-1 (MO219) digital computer program for the prediction of the flow transient in a multiloop, multibranch, pressurized water reactor resulting from the partial, total, or sequential loss of power to the operating pumps is presented. The most significant parameter in the rate of flow coastdown is the kinetic energy in the pump rotor. A new empirical method of treating the transfer of energy from the pump rotor to the fluid is developed. Accurate prediction of the flow coastdown permits optimization of core power for maximum safe operation. The accuracy of this method of prediction is verified by correlation of predicted results with test data for the PWR at the Shippingport (Pa.) Power Station. (NSA 22: 33101)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6741552
• Report Number(s): WAPD-TM-428
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
SHIPPINGPORT REACTOR
TRANSIENTS
C CODES
COMPUTER CODES
LOSS OF FLOW
LWBR TYPE REACTORS
ACCIDENTS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
210500 - Power Reactors
Breeding