Effects of the reactor-coolant pumps during a small-break loss-of-coolant accident

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:6661843

Elliott, J L

TRAC-PD2 calculations indicate that more coolant mass remains in the system when the reactor coolant pumps are left in operation following a small cold-leg break. The analyses were performed for a Westinghouse plant (Zion-1) to help determine whether to trip the pumps at high-pressure injection initiation (the present operator directive), to trip the pumps at some later time in the transient, or to leave the pumps running indefinitely. The loop seals' behavior and the system refill characteristics primarily determined the results. 9 figures.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6661843
• Report Number(s): LA-UR-82-1717; CONF-830103-10; ON: DE82018456
• Resource Relation: Conference: 2. international topical meeting on nuclear thermalhydraulics, Santa Barbara, CA, USA, 11 Jan 1982; Other Information: Portions of document are illegible
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ZION-1 REACTOR
LOSS OF COOLANT
COMPUTER CALCULATIONS
COMPUTER CODES
PUMPS
T CODES
ACCIDENTS
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