SOLA-LOOP analysis of a back pressure check valve

Conference · Sun Jan 01 00:00:00 EST 1984

OSTI ID:6975115

Travis, J R

The SOLA-LOOP computer code for transient, nonequilibrium, two-phase flows in networks has been coupled with a simple valve model to analyze a feedwater pipe breakage with a back-pressure check valve. Three tests from the Superheated Steam Reactor Safety Program Project (PHDR) at Kahl, West Germany, are analyzed, and the calculated transient back-pressure check valve behavior and fluid dynamics effects are found to be in excellent agreement with the experimentally measured data.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6975115
• Report Number(s): LA-UR-84-1620; CONF-8405164-1; ON: DE84012437
• Resource Relation: Conference: IAEA technical committee/workshop on the uses of computer codes for nuclear reactor safety analysis, Varna, Bulgaria, 29 May 1984; Other Information: Paper copy only, copy does not permit microfiche production
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
LOSS OF COOLANT
BLOWDOWN
NUCLEAR POWER PLANTS
COMPUTER CODES
FEEDWATER
S CODES
VALVES
ACCIDENTS
CONTROL EQUIPMENT
EQUIPMENT
FLOW REGULATORS
HYDROGEN COMPOUNDS
NUCLEAR FACILITIES
OXYGEN COMPOUNDS
POWER PLANTS
REACTOR ACCIDENTS
THERMAL POWER PLANTS
WATER
220900* - Nuclear Reactor Technology- Reactor Safety