Thermal hydraulics of a feed-water pipe breakage with a back-pressure check valve
Conference
·
OSTI ID:5798014
The SOLA-LOOP computer code for transient, nonequilibrium, two-phase flows in networks has been coupled with a dynamic check valve model. Transient back-pressure check valve behavior and fluid dynamic effects in the form of the so called water-hammer are numerically simulated for a feed-water pipe breakage accident. Three tests from the Superheated Steam Reactor Safety Program Project (PHDR) carried out near Frankfurt, 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. 5 refs., 15 figs., 4 tabs.
- Research Organization:
- Los Alamos National Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 5798014
- Report Number(s):
- LA-UR-85-457; CONF-851103-2; ON: DE85007703
- Country of Publication:
- United States
- Language:
- English
Similar Records
SOLA-LOOP analysis of a back pressure check valve
Hydraulics performance of tilting-disk check valves. [High temperature liquid sodium service for LMFBR primary circuits]
Fluid relief and check valve
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6975115
Hydraulics performance of tilting-disk check valves. [High temperature liquid sodium service for LMFBR primary circuits]
Journal Article
·
Wed Dec 31 23:00:00 EST 1975
· J. Hydraul. Div., Am. Soc. Civ. Eng.; (United States)
·
OSTI ID:7196081
Fluid relief and check valve
Patent
·
Thu Jul 17 00:00:00 EDT 1986
·
OSTI ID:6734670
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
CONTROL EQUIPMENT
COOLING SYSTEMS
DAMPING
ENERGY SYSTEMS
EQUIPMENT
FAILURES
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
HYDRODYNAMICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
VALVES
WATER COOLED REACTORS
WATER HAMMER
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BLOWDOWN
COMPUTER CALCULATIONS
CONTROL EQUIPMENT
COOLING SYSTEMS
DAMPING
ENERGY SYSTEMS
EQUIPMENT
FAILURES
FLOW REGULATORS
FLUID FLOW
FLUID MECHANICS
HYDRAULICS
HYDRODYNAMICS
LOSS OF COOLANT
MATHEMATICAL MODELS
MECHANICS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
VALVES
WATER COOLED REACTORS
WATER HAMMER
WATER MODERATED REACTORS