Valve inlet fluid conditions for pressurizer safety and relief valves in Westinghouse-designed plants. Final report. [PWR]

Technical Report · Wed Dec 01 04:00:00 EST 1982

OSTI ID:6636071

Meliksetian, A; Sklencar, A M

The overpressure transients for Westinghouse-designed NSSSs are reviewed to determine the fluid conditions at the inlet to the PORV and safety valves. The transients considered are: licensing (FSAR) transients; extended operation of high pressure safety injection system; and cold overpressurization. The results of this review, presented in the form of tables and graphs, define the range of fluid conditions expected at the inlet to pressurized safety and power-operated relief valves utilized in Westinghouse-designed PWR units. These results will provide input to the PWR utilities in their justification that the fluid conditions under which their valve designs were tested as part of the EPRI/PWR Safety and Relief Valve Test Program indeed envelop those expected in their units.

• Research Organization: Westinghouse Electric Corp., Pittsburgh, PA (USA). Nuclear Energy Systems Div.
• OSTI ID: 6636071
• Report Number(s): EPRI-NP-2296; ON: DE83901094
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CONTROL EQUIPMENT
COOLING SYSTEMS
ENERGY SYSTEMS
EQUIPMENT
FLOW RATE
FLOW REGULATORS
FLUID MECHANICS
HYDRAULICS
MECHANICS
PERFORMANCE TESTING
PRESSURE GRADIENTS
PRESSURIZERS
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIEF VALVES
STRESSES
TESTING
THERMAL STRESSES
TRANSIENTS
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS