Method and means for abruptly terminating the flow of fluid in closed circulating systems of nuclear reactor plants or the like. [PWR]
Patent
·
OSTI ID:7249688
A nuclear steam supply system is described wherein each of a plurality of centrifugal pumps begins to operate with full cavitation in response to an abrupt drop of system pressure in the event of leakage. This is achieved by influencing the net positive suction head of each pump over the entire range of fluid flow and/or by influencing the net positive suction head upstream of the pumps. The first mode of causing the pumps to operate with full cavitation includes an appropriate selection of the inlet angle and/or inlet diameter of the pump impeller, the provision of auxiliary impellers which are located upstream of the pumps and can circulate the fluid in or counter to the direction of rotation of the respective pump impellers, or the provision of suitably curved guide vanes in the pumps. The second mode include interrupting the admission of undercooled fluid into the system upstream of the pumps.
- Assignee:
- Klein, Schanzlin and Becker Aktiengesellschaft
- Patent Number(s):
- US 3977808
- OSTI ID:
- 7249688
- Country of Publication:
- United States
- Language:
- English
Similar Records
Method and means for abruptly terminating the flow of fluid in closed fluid circulating systems of nuclear reactor plants or the like
Means for abruptly terminating the flow of fluid in closed fluid circuit systems of nuclear reactor plants or the like
VISUAL CAVITATION STUDIES OF MIXED FLOW PUMP IMPELLERS
Patent
·
Mon Feb 13 23:00:00 EST 1978
·
OSTI ID:5052326
Means for abruptly terminating the flow of fluid in closed fluid circuit systems of nuclear reactor plants or the like
Patent
·
Mon Apr 02 23:00:00 EST 1979
·
OSTI ID:5944275
VISUAL CAVITATION STUDIES OF MIXED FLOW PUMP IMPELLERS
Journal Article
·
Thu Feb 28 23:00:00 EST 1963
· Journal of Basic Engineering (U.S.) Divided into J. Eng. Mater. Technol. and J. Fluids Eng.
·
OSTI ID:4748447
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CONTROL SYSTEMS
COOLING SYSTEMS
FLOW RATE
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CONTROL SYSTEMS
COOLING SYSTEMS
FLOW RATE
PRESSURE GRADIENTS
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS