Means for abruptly terminating the flow of fluid in closed fluid circuit systems of nuclear reactor plants or the like
Patent
·
OSTI ID:5944275
A nuclear steam supply system 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 is described. This is achieved by influencing a 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 stationary guide wheels which are located upstream of the pumps and can circulate the fluid in or counter to the direction of rotation of the respecive pump impellers, or the provision of suitably curved guide vanes in the pumps. The second mode includes interrupting the admission of undercooled fluid into the system upstream of the pumps.
- Assignee:
- Klein, Schanzlin and Becker AG
- Patent Number(s):
- US 4147465
- OSTI ID:
- 5944275
- 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
Method and means for abruptly terminating the flow of fluid in closed circulating systems of nuclear reactor plants or the like. [PWR]
VISUAL CAVITATION STUDIES OF MIXED FLOW PUMP IMPELLERS
Patent
·
Mon Feb 13 23:00:00 EST 1978
·
OSTI ID:5052326
Method and means for abruptly terminating the flow of fluid in closed circulating systems of nuclear reactor plants or the like. [PWR]
Patent
·
Tue Aug 31 00:00:00 EDT 1976
·
OSTI ID:7249688
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
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
CAVITATION
COOLING SYSTEMS
DESIGN
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
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
CAVITATION
COOLING SYSTEMS
DESIGN
PRESSURE DROP
PRIMARY COOLANT CIRCUITS
PUMPS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS