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Variable flow control for a nuclear reactor control rod. [LMFBR]

Patent ·
OSTI ID:6440082
;
A variable flow control for a control rod assembly of a nuclear reactor that depends on turbulent friction though an annulus. The annulus is formed by a piston attached to the ocntrol rod drive shaft and a housing or sleeve fitted to the enclosure housing the control rod. As the nuclear fuel is burned up and the need exists for increased reactivity, the control rods are withdrawn, which increases the length of the annulus and decreases the rate of coolant flow through the control rod assembly.
Assignee:
Dept. of Energy
Patent Number(s):
US 4118275
OSTI ID:
6440082
Country of Publication:
United States
Language:
English

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Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
ALKALI METALS
BREEDER REACTORS
CONTROL ELEMENTS
CONTROL EQUIPMENT
COOLING SYSTEMS
DESIGN
ELEMENTS
EPITHERMAL REACTORS
EQUIPMENT
FAST REACTORS
FBR TYPE REACTORS
FLOW REGULATORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
METALS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SODIUM