System providing improved guidance support with restricted coolant flow for control rods in the upper head plenum of a nuclear reactor

Patent · Tue Oct 01 04:00:00 EDT 1991

OSTI ID:5667484

Chrise, J R; Rex, J A; Boyle, D E; Schwirian, R E

This patent describes a system for providing control rod guidance support with restricted rod coolant flow in a nuclear reactor pressure vessel having a fuel core with an outlet plenum for core heated coolant located thereabove and with an upper head plenum located above the outlet plenum and receiving a portion of return core coolant flow, a plurality of externally driven control rod assemblies each having a drive rod coupled to a depending control rod and extending vertically through the upper plenum and outlet plenum spaces for control rod movement into and out of the core to control the nuclear reaction. It comprises a generally solid upper horizontal support plate; a control rod guide tube assembly; the upper guide tube and the lower tube means; the upper guide tube having a top enclosure plate; means for restricting coolant flow; coupling means.

• Assignee: Westinghouse Electric Corp., Pittsburgh, PA (United States)
• Patent Number(s): US 5053189; A
• Application Number: PPN: US 7-422261
• OSTI ID: 5667484
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220400* -- Nuclear Reactor Technology-- Control Systems
220900 -- Nuclear Reactor Technology-- Reactor Safety
CONTAINERS
CONTROL ELEMENTS
CONTROL EQUIPMENT
CONTROL ROD DRIVES
CONTROL SYSTEMS
COOLING SYSTEMS
ENGINEERING
EQUIPMENT
FLOW REGULATORS
GUIDE TUBES
PRESSURE VESSELS
REACTOR COMPONENTS
REACTOR CONTROL SYSTEMS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAFETY
SAFETY ENGINEERING
TUBES