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Title: Nuclear reactor heat transport system component low friction support system

Abstract

A support column for a heavy component of a liquid metal fast breeder reactor heat transport system which will deflect when the pipes leading coolant to and from the heavy component expand or contract due to temperature changes includes a vertically disposed pipe, the pipe being connected to the heavy component by two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles and the pipe being supported through two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles, each of the cylindrical surfaces bearing on a flat and horizontal surface.

Inventors:
 [1]
  1. Ruffs Dale, PA
Issue Date:
Research Org.:
Westinghouse Electric Corp., Pittsburgh, PA (United States)
OSTI Identifier:
863748
Patent Number(s):
4239598
Assignee:
United States of America as represented by United States (Washington, DC)
Patent Classifications (CPCs):
F - MECHANICAL ENGINEERING F16 - ENGINEERING ELEMENTS AND UNITS F16B - DEVICES FOR FASTENING OR SECURING CONSTRUCTIONAL ELEMENTS OR MACHINE PARTS TOGETHER, e.g. NAILS, BOLTS, CIRCLIPS, CLAMPS, CLIPS, WEDGES, JOINTS OR JOINTING
G - PHYSICS G21 - NUCLEAR PHYSICS G21C - NUCLEAR REACTORS
DOE Contract Number:  
EY-76-C-02-3045
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
nuclear; reactor; heat; transport; component; friction; support; column; heavy; liquid; metal; fast; breeder; deflect; pipes; leading; coolant; expand; contract; due; temperature; changes; vertically; disposed; pipe; connected; longitudinally; spaced; cycloidal; dovetail; joints; distal; dovetails; constitutes; surface; diameter; cylinder; centerlines; cylinders; intersect; angles; supported; cylindrical; surfaces; bearing; flat; horizontal; support column; longitudinally spaced; temperature change; vertically disposed; temperature changes; cylindrical surface; breeder reactor; fast breeder; nuclear reactor; liquid metal; metal fast; reactor heat; heat transport; cylindrical surfaces; horizontal surface; pipes leading; /376/248/403/976/

Citation Formats

Wade, Elman E. Nuclear reactor heat transport system component low friction support system. United States: N. p., 1980. Web.
Wade, Elman E. Nuclear reactor heat transport system component low friction support system. United States.
Wade, Elman E. Tue . "Nuclear reactor heat transport system component low friction support system". United States. https://www.osti.gov/servlets/purl/863748.
@article{osti_863748,
title = {Nuclear reactor heat transport system component low friction support system},
author = {Wade, Elman E},
abstractNote = {A support column for a heavy component of a liquid metal fast breeder reactor heat transport system which will deflect when the pipes leading coolant to and from the heavy component expand or contract due to temperature changes includes a vertically disposed pipe, the pipe being connected to the heavy component by two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles and the pipe being supported through two longitudinally spaced cycloidal dovetail joints wherein the distal end of each of the dovetails constitutes a part of the surface of a large diameter cylinder and the centerlines of these large diameter cylinders intersect at right angles, each of the cylindrical surfaces bearing on a flat and horizontal surface.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jan 01 00:00:00 EST 1980},
month = {Tue Jan 01 00:00:00 EST 1980}
}