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:
-
- 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):
-
Y - NEW / CROSS SECTIONAL TECHNOLOGIES Y02 - TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE Y02E - REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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 = {1980},
month = {1}
}