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Title: Nuclear reactor overflow line

Abstract

The overflow line for the reactor vessel of a liquid-metal-cooled nuclear reactor includes means for establishing and maintaining a continuous bleed flow of coolant amounting to 5 to 10% of the total coolant flow through the overflow line to prevent thermal shock to the overflow line when the reactor is restarted following a trip. Preferably a tube is disposed concentrically just inside the overflow line extending from a point just inside the reactor vessel to an overflow tank and a suction line is provided opening into the body of liquid metal in the reactor vessel and into the annulus between the overflow line and the inner tube.

Inventors:
 [1]
  1. (Pittsburgh, PA)
Publication Date:
Research Org.:
Westinghouse Electric Corp., Madison, Pa. Advanced Reactors Div.
OSTI Identifier:
862716
Patent Number(s):
US 3994777
Assignee:
United States of America as represented by United States Energy (Washington, DC) OSTI
DOE Contract Number:
AT(11-1)-3045
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
nuclear; reactor; overflow; line; vessel; liquid-metal-cooled; means; establishing; maintaining; continuous; bleed; flow; coolant; amounting; 10; total; prevent; thermal; shock; restarted; following; trip; preferably; tube; disposed; concentrically; inside; extending; tank; suction; provided; liquid; metal; annulus; inner; thermal shock; inner tube; reactor vessel; nuclear reactor; liquid metal; coolant flow; cooled nuclear; overflow line; metal-cooled nuclear; flow line; disposed concentrically; liquid-metal-cooled nuclear; line extending; continuous bleed; /376/976/

Citation Formats

Severson, Wayne J. Nuclear reactor overflow line. United States: N. p., 1976. Web.
Severson, Wayne J. Nuclear reactor overflow line. United States.
Severson, Wayne J. 1976. "Nuclear reactor overflow line". United States. doi:. https://www.osti.gov/servlets/purl/862716.
@article{osti_862716,
title = {Nuclear reactor overflow line},
author = {Severson, Wayne J.},
abstractNote = {The overflow line for the reactor vessel of a liquid-metal-cooled nuclear reactor includes means for establishing and maintaining a continuous bleed flow of coolant amounting to 5 to 10% of the total coolant flow through the overflow line to prevent thermal shock to the overflow line when the reactor is restarted following a trip. Preferably a tube is disposed concentrically just inside the overflow line extending from a point just inside the reactor vessel to an overflow tank and a suction line is provided opening into the body of liquid metal in the reactor vessel and into the annulus between the overflow line and the inner tube.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1976,
month = 1
}

Patent:

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  • The overflow line for the reactor vessel of a liquid-metal-cooled nuclear reactor includes means for establishing and maintaining a continuous bleed flow of coolant amounting to 5 to 10 percent of the total coolant flow through the overflow line to prevent thermal shock to the overflow line when the reactor is restarted following a trip. Preferably a tube is disposed concentrically just inside the overflow line extending from a point just inside the reactor vessel to an overflow tank and a suction line is provided opening into the body of liquid metal in the reactor vessel and into the annulusmore » between the overflow line and the inner tube. 2 claims, 2 figures.« less
  • A method is described of on-line synthesis of the local power in a nuclear reactor having rods which are inserted in and retracted from the reactor core axially to control the reactivity thereof and having fixed incore nuclear detectors distributed across the core. The method is operable despite misalignment of a rod and comprises: generating and storing reference signals representative of the power in the core under reference conditions at a plurality of specified locations across the core including the location of the detectors and additional locations at which it is desired to determine the local power; storing signals representativemore » of the positions of the rods under the reference conditions; detecting the positions of the rods with rod positions indicators; monitoring response signals generated by the detectors; adjusting the detector response signals to substantially eliminate the local effects thereon of changes in rod position from the reference conditions as detected by the rod position indicators; and generating deviation signals as the fractional difference between the adjusted detector response signals and the stored reference signals for the detector locations.« less
  • A water-cooled nuclear reactor is provided with a passive emergency shutdown and core cooling capability by providing it with emergency fuel element dispersal means operable from internal energy contained within the reactor pressure vessel for dispersing the core fuel content into an adjacent heat sink. In a preferred embodiment, the reactor is provided with especially designed fuel elements and fuel element guides to permit passive emergency core dispersal. The reactor shutdown mechanism also facilitates reactor refueling and permits selective on-line refueling during normal reactor operation.
  • A bundle of individual measuring lines extends through the cover of a reactor pressure vessel, the bundle extending into a tubular mounting having a multiplicity of extending tubes through which the individual lines of the bundle extend. In each tube the line is passed through a sleeve slidably inserted in the tube and having an inner portion soldered to the line and an outer portion welded to the tube's outer end. The length of the sleeve and tube between the soldered and welded joints is made sufficient to prevent the heat of welding from effecting the soldered joints. Each linemore » can be removed from its tube by cutting away the welded joint and removing the line with its sleeve from the tube. The line can be reinstalled by returning the sleeve to its tube and making a new welded joint with the sleeve spacing its soldered connection with the line far enough to prevent the welding heat from affecting the soldered joint between the sleeve and the line. 5 claims, 3 figures.« less