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Title: Energy absorber for sodium-heated heat exchanger

Abstract

A heat exchanger is described in which water-carrying tubes are heated by liquid sodium and in which the results of accidental contact between the water and the sodium caused by failure of one or more of the water tubes is minimized. An energy absorbing chamber contains a compressible gas and is connected to the body of flowing sodium by a channel so that, in the event of a sodium-water reaction, products of the reaction will partially fill the energy absorbing chamber to attenuate the rise in pressure within the heat exchanger.

Inventors:
Publication Date:
Research Org.:
Originating Research Org. not identified
OSTI Identifier:
4091780
Patent Number(s):
PAT-APPL-356,879.; US 3924675
Assignee:
to U.S. Energy Research and Development Administration TIC; NSA-33-028058
Resource Type:
Patent
Resource Relation:
Patent File Date: 1973 May 01; Other Information: F28f9/00. Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English
Subject:
N77500* -Reactors-Power Reactors, Breeding; 210500* -Nuclear Power Plants-Power Reactors, Breeding; *HEAT EXCHANGERS; *LMFBR TYPE REACTORS- HEAT EXCHANGERS; DESIGN; ENERGY ABSORPTION; KINETIC ENERGY; SAFETY; STEAM GENERATORS

Citation Formats

Essebaggers, J. Energy absorber for sodium-heated heat exchanger. United States: N. p., 1975. Web.
Essebaggers, J. Energy absorber for sodium-heated heat exchanger. United States.
Essebaggers, J. 1975. "Energy absorber for sodium-heated heat exchanger". United States. doi:.
@article{osti_4091780,
title = {Energy absorber for sodium-heated heat exchanger},
author = {Essebaggers, J.},
abstractNote = {A heat exchanger is described in which water-carrying tubes are heated by liquid sodium and in which the results of accidental contact between the water and the sodium caused by failure of one or more of the water tubes is minimized. An energy absorbing chamber contains a compressible gas and is connected to the body of flowing sodium by a channel so that, in the event of a sodium-water reaction, products of the reaction will partially fill the energy absorbing chamber to attenuate the rise in pressure within the heat exchanger.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 1975,
month =
}
  • A method is presented for locating a tube with a leak among heat exchanger tubes in which the primary fluid is sodium and the secondary fluid is steam or a liquid--steam mixture. The process is particularly suited for the location of microleaks. The technique used consists of detecting hydrogen in the sodium by diffusing this hydrogen across a membrane associated with a mass spectrometer. Improvements made to the initial method enable the bundle of tubes containing the leaking tube to be located with the hydrogen detection apparatus. (FR)
  • A heat exchanger comprising a tank for hot liquid and a plurality of concentric, double tubes for cool liquid extending vertically through the tank is described. These tubes are bonded throughout most of their length but have an unbonded portion at both ends. The inner tubes extend between headers located above and below the tanmk and the outer tubes are welded into tube sheets forming the top and bottom of the tank at locations in the unbonded portions of the tubes. (AEC)
  • This patent describes, in a steam generator utilized with a liquid sodium cooled nuclear reactor, provision is made to vent the violent sodium water reaction emanating from a tube rupture casualty. The steam generator includes a sodium plenum at the bottom thereof containing a conventional rupture disk for venting sodium, steam, and reaction products including hydrogen immediately upon a tube rupture casualty. The invention includes providing an alternative concentric flow path interior to the steam generator and parallel to the tube bundle. This alternative concentric flow path extends from the upper portion of the steam generator down into the lowermore » head or plenum adjacent to the pressure relief diaphragm. This alternate path is partially filled with sodium during normal reactor operation. In the event of a tube bundle break, the alternative flow path dumps its sodium through the conventional rupture disk and then provides an immediate alternate pressure release path in parallel with the tube bundle for steam and water flow from the tube rupture site to the rupture disk. This parallel flow path reduces the pressure differential from the water/steam flow through the tube bundle such that water/steam does not flow back through the intermediate heat transport system to the intermediate heat exchanger (IHX) where it would react with residual sodium and potentially damage the IHX tube bundle which is part of the reactor primary containment barrier.« less