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Title: Method and apparatus for separating radionuclides from non-radionuclides

Abstract

In an apparatus for separating radionuclides from non-radionuclides in a mixture of nuclear waste, a vessel is provided wherein the mixture is heated to a temperature greater than the temperature of vaporization for the non-radionuclides but less than the temperature of vaporization for the radionuclides. Consequently the non-radionuclides are vaporized while the non-radionuclides remain the solid or liquid state. The non-radionuclide vapors are withdrawn from the vessel and condensed to produce a flow of condensate. When this flow decreases the heat is reduced to prevent temperature spikes which might otherwise vaporize the radionuclides. The vessel is removed and capped with the radioactive components of the apparatus and multiple batches of the radionuclide residue disposed therein. Thus the vessel ultimately provides a burial vehicle for all of the radioactive components of the process.

Inventors:
 [1]
  1. (18746 Viking Way, Cerritos, CA 90701)
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
OSTI Identifier:
867238
Patent Number(s):
US 4892684
Assignee:
Harp, Richard J. (18746 Viking Way, Cerritos, CA 90701) LLNL
DOE Contract Number:
W-7405-ENG-48
Resource Type:
Patent
Country of Publication:
United States
Language:
English
Subject:
method; apparatus; separating; radionuclides; non-radionuclides; mixture; nuclear; waste; vessel; provided; heated; temperature; vaporization; consequently; vaporized; remain; solid; liquid; non-radionuclide; vapors; withdrawn; condensed; produce; flow; condensate; decreases; heat; reduced; prevent; spikes; otherwise; vaporize; removed; capped; radioactive; components; multiple; batches; radionuclide; residue; disposed; therein; ultimately; provides; burial; vehicle; process; nuclear waste; disposed therein; radioactive components; active components; separating radionuclides; active component; /588/376/976/

Citation Formats

Harp, Richard J. Method and apparatus for separating radionuclides from non-radionuclides. United States: N. p., 1990. Web.
Harp, Richard J. Method and apparatus for separating radionuclides from non-radionuclides. United States.
Harp, Richard J. Mon . "Method and apparatus for separating radionuclides from non-radionuclides". United States. doi:. https://www.osti.gov/servlets/purl/867238.
@article{osti_867238,
title = {Method and apparatus for separating radionuclides from non-radionuclides},
author = {Harp, Richard J.},
abstractNote = {In an apparatus for separating radionuclides from non-radionuclides in a mixture of nuclear waste, a vessel is provided wherein the mixture is heated to a temperature greater than the temperature of vaporization for the non-radionuclides but less than the temperature of vaporization for the radionuclides. Consequently the non-radionuclides are vaporized while the non-radionuclides remain the solid or liquid state. The non-radionuclide vapors are withdrawn from the vessel and condensed to produce a flow of condensate. When this flow decreases the heat is reduced to prevent temperature spikes which might otherwise vaporize the radionuclides. The vessel is removed and capped with the radioactive components of the apparatus and multiple batches of the radionuclide residue disposed therein. Thus the vessel ultimately provides a burial vehicle for all of the radioactive components of the process.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 1990},
month = {Mon Jan 01 00:00:00 EST 1990}
}

Patent:

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  • This patent describes apparatus for Separating radionuclides from non-radionuclides. It comprises: a reactor vessel including wall members defining a reactor chamber adapted to receive a mixture of the radionuclides and non-radionuclides in a solid or liquid phase; the radionuclides having temperatures of vaporization higher than a first temperature; the non-radionuclides having temperatures of vaporization lower than a second temperature; means for heating the mixture in the chamber to a temperature greater than the second temperature but less than the first temperature to drive the non-radionuclides to a vapor phase while retaining the radionuclides in a solid or liquid phase; andmore » means for removing the vapors of the non-radionuclides from the chamber. Whereby substantially all of the non-radionuclides exist the chamber in a vapor phase while the radionuclides remain within the chamber in a solid or liquid phase. Also described is a method for disposing of radionuclides present in a mixture of non-radionuclides and radionuclides.« less
  • The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixture is a hydrochloric acid mixture; (b) oxidizing the acidic mixture and specifically oxidizing the impurity to its highest oxidation state; and (c) passing the oxidized mixture through a chloride form anion exchange column whereupon the oxidized impurity absorbs to the chloride form anion exchange column and the {sup 229}Th or {sup 227}Ac ``cow`` radionuclide passes through themore » chloride form anion exchange column. The plutonium is removed for the purpose of obtaining other alpha emitting radionuclides in a highly purified form suitable for medical therapy. In addition to plutonium, lead, iron, cobalt, copper, uranium, and other metallic cations that form chloride anionic complexes that may be present in the mixture are removed from the mixture on the chloride form anion exchange column. 8 figs.« less
  • The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixture is a hydrochloric acid mixture; (b) oxidizing the acidic mixture and specifically oxidizing the impurity to its highest oxidation state; and (c) passing the oxidized mixture through a chloride form anion exchange column whereupon the oxidized impurity absorbs to the chloride form anion exchange column and the 22.sup.9 Th or 2.sup.27 Ac "cow" radionuclide passes through themore » chloride form anion exchange column. The plutonium is removed for the purpose of obtaining other alpha emitting radionuclides in a highly purified form suitable for medical therapy. In addition to plutonium; lead, iron, cobalt, copper, uranium, and other metallic cations that form chloride anionic complexes that may be present in the mixture; are removed from the mixture on the chloride form anion exchange column.« less
  • The continuous casting of strip, ribbon and wire is improved by using a free jet nozzle which provides a fluid that follows a rotating substrate surface to the separation point. The nozzle includes an inclined surface having a ratio of its length to the gap between the substrate and the nozzle edge of 5:1 to 15:1. The inclined surface improves the ability of the jet to tangentially follow the substrate in a direction opposite to its rotation to the separation point. This also allows a close positioning of the nozzle to the substrate which serves to provide a back-up mechanicalmore » separation means by using the edge of nozzle lip. The nozzle may be rotated from its operating position for cleaning of the substrate and the nozzle.« less