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US4080429A Expired / Lapsed US ⏱️ 0.0 years remaining

Method of and apparatus for separating krypton from radioactive waste gases

Assignee: Forschungszentrum Jülich
•
Filing: 1975-06-02
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Granted: 1978-03-21
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Expires: 1995-06-02
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Abstract

Abstract A method of and apparatus for separating krypton from radioactive waste gases which become free during the chemical dissolution of burnt-off fuel particles and contain krypton and xenon. Simultaneously with the core fuel particles conveyed to the chemical dissolution, such quantity of chemically inactive carrier gas intermixable with the waste gases is added to the substances bringing about the chemical dissolution that after purification of the waste gas mixture from gas components such as oxygen, carbon dioxide, nitrous oxide, hydrocarbons and water steam and after subsequent cooling of the waste gas mixture to the boiling temperature of the liquid nitrogen, the quantity of xenon contained in the waste gas mixture is quantitatively precipitated in solid form. Thereupon the waste gas mixture is cooled by means of liquid nitrogen, while simultaneously increasing the pressure, to such an extent that krypton is precipitated. The apparatus for practicing the above mentioned method is characterized primarily in that a chamber communicating with a supply for the fuel particles and for carrier gas and equipped with a conveying device is provided with a connection to a dissolver. In a waste gas conduit connected to the dissolver are inserted in series a waste gas purifier, a nitrogen cooled container for separating solid xenon, a compressor for subjecting the waste gas mixture to a pressure of approximately 4 bars, and a nitrogen cooled separator for krypton with following shut-off device.

Inventors

  • 👤 Werner Koeppe
  • 👤 Josef Bohnenstingl
  • 👤 Stanislaus Gottfried Josef Mastera

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-06 13:08
CPC Classifications
G; G21; G21F; G21F9/00; G21F9/02; C; C01; C01B; C01B23/00; F; F25; F25J; F25J3/00; F25J3/06; F25J3/063; F25J3/0685; F25J2205/00; F25J2205/20; F25J2210/00; F25J2210/70; F25J2215/00; F25J2215/34; F25J2215/36; Y; Y02; Y02P; Y02P20/00; Y02P20/151; Y10; Y10S; Y10S422/00; Y10S422/903; Y10S62/00; Y10S62/923; Y10S62/925

Claims Analysis

Total Claims: 6
Claim 1
Independent Claim 161 words
In a process of reprocessing nuclear fuel particles by chemical dissolution to separate fission products and the disintegration products which form during reactor operation from reusable fuel materials wherein during said dissolution waste gases containing oxygen, carbon dioxide, nitrous oxides, hydrocarbons, and steam, xenon and radioactive krypton are released, the method of separating xenon and radioactive krypton from said waste gases comprising the steps of: adding a chemically inactive carrier gas to said fuel particles during the chemical dissolution step, withdrawing said carrier gas mixed with said waste gas mixture released in said dissolution step, removing oxygen, carbon dioxide, nitrous oxides and hydrocarbons and steam from the gaseous mixture, cooling the resultant gas mixture comprising xenon, radioactive krypton and carrier gas by means of liquid nitrogen to first precipitate xenon as a solid, thereafter increasing the pressure of the substantially xenon-free gas mixture and further cooling by means of liquid nitrogen to substantially separate krypton from said mixture in solid form.
Claim 2
Dependent Claim 161 words
In a process of reprocessing nuclear fuel particles by chemical dissolution to separate fission products and the disintegration products which form during reactor operation from reusable fuel materials wherein during said dissolution waste gases containing oxygen, carbon dioxide, nitrous oxides, hydrocarbons, and steam, xenon and radioactive krypton are released, the method of separating xenon and radioactive krypton from said waste gases comprising the steps of: adding a chemically inactive carrier gas to said fuel particles during the chemical dissolution step, withdrawing said carrier gas mixed with said waste gas mixture released in said dissolution step, removing oxygen, carbon dioxide, nitrous oxides and hydrocarbons and steam from the gaseous mixture, cooling the resultant gas mixture comprising xenon, radioactive krypton and carrier gas by means of liquid nitrogen to first precipitate xenon as a solid, thereafter increasing the pressure of the substantially xenon-free gas mixture and further cooling by means of liquid nitrogen to substantially separate krypton from said mixture in solid form.
Claim 3
Dependent Claim 28 words
A method according to claim 1, in which said waste gas mixture during the further cooling thereof is subjected to an increased pressure of at least 4 bars.
Claim 4
Dependent Claim 38 words
A method according to claim 1, which includes the step of adding to the waste gases such a quantity of chemically inactive carrier gas that the total partial pressure of krypton and xenon is lowered to approximately 16.7mb.
Claim 5
Dependent Claim 17 words
A method according to claim 1, in which helium is utilized as the chemically inactive carrier gas.
Claim 6
Dependent Claim 51 words
A method according to claim 1, in which from the waste gas mixture only a portion of the krypton contained therein is separated in solid form and that the residual waste gas mixture is subsequently conveyed into an adsorber comprising active carbon while the latter is further cooled by liquid nitrogen.

References Cited (Backward Citations)

US3203866A Cited
US3404067A Cited
US3748864A Cited
US3922150A Cited
US4012490A Cited
US3829551A Cited

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1981-03-20 1981-09-19 1982-03-21 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 1985-03-20 1985-09-19 1986-03-21 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 1989-03-20 1989-09-19 1990-03-21 $7700.00 Window Closed / Lapsed

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