Process for the separation of krypton from a radioactive waste g

Gas separation – Means within gas stream for conducting concentrate to collector

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55386, B01D 1508

Patent

active

046540563

ABSTRACT:
A process for the separation of krypton from a radioactive waste gas mixt which is released during the chemical dissolution of burned-down nuclear fuel particles, and which in a carrier gas such as air, in addition to krypton, also contains xenon, argon, nitrous oxide and residual gas components. The waste gas mixture flowing out from a resolver has xenon removed therefrom after purifying the waste gas of nitrous oxides and radioactive residual gas components, such as aerosols, iodine, tritium and carbon(C-14) dioxide; and wherein krypton is finally withdrawn from the residual gas mixture and then stored. The invention also relates to an arrangement for the implementation of the inventive process. Subsequent to the purifying of the waste gas mixture from nitrous oxides and radioactive residual gas components, such as aerosols and iodine, a portion of the waste gas mixture is reconveyed into the resolver, and wherein the remaining portion of the waste gas mixture is purified of tritium and carbon(C-14) dioxide, and after an adsorptive removal of xenon discontinuously flows through a preparative gas chromatograph in which the krypton is separated from the residual gas. The remaining portion of the waste gas mixture is thereafter purified of tritium and carbon(C-14), which are removed in the form of HTO or, in essence, 14CO.sub.2, and thereafter adsorptively freed from xenon. The remaining waste gas mixture containing krypton is discontinously conveyed to a preparative gas chromatograph in which the krypton is separated from the residual gas.

REFERENCES:
patent: 1906917 (1933-05-01), Peters et al.
patent: 4012490 (1977-03-01), Lofredo
patent: 4369048 (1983-01-01), Pence
patent: 4447353 (1984-05-01), Pence et al.
patent: 4469496 (1984-09-01), Frischmuth et al.

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