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US4331522A Expired / Lapsed US ⏱️ 0.0 years remaining

Reprocessing of spent plasma

Assignee: European Atomic Energy Community Euratom
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Filing: 1981-01-12
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Granted: 1982-05-25
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Expires: 2001-01-12
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Abstract

Abstract A process for removing helium and other impurities from a mixture containing deuterium and tritium, which process comprises the following steps: separating the isotopes of hydrogen from the impurity by catalytic oxidation; condensing out the oxides H 2 O, D 2 O and T 2 O thus formed; separating by electrolysis a portion of the said oxides in an electrolytic cell in order to produce a protium-rich portion; distillating the protium-rich portion to separate deuterium and tritium oxides from a distillate rich in water; and electrolyzing the condensate of the distillation step and the non-electrolyzed portion of the first electrolyzing step in order to form a mixture of deuterium and tritium. Preferably the impure mixture of deuterium and tritium is a waste product of a fusion reactor and the purified deuterium-tritium mixture is recycled to the reactor.

Inventors

  • 👤 Giancarlo Pierini

Bibliographic Details

Application Number —
Jurisdiction US
Data Source google_patents
Last Synchronized 2026-11-07 14:18
CPC Classifications
C; C01; C01B; C01B4/00

Claims Analysis

Total Claims: 9
Claim 1
Independent Claim 105 words
A process for removing helium and other impurities from a mixture containing deuterium and tritium, which process comprises the following steps: separating out isotopes of hydrogen from the mixture by catalytic oxidation; condensing out hydrogen isotope oxides thus formed; separating by electrolysis a portion of the said oxides in an electrolytic cell in order to produce a protium-rich portion and a non-electrolysed portion distillating the protium-rich portion to separate deuterium and tritium oxides from a distillate rich in water; and electrolysing condensate from the distillation step and the non-electrolysed portion of the electrolysis separation step in order to form a mixture of deuterium and tritium.
Claim 2
Dependent Claim 105 words
A process for removing helium and other impurities from a mixture containing deuterium and tritium, which process comprises the following steps: separating out isotopes of hydrogen from the mixture by catalytic oxidation; condensing out hydrogen isotope oxides thus formed; separating by electrolysis a portion of the said oxides in an electrolytic cell in order to produce a protium-rich portion and a non-electrolysed portion distillating the protium-rich portion to separate deuterium and tritium oxides from a distillate rich in water; and electrolysing condensate from the distillation step and the non-electrolysed portion of the electrolysis separation step in order to form a mixture of deuterium and tritium.
Claim 3
Dependent Claim 37 words
A process as claimed in claim 1 wherein a major portion of protium in the form of water in the said protium-rich portion is separated from other hydrogen isotope oxides by electrolysis using a selective ionic membrane.
Claim 4
Dependent Claim 22 words
A process as claimed in claim 1 wherein a minor portion of the said oxides is separated by distillation under reduced pressure.
Claim 5
Dependent Claim 16 words
A process as claimed in claim 2 wherein the said other hydrogen isotope oxides are electrolysed.
Claim 6
Dependent Claim 43 words
A process as claimed in claim 1 wherein waste products from the catalytic oxidation step, from the distillation step and from the electrolysis steps, including radiolysis products, are oxidised and absorbed by a molecular sieve drier system; any remaining inactive gases being vented.
Claim 7
Dependent Claim 46 words
A process as claimed in claim 3 wherein distillate from the said minor portion is subjected to complementary purification by multi-stage electrolysis in order to recover tritium in any of its diatomic oxide forms; which recovered tritium is then recycled to the said oxide distillation step.
Claim 8
Dependent Claim 23 words
A process as claimed in claim 1 wherein most of the said process steps handle tritium in the form of its liquid oxides.
Claim 9
Dependent Claim 47 words
A process as claimed in any one of the preceding claims wherein the said mixture of deuterium and tritium to be processed is a waste product of a fusion reactor and wherein the mixture of deuterium and tritium formed after processing is recycled to the said reactor.

References Cited (Backward Citations)

US4191626A Cited

USPTO Annuity & Maintenance Windows

Annuity Stage Window Opens Payment Deadline Surcharge Period Until Estimated Fee Status
3.5 Years (Year 4) 1985-05-24 1985-11-23 1986-05-25 $2000.00 Window Closed / Lapsed
7.5 Years (Year 8) 1989-05-24 1989-11-23 1990-05-25 $3760.00 Window Closed / Lapsed
11.5 Years (Year 12) 1993-05-24 1993-11-23 1994-05-25 $7700.00 Window Closed / Lapsed

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