US4331522A
Expired / Lapsed
US
⏱️ 0.0 years remaining
Reprocessing of spent plasma
Assignee: European Atomic Energy Community Euratom
•
Filing: 1981-01-12
•
Granted: 1982-05-25
•
Expires: 2001-01-12
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 14:08
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 |