Improvements in and relating to isotope separation in a fusion power system
There is described an apparatus 100 for separating hydrogen isotopes from exhaust gas of a fusion power system. A gas comprising a mixture of isotopes is received at an inlet 111 and evenly distributed between a plurality of conduits 130, each conduit 130 receiving substantially the same input of ga...
Saved in:
Main Author | |
---|---|
Format | Patent |
Language | English |
Published |
01.03.2023
|
Subjects | |
Online Access | Get full text |
Cover
Loading…
Summary: | There is described an apparatus 100 for separating hydrogen isotopes from exhaust gas of a fusion power system. A gas comprising a mixture of isotopes is received at an inlet 111 and evenly distributed between a plurality of conduits 130, each conduit 130 receiving substantially the same input of gas. Each conduit 130 comprises a composition, e.g. a stationary-phase of palladium-coated alumina, configured to change a flow rate of a first isotope of the mixture of isotopes through the plurality of conduits. The first isotope is thereby separated from the mixture of isotopes according to its flow rate through the plurality of conduits 130 and exits through an outlet 112. For example, the flow rate of tritium in the exhaust gas through the composition in the conduits may be arranged to be faster/slower than that of protium and deuterium. |
---|---|
Bibliography: | Application Number: GB20220008705 |