Iniotakis et al., 1985 - Google Patents
Hydrogen permeation wall, process for manufacturing this and its useIniotakis et al., 1985
View PDF- Document ID
- 4027813593753766183
- Author
- Iniotakis N
- von der Decken C
- Froehling W
- Publication year
External Links
Snippet
[en] Thin hydrogen permeation walls are obtained by galvanic separation of metal permeable by hydrogen on a fine-meshed metal grid with a thickness of at least half the mesh width. The permeation walls produced in this way combine mechanical stability with …
- 229910052739 hydrogen 0 title abstract 5
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| EP0141176B1 (en) | Permeable membrane for hydrogen, its manufacturing method and use | |
| DE3606316C2 (en) | ||
| DE2545001C2 (en) | ||
| DE3222633A1 (en) | OXYGEN STABILIZED ZIRCON VANADIUM IRON ALLOY | |
| Iniotakis et al. | Hydrogen permeation wall, process for manufacturing this and its use | |
| DE3606317A1 (en) | METHOD AND DEVICE FOR DECONTAMINATING THE EXHAUST GAS FROM THE FUEL CYCLE OF A FUSION REACTOR OF TRITIUM AND / OR DEUTERIUM IN CHEMICALLY BONDED EXHAUST GAS COMPONENTS | |
| DE69206302T2 (en) | Process for producing hydrogen gas and process for determining the mass ratio between the hydrogen isotopes. | |
| DE2314798C3 (en) | Double encapsulated californium 252 oxide containing small size neutron source | |
| DE3932670A1 (en) | RADIOACTIVE CATALYST | |
| WO1995008827A1 (en) | Nuclear fuel sintered body and process for producing it | |
| Penzhorn et al. | Process and device for the decontamination of the waste gas of the fuel cycle of a fusion reactor of waste gas components containing tritium and/or deuterium in chemically bound form | |
| DE3318611C2 (en) | ||
| Niemann et al. | Process for the production of a uranium compound enriched with uranium 235 as nuclear fuel for nuclear reactors | |
| Boyle et al. | Absorber for gaseous tritium and process for its manufacture | |
| DE2322954C3 (en) | Process for the production of an ionizing radiation source | |
| Wieland et al. | Detector for determining the tritium concentration in gases | |
| Erhardt et al. | Method and equipment to fabricate superconducting material | |
| Shmayda et al. | Process and device for separating hydrogen from a mixture, particularly a mixture of gases | |
| Penzhorn et al. | Process and device for decontamination of the waste gas of the fuel circuit of a fusion reactor from tritium and/or deuterium in waste gas containing them in chemically bound form | |
| Teitel | Method of utilization of the radiation generated by nuclear fusion | |
| Iniotakis et al. | Process for separating hydrogen and/or deuterium and tritium from a flow of inert gas and device for carrying out the process in the coolant gas circuit of a gas-cooled nuclear reactor | |
| DE3221315A1 (en) | DEVICE FOR THE OXIDATION OR REDUCTION OF OXIDIZABLE OR REDUCABLE SUBSTANCES IN AQUEOUS SOLUTION | |
| DE2160201C3 (en) | Process for the production of an electrode frame made of nickel for electrodes in galvanic elements | |
| Ringel et al. | Sorption column for the separation of protactinium from a nuclear fuel solution | |
| Friedrich et al. | Detector for determining the tritium concentration in gases |