An experimental evaluation of a small fusion fuel cleanup system
- 1. Atomic Energy of Canada Ltd., Chalk River, Ontario K0J 1J0
Description
Small tritium-burning experimental tokamaks will require some means of handling the fuel after a burn. This paper presents an experimental evaluation of a scheme that would provide for the removal of the impurities produced in the fuel during the burn and delivery of the purified fuel for a subsequent burn in the machine. The fuel, simulated in this work by a hydrogen-impurity mixture, is taken from the machine, diluted to 25% with helium and passed through a uranium metal bed at 250C, where the hydrogen is trapped reversibly and several of the impurities are irreversibly absorbed. The results showed complete removal of O/sub 2/, CO, CO/sub 2/, H/sub 2/O and N/sub 2/O at room temperature. Removal of CH/sub 4/ and NH/sub 3/ required the uranium to be heated to approximately 4000C. At 4000C the hydrogen is released from the uranium metal, so the cleanup scheme requires circulation of the gas through two uranium beds, one at room temperature and one at near 4000C. When all the impurities are reacted the low temperature uranium bed is heated to 4000C to release the hydrogen back into the system in preparation for reinjection into the machine. An apparatus, simulating a small fusion fuel cleanup system, was built and demonstrated
Additional details
Publishing Information
- Journal Title
- Fusion Technol.
- Journal Volume
- 10
- Journal Issue
- 3
- Series
- Fusion Technol.
- Journal Page Range
- 1340-1344
- ISSN
- 0748-1896
- CODEN
- FUSTE
Conference
- Title
- 7. topical meeting on the technology of fusion energy.
- Dates
- 15-19 Jun 1986.
- Place
- Reno, NV (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18041152
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ADSORPTION; BURNUP; CARBON DIOXIDE; CARBON MONOXIDE; DECONTAMINATION; HIGH TEMPERATURE; HYDROGEN; IMPURITIES; NITROGEN OXIDES; OXYGEN; RADIOACTIVE WASTE PROCESSING; RECYCLING; RESEARCH PROGRAMS; SEPARATION PROCESSES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TRITIUM; URANIUM; WASTE PRODUCT UTILIZATION; WATER
- Descriptors DEC
- ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CARBON COMPOUNDS; CARBON OXIDES; CHALCOGENIDES; CLEANING; CLOSED PLASMA DEVICES; ELEMENTS; HYDROGEN COMPOUNDS; HYDROGEN ISOTOPES; ISOTOPES; LIGHT NUCLEI; MANAGEMENT; METALS; NITROGEN COMPOUNDS; NONMETALS; NUCLEI; ODD-EVEN NUCLEI; OXIDES; OXYGEN COMPOUNDS; POLAR SOLVENTS; RADIOISOTOPES; SOLVENTS; THERMONUCLEAR DEVICES; WASTE MANAGEMENT; WASTE PROCESSING; YEARS LIVING RADIOISOTOPES
Optional Information
- Secondary number(s)
- CONF-860652--.