Tritium Extraction from Pb-17Li by Bubble Columns

Malara, C.

doi:10.13182/fst95-a30485

Cited by 6 publications

(2 citation statements)

References 11 publications

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“…However, 2-phase dispersion models have been studied for quite a long time within the context of tritium recovery systems, i.e. bubble columns [34,35], what can be applied for TBM design. First efforts on determining the bubble diameter and behavior in helium-cooled lithium lead (HCLL) blankets have been advanced in [33].…”

Section: Helium Transport Propertiesmentioning

confidence: 99%

Lead–lithium eutectic material database for nuclear fusion technology

Valls

Sedano

Batet

et al. 2008

Journal of Nuclear Materials

186

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Section: Helium Transport Propertiesmentioning

confidence: 99%

Lead–lithium eutectic material database for nuclear fusion technology

Valls

Sedano

Batet

et al. 2008

Journal of Nuclear Materials

186

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“…In order to reduce tritium retention in the liquid lithium-lead and meet the TBM design requirements, the upper limit of tritium partial pressure must be restricted to not more than 10 7 Pa. Using a pure helium purge or vacuum degassing can only reach 10 2 Pa. At low tritium levels, the transport of tritium from the liquid into the gas phase is limited by the diffusion process in the liquid and gas, and at the gas-liquid interface [7]. This paper describes experimental studies of the recycling of trace tritium by using purge helium gas and a hydrogen-deuterium gaseous mixture to collect tritium by isotope exchange, as a way of improving the recovery efficiency of tritium from the lithiumlead alloy residue, to lower molecular diffusion resistance of tritium in the liquid phase and the gas phase, and to reduce the retention time of the gas phase in the liquid phase.…”

Section: Introductionmentioning

confidence: 99%

Trace tritium recovery from the residue of liquid Li17Pb83 alloy

2010

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The liquid Li 17 Pb 83 alloy is a prominent breeder material for use in a fusion reactor. In the design of an effective tritium extraction system for the liquid lithium lead bubbler of the test blanket module of such a reactor, finding ways to strictly limit the losses of tritium and to minimize radioactive risks is very important. For this purpose, the isotope exchange process has been investigated as a means of trace tritium recovery from a model of the residue from Li 17 Pb 83 alloy. The results indicate that the isotope exchange process is an effective means of tritium recovery from the residue of Li 17 Pb 83 alloy, and the optimum composition of the exchange carrier gas is He + 0.1% D 2 . The exchange temperature and number of exchange steps are the main factors influencing the efficiency of tritium recovery from the residue. Trace tritium recovery efficiency increases with increasing exchange temperature and number of times of exchange. Tritium recovery efficiency can approach 80% when the residue is treated six times at 823 K. A gas-liquid two-phase contact model to describe the proceeding of tritium release from the liquid Li 17 Pb 83 alloy has been derived on the basis of this experiment.Li 17 Pb 83 alloy, tritium recovery, isotope exchange, carrier

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