1986
DOI: 10.1016/s0022-3115(86)80048-4
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The time dependence of in-situ tritium release from lithium oxide and lithium aluminate (VOM-22H experiment)

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Cited by 37 publications
(3 citation statements)
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“…The liberation of tritium from neutron-irradiated lithium ceramics involves the diffusive motion of the tritium atom within the solid and its subsequent release from the ceramic surface [37][38][39][40][41]. It is important to distinguish the rate-controlling step contributing to tritium release.…”
Section: Tritium Transport and Releasementioning
confidence: 99%
“…The liberation of tritium from neutron-irradiated lithium ceramics involves the diffusive motion of the tritium atom within the solid and its subsequent release from the ceramic surface [37][38][39][40][41]. It is important to distinguish the rate-controlling step contributing to tritium release.…”
Section: Tritium Transport and Releasementioning
confidence: 99%
“…Each gas stream is instrumented to continuously monitor the flow rate, total moisture, tritium concentration, and the form of the tritium. The total tritium concentration and form of the tritium is determined in a manner similar to the VOMexperiment (Kurasawa 1986) and uses a ceramic electrolysis cell (CEC) to reduce the water vapor (Konishi et al 1987) and a molecular sieve trap to remove the water vapor from the sweep gas. The complete data set was continuouslymonitoredand stored on data disks at the experimentsite at the FFTF.…”
Section: Phase Ii: Scopementioning
confidence: 99%
“…One performance characteristic o f a solid breeder material which will be monitored is the in situ tritium release behavior. There has been some success in correlating time dependent tritium release predictions from diffusional theories with data taken from mixed spectrum in situ tritium recovery tests (Clemmer et al 1984; Kurasawa et al 1986; Verall/Miller 1987). The purpose of BEATRIX-11 is to examine the kinetics of tritium release at higher burnup levels and more homogeneous burnup and heat generation conditions similar to those anticipated in ITER and commercial fusion blankets.…”
Section: Whc-sp-0224mentioning
confidence: 99%