TMIST-2 Transport Test

Longhurst, Glen R.

Idaho National Laboratory

关键词: Isotopic Exchange;    46 Instrumentation Related To Nuclear Science And Technology;    Flow Rate;    Scintillation Counting;    Hydrogen Isotopes;   

DOI  :  10.2172/928083
RP-ID  :  INL/EXT-08-13791
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  928083

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来源: UNT Digital Library

【 摘 要 】

In anticipation of the TMIST-2 experiment in the Advanced Test Reactor, there was a need to determine if the tritium that is expected to be observed at the outlet of the experiment would be seen or if it may be lost on its way from the experiment in the core to the measurement station. To assist in resolving that issue, a bench-scale experiment was conducted in the Idaho National Laboratory’s Safety and Tritium Applied Research (STAR) facility using deuterium and a mass spectrometer in lieu of tritium with ion chambers, bubblers, and scintillation counting. The experiment replicated the concentration of the hydrogen isotope, the flow rates anticipated, and the residence times. It was found that there was initial uptake on tubing walls, presumably due to oxidation of the hydrogen isotopes to water and adsorption or isotopic exchange, but that saturates relatively quickly, and once saturated, the concentration of deuterium at the outlet of the tubing system was essentially the same as it was at the experiment inlet under the conditions modeled in the experiment.