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TMIST-2 Transport Test
| 题名： | TMIST-2 Transport Test |
| 作者： | Glen R. Longhurst; |
| 关键词： | Bench Experiment; Reactor Experiment; TMIST; Tritium46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEFENSE; ADSORPTION; BENCH-SCALE EXPERIMENTS; DEUTERIUM; FLOW RATE; HYDROGEN ISOTOPES; IDAHO; ISOTOPIC EXCHANGE; MASS SPECTROMETERS; OXIDATION; SAFETY; SCINTILLATION COUNTING; TEST REACTORS; TRANSPORT; TRITIUM; WATER |
| 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鈥檚 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. |
| 报告类型： | 科技报告 |
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