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Title: TMIST-2 Transport Test

Abstract

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.

Authors:
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NNSA
OSTI Identifier:
928083
Report Number(s):
INL/EXT-08-13791
TRN: US0804190
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
46 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; Bench Experiment; Reactor Experiment; TMIST; Tritium

Citation Formats

Glen R. Longhurst. TMIST-2 Transport Test. United States: N. p., 2008. Web. doi:10.2172/928083.
Glen R. Longhurst. TMIST-2 Transport Test. United States. doi:10.2172/928083.
Glen R. Longhurst. Fri . "TMIST-2 Transport Test". United States. doi:10.2172/928083. https://www.osti.gov/servlets/purl/928083.
@article{osti_928083,
title = {TMIST-2 Transport Test},
author = {Glen R. Longhurst},
abstractNote = {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.},
doi = {10.2172/928083},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2008},
month = {2}
}

Technical Report:

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