摘要 :
Reacting tritiated water with hot metal to recover the tritium from tritiated water has been practiced for considerable time. A metal frequently used for this purpose has been uranium. Recent work at the Tritium Systems Test Assem...
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Reacting tritiated water with hot metal to recover the tritium from tritiated water has been practiced for considerable time. A metal frequently used for this purpose has been uranium. Recent work at the Tritium Systems Test Assembly at Los Alamos National Laboratory has focused on using magnesium for this purpose. This work was done as part of the Annex IV collaboration between the US Department of Energy/TSTA and the Japan Atomic Energy Research Institute/Tritium Processing Laboratory. Magnesium appears to have reactive properties that are as good as uranium and possibly better, and, of course, magnesium is easier to handle and less strictly controlled. Both bench-scale and practical-scale experiments were conducted with magnesium, including tests with tritiated water. Mg bed construction techniques and operating parameters were determined. Testing showed that the Mg packed bed was very effective for recovering hydrogen isotopes from water. However, when used for this purpose either Mg or U is irreversibly consumed and must be disposed of as tritiated waste. It follows that this processing technique would be inappropriate for a large tritiated water processing operation. However, this technique may find utility for small-scale systems.
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The chemical processes by which elemental tritium can be converted to tritiated water have been examined by reviewing the available literature on these processes. It would appear that gas phase conversion reactions at room tempera...
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The chemical processes by which elemental tritium can be converted to tritiated water have been examined by reviewing the available literature on these processes. It would appear that gas phase conversion reactions at room temperature are slow and that they do not contribute significantly to any observed conversion following releases of elemental tritium. The effects of surfaces are not clearly understood. Metals, however, can increase the rate over the gas phase processes, but the magnitude of this increase is not well documented. Further work is necessary to examine the effects of various materials, elevated temperatures, and other parameters on conversion reactions in order to more closely reflect conditions in reactor buildings and other tritium containing facilities. (Atomindex citation 16:043730)
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There have been many significant changes in the status of tritium activities in the US since the 4th Tritium Conference in October, 1991. The replacement Tritium Facility (RTF) at Savannah River Site and the Weapons Engineering Tr...
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There have been many significant changes in the status of tritium activities in the US since the 4th Tritium Conference in October, 1991. The replacement Tritium Facility (RTF) at Savannah River Site and the Weapons Engineering Tritium Facility (WETF) at the Los Alamos National Laboratory are now operational with tritium. The Tokamak Fusion Test Reactor (TFTR) has initiated a highly successful experimental campaign studying DT plasmas, and has produced more than 10 Megawatts (MW) of fusion power in a D-T plasma. Sandia National Laboratory has ceased tritium operations at the Tritium Research Laboratory (TRL) and many of the activities previously performed there have been transferred to Los Alamos and Savannah River. The tritium laboratory at Lawrence Livermore National Laboratory has reduced the tritium inventory to <5 grams. The Tritium Systems Test Assembly (TSTA) at Los Alamos continues to be at the forefront of tritium technology and safety development for the fusion energy program.
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In the extended Annex IV (1992-1994), it was aimed to perform realistic non-steady condition experiments of the fuel loop and Breeding Blanket Interface (BBI) experiments. It was proposed to use the combination process of Cryo-Mol...
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In the extended Annex IV (1992-1994), it was aimed to perform realistic non-steady condition experiments of the fuel loop and Breeding Blanket Interface (BBI) experiments. It was proposed to use the combination process of Cryo-Molecular Sieve Bed (CMSB) and Palladium Diffuser (PD) for the recovery and purification of tritium in the Breeding Blanket purge stream. The BBI campaign experiment by using the CMSB of TSTA-FCU and the PD of JFCU was performed for the recovery of tritium from the simulated Breeding Blanket purge stream in the flow rate of 12.61/min. It was demonstrated that the proposed combination process has the feasibility as the Blanket Tritium Recovery System in fusion plant. This report summarizes the experimental result and analysis of the simulated BBI experiment. (author). (ERA citation 20:028371)
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The report summarizes present information on the atmospheric reactions of tritium. The global distribution of hydrogen and of water is first considered. Data on tritium distribution are then compared and, finally, known reactions ...
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The report summarizes present information on the atmospheric reactions of tritium. The global distribution of hydrogen and of water is first considered. Data on tritium distribution are then compared and, finally, known reactions which may convert tritiated hydrogen-containing molecules are discussed. Approximately 99 percent of the world's inventory of tritium exists as HTO. Although most of it is in the ocean, a significant portion still resides in the stratosphere. However, in the troposphere, which is the primary concern of this review, most of the tritium is in the form of HT, a smaller amount as HTO, and a much smaller but still significant amount as CH sub 3 T. Further, the tritium-to-hydrogen ratio in the troposphere is higher in hydrogen and in methane than it is in water vapor. The formation of HTO by exchange of HT or T sub 2 with water or by direct oxidation with oxygen, in the absence of catalysts, is extremely slow at concentrations in the atmosphere that might exist a few minutes after a tritium release. Photochemical oxidation may be the predominant conversion mechanism and over larger periods of time may combine with bacterial action to serve as the principal pathways of conversion of HT (or T sub 2 ) and CH sub 3 T to HTO or other more reactive forms of tritium. The net conversion rate following a tritium release to the atmosphere would be expected to be less than 1 percent in 24 hr. The significance of the relatively high tritium content in atmospheric methane needs evaluation. Monitoring of CH sub 3 T has been largely neglected in the past. Considerable uncertainty exists in some of the data on which these conclusions are based and recommendations are made for further work. (ERA citation 02:025167)
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The purpose of the Management Plan is to describe the scope and responsibilities of the Accelerator Production of Tritium (APT) Plant Project Office (PPO); the PPO organization; guiding vision and strategies; and PPO work processes and controls.
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The purpose of the Management Plan is to describe the scope and responsibilities211 of the Accelerator Production of Tritium (APT) Plant Project Office (PPO); the 211 PPO organization; guiding vision and strategies; and PPO work p...
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The purpose of the Management Plan is to describe the scope and responsibilities211 of the Accelerator Production of Tritium (APT) Plant Project Office (PPO); the 211 PPO organization; guiding vision and strategies; and PPO work processes and 211 controls.
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JAERI designed, fabricated, and installed the JAERI Fuel Cleanup System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA. The main function of the J-FCU is to purify and to recover hydrogen isotopes from simulated ...
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JAERI designed, fabricated, and installed the JAERI Fuel Cleanup System (J-FCU) as a subsystem of simulated fusion fuel loop at the TSTA. The main function of the J-FCU is to purify and to recover hydrogen isotopes from simulated plasma exhaust while exhausting tritium free impurities. After a lot of deuterium tests, a first tritium test of the J-FCU was performed with one gram of tritium at the TSTA on June 1991. Main purpose of this test was to evaluate the total integrity and function of the J-FCU system with a DT mixture. Through this test, the J-FCU was operated well and its function with tritium was demonstrated. This report describes the detail test results of the J-FCU first tritium test and discuss its functions by stand-alone mode. Residual tritium inventory of the J-FCU system was also discussed. (author). (ERA citation 19:006083)
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The reactivity of tritium is largely determined by a steady state ion concentration of about one part in 10(sup 9) of the background molecules. These ions determine the reaction rates with other materials, and impurities of the or...
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The reactivity of tritium is largely determined by a steady state ion concentration of about one part in 10(sup 9) of the background molecules. These ions determine the reaction rates with other materials, and impurities of the order of 1 ppM can be shown to determine on which species the ion resides. In pure tritium, T(sub 3+) changes to T(sub 5+) as the pressure is increased above a few thousand pascals (10 torr). In the presence of common impurities, the ions CT(sub 5+), T(sub 3)O(sup +), and N(sub 2)T(sup +) become dominant. Rarely, because of the large energy involved, N(sup +) is formed which leads to NT(sub 4+). It is shown that when the ion resides on the impurity such as CH(sub 4)T(sup +), the exchange only takes place during methane-methane collisions and thus it is slow. 10 refs., 2 figs., 1 tab. (ERA citation 13:047086)
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