Recent Results At The Tritium Systems Test Assembly
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Tritium Systems Test Assembly
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Author : Los Alamos National Laboratory
language : en
Publisher:
Release Date : 1989
Tritium Systems Test Assembly written by Los Alamos National Laboratory and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1989 with categories.
Recent Results At The Tritium Systems Test Assembly
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Author :
language : en
Publisher:
Release Date : 1988
Recent Results At The Tritium Systems Test Assembly written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1988 with categories.
The Tritium Systems Test Assembly (TSTA) project at Los Alamos is charged with developing and demonstrating the tritium technology required for the magnetic fusion energy program. Since June 1987 the project has been operated by Los Alamos National Laboratory under the joint funding of the US Department of Energy (DOE) and the Japan Atomic Energy Research Institute (JAERI). At TSTA the technology under development includes reactor exhaust gas processing technology and safety systems. This project is not currently investigating the processing of tritium extracted from a breeding blanket. The processing of tritium extracted from a breeding blanket is a possible upgrade to TSTA. This possible upgrade is the subject of an ongoing study among Los Alamos, JAERI and the Argonne National Laboratory (ANL). This installing such on upgraded process systems at TSTA in the 1990--1992 time frame. The exhaust gas processing system at TSTA is designed to demonstrate full-scale exhaust gas processing for a fusion machine of a size currently being designed for ITER. Of course, deuterium is also a major component of the exhaust gas. Current gas processing uses a total gas stream comprised of (approximately)65% deuterium, 35% tritium, 1-2% reactive impurities (currently nitrogen and methane) with the remaining gas hydrogen and helium. The tritium inventory required to process through this loop at this rate is about 110 g. The main process loop at TSTA has been operating at this flow rate since July 1987. In addition to the operation of the main process loop, a number of nonloop experiments are underway at TSTA. This paper will update the status of both loop and nonloop studies at Los Alamos.
Tritium Systems Test Assembly
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Author : James L. Anderson
language : en
Publisher:
Release Date : 1979
Tritium Systems Test Assembly written by James L. Anderson and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1979 with Hydrogen categories.
Three Tritium Systems Test Assembly Tsta Off Loop Experiments
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Author :
language : en
Publisher:
Release Date : 1993
Three Tritium Systems Test Assembly Tsta Off Loop Experiments written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1993 with categories.
This report contains the results from three different experiments. Experiment one was initiated to establish the possibility of using a soft elastomer in ITER (International Thermonuclear Experimental Reactor) applications. Used in this application, the sealing material is anticipated to be in tritium at pressures in the range of 1 x 10−3 torr for many years. Here two O-ring valve seals each of Viton-A, Buna-N, and EDPM were exposed to 1, 40, or 400 torr of tritium while being cycled open and closed approximately 11,500 times in 192 days. EDPM is the least susceptible to damage from the tritium. Both Buna-N and Viton-A showed deterioration following the first cycling at 400 torr. Using commercially available materials, the Tritium Systems Test Assembly (TSTA) designed and built a Portable Water Removal (PWR) Unit to reduce tritium oxide emissions during glovebox breaches. The PWR removes 99.9% of all tritium and saves between 0.7 and 3.5 curies of tritium oxide from being stacked during each of the five tests. Finally, a series of tests are done to determine whether the presence of SF6 changes the ability of palladium and platinum to catalyze the T2-O2 reaction to form T2O. No deterioration of the catalytic activity is observed. This is important because the Tokamak Fusion Test Reactor (TFTR) requires information about the effect of SF6, an electrical insulator, on the catalytic behavior of Pt and Pd in a T2 environment. This information is necessary for the accident analysis in the Safety Analysis Report for TFTR. This study is done using an apparatus supplied to TSTA by TFTR.
Tritium Systems Test Assembly
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Author : Los Alamos National Laboratory
language : en
Publisher:
Release Date : 1989
Tritium Systems Test Assembly written by Los Alamos National Laboratory and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1989 with categories.
Recent Palladium Membrane Reactor Development At The Tritium Systems Test Assembly
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Author :
language : en
Publisher:
Release Date : 1995
Recent Palladium Membrane Reactor Development At The Tritium Systems Test Assembly written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1995 with categories.
The palladium membrane reactor (PMR) is proving to be a simple and effective means for recovering hydrogen isotopes from fusion fuel impurities such as methane and water. This device directly combines two techniques which have long been utilized for hydrogen processing, namely catalytic shift reactions and palladium/silver permeators. A proof-of-principle (PMR) has been constructed and tested at the Tritium Systems Test Assembly of Los Alamos National Laboratory. The first tests with this device showed that is was effective for the proposed purpose. Initial work concluded that a nickel catalyst was an appropriate choice for use in a PMR. More detailed testing of the PMR with such a catalyst was performed and reported in other works. It was shown that a nickel catalyst-packed PMR did, indeed, recover hydrogen from water and methane with efficiencies approaching 100% in a single processing pass. These experiments were conducted over an extended period of time and no failure or need for regeneration was encountered. These positive results have prompted further PMR development. Topics addressed include alternate PMR geometries and initial testing of the PMR with tritium. These are the subjects of this paper.
Experience Of Tsta Tritium Systems Test Assembly Milestone Runs With 100 Grams Level Of Tritium
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Author :
language : en
Publisher:
Release Date : 1988
Experience Of Tsta Tritium Systems Test Assembly Milestone Runs With 100 Grams Level Of Tritium written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1988 with categories.
The first loop operation tests of the Tritium Systems Test Assembly (TSTA) with 100 grams-level of tritium were performed at the Los Alamos National Laboratory (LANL) in June and July, 1987. The July run was resumption of the June run, which was halted because of a loss of cryogenic refrigerant in the hydrogen isotope separation system. 3 refs., 3 figs.
Overview Of Tritium Processing Development At The Tritium Systems Test Assembly
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Author :
language : en
Publisher:
Release Date : 1986
Overview Of Tritium Processing Development At The Tritium Systems Test Assembly written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1986 with categories.
The Tritium Systems Test Assembly (TSTA) at the Los Alamos National Laboratory has been operating with tritium since June 1984. Presently there are some 50 g of tritium in the main processing loop. This 50 g has been sufficient to do a number of experiments involving the cryogenic distillation isotope separation system and to integrate the fuel cleanup system into the main fuel processing loop. In January 1986 two major experiments were conducted. During these experiments the fuel cleanup system was integrated, through the transfer pumping system, with the isotope separation system, thus permitting testing on the integrated fuel processing loop. This integration of these systems leaves only the main vacuum system to be integrated into the TSTA fuel processing loop. In September 1986 another major tritium experiment was performed in which the integrated loop was operated, the tritium inventory increased to 50 g and additional measurements on the performance of the distillation system were taken. In the period June 1984 through September 1986 the TSTA system has processed well over 108 Ci of tritium. Total tritium emissions to the environment over this period have been less than 15 Ci. Personnel exposures during this period have totaled less than 100 person-mRem. To date, the development of tritium technology at TSTA has proceeded in progressive and orderly steps. In two years of operation with tritium, no major design flows have been uncovered.
Early Experience With The Tritium Systems Test Assembly
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Author :
language : en
Publisher:
Release Date : 1983
Early Experience With The Tritium Systems Test Assembly written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1983 with categories.
The Tritium Systems Test Assembly (TSTA) project at Los Alamos is charged with developing and demonstrating the tritium technology required to fuel a deuterium-tritium burning fusion reactor and to develop and evaluate the personnel and environmental safety systems associated with the tritium facility. The TSTA project completed the construction phase in late 1982 and is currently in the component checkout and early experimental phase. Tritium introduction is scheduled for mid-summer 1983. Several major systems have been operated and tested with hydrogen and deuterium. These include the vacuum pump, the isotope separation system and the emergency tritium cleanup system. The results of the early experiments are summarized and the experimental programs for other systems are presented.
Development Of Tritium Technology At The Tritium Systems Test Assembly
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Author :
language : en
Publisher:
Release Date : 1982
Development Of Tritium Technology At The Tritium Systems Test Assembly written by and has been published by this book supported file pdf, txt, epub, kindle and other format this book has been release on 1982 with categories.
The Tritium Systems Test Assembly (TSTA) at the Los Alamos National Laboratory is dedicated to the development, demonstration, and interfacing of technologies related to the deuterium-tritium fuel cycle for large scale fusion reactor systems starting with the Fusion Engineering Device (FED) or the International Tokamak Reactor (INTOR). This paper briefly describes the fuel cycle and safety systems at TSTA including the Vacuum Facility, Fuel Cleanup, Isotope Separation, Transfer Pumping, Emergency Tritium Cleanup, Tritium Waste Treatment, Tritium Monitoring, Data Acquisition and Control, Emergency Power and Gas Analysis systems. Discussed in further detail is the experimental program proposed for the startup and testing of these systems.