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Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
In January 1977 the Los Alamos Scientific Laboratory started designing the Tritium Systems Test Assembly (TSTA) to support the national fusion energy program. We have now designed all the necessary systems and are proceeding with the fabrication and installation of equipment at the TSTA facility. TSTA will be capable of processing fusion-reactor quantities of DT gas by early 1982. Units which we have already built and installed include the building utilities and ventilation, the Emergency Tritium Cleanup (ETC) and Tritium Waste Treatment (TWT) modules, and the cryogenic Isotope Separation System (ISS). We have contracted for the outside fabrication of a DT Fuel Clean-Up (FCU) package to be installed in 1981. We are now assembling on site the plasma chamber evacuation (VAC) and DT gas Transfer Pumping (TPU) modules and the computer-based Master Data Acquisition and Control (MDAC) system.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
In January 1977 the Los Alamos Scientific Laboratory started designing the Tritium Systems Test Assembly (TSTA) to support the national fusion energy program. We have now designed all the necessary systems and are proceeding with the fabrication and installation of equipment at the TSTA facility. TSTA will be capable of processing fusion-reactor quantities of DT gas by early 1982. Units which we have already built and installed include the building utilities and ventilation, the Emergency Tritium Cleanup (ETC) and Tritium Waste Treatment (TWT) modules, and the cryogenic Isotope Separation System (ISS). We have contracted for the outside fabrication of a DT Fuel Clean-Up (FCU) package to be installed in 1981. We are now assembling on site the plasma chamber evacuation (VAC) and DT gas Transfer Pumping (TPU) modules and the computer-based Master Data Acquisition and Control (MDAC) system.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
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.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
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.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
This document has been prepared for the Major Device Fabrication Review for the Tritium Systems Test Assembly (TSTA). The TSTA is dedicated to the development, demonstration, and interfacing of technologies related to the deuterium-tritium fuel cycle for fusion reactor systems. The principal objectives for TSTA are: (a) demonstrate the fuel cycle for fusion reactor systems; (b) develop test and qualify equipment for tritium service in the fusion program; (c) develop and test environmental and personnel protective systems; (d) evaluate long-term reliability of components; (e) demonstrate long-term safe handling of tritium with no major releases or incidents; and (f) investigate and evaluate the response of the fuel cycle and environmental packages to normal, off-normal, and emergency situations. This document presents the current status of a conceptual design and cost estimate for TSTA. The total cost to design, construct, and operate TSTA through FY-1981 is estimated to be approximately $12.2 M.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Tritium Systems Test Assembly (TSTA) is dedicated to the development, demonstration, and interfacing of technologies related to the deuterium-tritium fuel cycle for fusion reactor systems. The principal objectives for TSTA are: (a) demonstrate the fuel cycle for fusion reactor systems; (b) develop test and qualify equipment for tritium service in the fusion program; (c) develop and test environmental and personnel protective systems; (d) evaluate long-term reliability of components; (e) demonstrate long-term safe handling of tritium with no major releases or incidents; and (f) investigate and evaluate the response of the fuel cycle and environmental packages to normal, off-normal, and emergency situations.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
The Tritium Systems Test Assembly (TSTA) is a computer-controlled facility designed to mock up full-scale the deuterium-tritium fuel cycle of next-generation tokamak fusion test reactors. Such reactors will use or build on the experience and technologies of the TSTA and other engineering facilities. The TSTA is presently under construction at the Los Alamos Scientific Laboratory and will be fully operational in 1982.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
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.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
In March of 1988 full operation of the 4-column isotope separation system (ISS) was realized in runs that approximated the design load of tritium. Previous operations had been fraught with operating difficulties principally due to external systems. This report will examine the recent highly successful 6-day period of operation. During this time the system was cooled from room temperature, loaded with hydrogen isotopes including 109 grams of tritium, integrated with the transfer pumping, impurity injection, and impurity removal systems, as well as the remote computer control system. At the end of the operation 12 grams of tritium having a measured purity of 99.987% (remainder deuterium) were offloaded from the system. Observed profiles in the columns in general agree with computer models. A Height Equivalent to a Theoretical Plate (HETP) of 5.0 cm is confirmed. 3 refs., 5 figs.
Author: Publisher: ISBN: Category : Languages : en Pages :
Book Description
Operating procedures are important for the safe and efficient operation of the Tritium Systems Test Assembly (TSTA). TSTA has been operating for four years with tritium in a safe and efficient manner. The inventory of tritium in the process loop is 100 grams and several milestone runs have been completed. This paper describes the methods used to operate TSTA. 3 refs., 1 fig.
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Author: Los Alamos National Laboratory
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