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First wall/blanket/shield design and optimization system

Description: First wall/blanket/shield design and optimization system (BSDOS) has been developed to provide a state-of-the-art design tool for fast accurate analysis. In addition, it has been designed to perform several other functions: (1) allowing comparison and evaluation studies for different concepts using the same data bases and ground rules, (2) permitting the use of any figure of merit in the evaluation studies, (3) optimizing the first wall/blanket/shield design parameters for any figure of merit u… more
Date: February 1, 1988
Creator: Gohar, Y.; Baker, C.; Attaya, H.; Cha, Y.; Majumdar, S. & Scandora, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The safety record at the tritium systems test assembly

Description: This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary … more
Date: February 1, 1988
Creator: Coffin, D.O.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Blanket technology experiments at Argonne National Laboratory

Description: Argonne National Laboratory has the largest US program for the development of blanket technology. The goals of the program are to resolve critical issues for different blanket concepts, to develop the understanding and predictive capability of blanket behavior, and to develop the technology needed to build and operate advanced fusion blankets. The projects within the program are liquid metal MHD, breeder neutronics, tritium oxidation, transient electromagnetics, FLIBE chemistry, and insulator c… more
Date: February 1, 1988
Creator: Mattas, R. F.; Reed, C. B.; Picologlou, B.; Finn, P.; Clemmer, R.; Porges, K. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Health physics aspects of nuclear radiations from deuterium beam injectors

Description: Estimations are made for X-ray generation from the accelerator column of various neutral beam injectors. For the case of deuterium beam operation where 2.5-MeV D-D neutrons pose a serious health physics concern, neutron and tritium production rates from beam targets are calculated for different beam energies. Biological doses from these radiations and shielding requirements are discussed.
Date: February 1, 1978
Creator: Kim, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The hole of a blanket tritium system on the fusion fuel cycle

Description: The requirements of tritium technology are centered in three main areas, i.e., (1) fuel processing, (2) breeder tritium extraction, and (3) tritium containment. The gaseous tritium stream from the breeder tritium extraction system is significantly different from the plasma exhaust stream and, therefore, may have important impact on the operation of the fuel processing system. For some blankets, such as aqueous solution blanket, the blanket tritium stream may dominate the fuel processing system … more
Date: February 1988
Creator: Sze, D.K.; Finn, P.; Clemmer, R.; Anderson, J.; Bartlit, J.; Naruse, Y. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Savannah River Laboratory monthly report, February 1992

Description: This report is a progress report for the Savannah River Laboratory for the month of February 1992. The progress and activities in six categories were described in the report. The categories are reactor, tritium, separations, environmental, waste management, and general. Each category described numerous and varied activities. Some examples of these activities described are such things as radiation monitoring, maintenance, modifications, and remedial action.
Date: February 1, 1992
Creator: Ferrell, J.M. (comp.) & Ice, L.W. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A tritium-compatible piezoelectric valve for the tokamak fusion test reactor

Description: This work describes modifications made to a commercial piezoelectric valve to make it sufficiently tritium compatible for the TFTR trritium injection scenario. The results of testing the valve for leakage and performance following a series of progressively more severe tritium exposures are also presented. Finally, a proposal for a totally radiation-compatible piezoelectric valve, suitable for tritium-burning fusion machines of the future, is decribed. 9 refs., 2 figs., 1 tab.
Date: February 1, 1988
Creator: Coffin, D.O.; Cole, S.P. & Wilhelm, R.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radiological design criteria for fusion power test facilities

Description: The quest for fusion power and understanding of plasma physics has resulted in planning, design, and construction of several major fusion power test facilities, based largely on magnetic and inertial confinement concepts. We have considered radiological design aspects of the Joint European Torus (JET), Livermore Mirror and Inertial Fusion projects, and Princeton Tokamak. Our analyses on radiological design criteria cover acceptable exposure levels at the site boundary, man-rem doses for plant p… more
Date: February 12, 1982
Creator: Singh, M.S. & Campbell, G.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Combined gettering and molten salt process for tritium recovery from lithium

Description: A new tritium recovery concept from lithium has been developed as part of the US/Japan collaboration on Reversed-Field Pinch Reactor Design Studies. This concept combines the ..gamma..-gettering process as the front end to recover tritium from the coolant, and a molten salt recovery process to extract tritium for fuel processing. A secondary lithium is used to regenerate the tritium from the gettering bed and, in the process, increases the tritium concentration by a factor of about 20. That way… more
Date: February 1, 1988
Creator: Sze, D.K.; Finn, P.A.; Bartlit, J.; Tanaka, S.; Teria, T. & Yamawaki, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Special purpose materials for the fusion reactor environment: a technical assessment

Description: This technology assessment considers the following areas: (1) breeding materials, (2) coolants, (3) tritium barriers, (4) graphite and silicon carbide, (5) ceramics, (6) heat-sink materials, and (7) magnet materials. Some questions and analyses forming the assessment are described. (MOW)
Date: February 1, 1978
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal springs in the Salmon River basin, central Idaho

Description: The Salmon River basin within the study area occupies an area of approximately 13,000 square miles in central Idaho. Geologic units in the basin are igneous, sedimentary, and metamorphic rocks; however, granitic rocks of the Idaho batholith are predominant. Water from thermal springs ranges in temperature from 20.5/sup 0/ to 94.0/sup 0/ Celsius. The waters are slightly alkaline and are generally a sodium carbonate or bicarbonate type. Dissolved-solids concentrations are variable and range from … more
Date: February 1, 1982
Creator: Young, H. W. & Lewis, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Low-exposure tritium radiotoxicity in mammals

Description: Studies of tritium radiotoxicity involving chronic /sup 3/H0H exposures in mammals demonstrate in both mice and monkeys that biological effects can be measured following remarkably low levels of exposure - levels in the range of serious practical interest to radiation protection. These studies demonstrate also that deleterious effects of /sup 3/H beta radiation do not differ significantly from those of gamma radiation at high exposures. In contrast, however, at low exposures tritium is signific… more
Date: February 11, 1982
Creator: Dobson, R.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Radionuclide distributions and migration mechanisms at shallow land burial sites. 1982 annual report of research investigations on the distribution, migration and containment of radionuclides at Maxey Flats, Kentucky

Description: Subsurface waters at Maxey Flats are anoxic, have a high alkalinity and contain high concentrations of ferrous, sulfide and ammonium ions and organic carbon. The trench leachates are extremely variable in composition. Prominent radionuclides include /sup 3/H, /sup 60/Co, /sup 90/Sr, /sup 137/Cs, /sup 238/ /sup 239/ /sup 240/Pu and /sup 241/Am. A wide spectrum of dissolved organic compounds is present in the leachates, including EDTA, polar organics and decomposition products from the waste form… more
Date: February 1, 1984
Creator: Kirby, L.J. (ed.)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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International cooperation at RTNS-II

Description: The Rotating Target Neutron Source-II (RTNS-II) facility at LLNL is a unique materials-test facility. It provides the most intense source of 14-MeV neutrons in the world. Dedicated operation in support of the fusion-materials-research community began in early 1979. Three years later, the Japanese Ministry of Education, Science, and Culture (Monbusho) and the US Department of Energy agreed to jointly support the RTNS-II operation and to share in the use of the facility.
Date: February 1, 1984
Creator: Logan, C.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Selection of fluids for tritium pumping systems

Description: The degradation characteristics of three types of vacuum pump fluids, polyphenyl ethers, perfluoropolyethers and hydrocarbon oils were reviewed. Fluid selection proved to be a critical factor in the long-term performance of tritium pumping systems and subsequent tritium recovery operations. Thermal degradation and tritium radiolysis of pump fluids produce contaminants which can damage equipment and interfere with tritium recovery operations. General characteristics of these fluids are as follow… more
Date: February 1, 1984
Creator: Chastagner, P
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Modelling of tritium transport in a pin-type solid breeder blanket

Description: This study supplements a larger study of a solid breeder blanket design featuring lithium ceramic pins. This aspect of the study looks at tritium transport, release, and inventory within this blanket design. Li/sub 2/O and ..gamma..-LiAlO/sub 2/ are the two primary candidates for ceramic solid breeders. ..gamma..-LiAlO/sub 2/ was chosen for this blanket design due to its higher structural stability. Analysis of tritium behavior in solid breeder blankets is of great importance due to its impact … more
Date: February 1, 1986
Creator: Martin, R. & Ghoniem, N. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ICF tritium production reactor

Description: The conceptual design of an ICF tritium production reactor is described. The chamber design uses a beryllium multiplier and a liquid lithium breeder to achieve a tritium breeding ratio of 2.08. The annual net tritium production of this 532 MW/sub t/ plant is 16.9 kg, and the estimated cost of tritium is $8100/g.
Date: February 28, 1985
Creator: Meier, W. R.; McCarville, T. J.; Berwald, D. H.; Gordon, J. D. & Steele, W. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Correlation between predicted and observed levels of airborne tritium at Lawrence Livermore Laboratory site boundary

Description: At the Lawrence Livermore Laboratory, a computer code based on the Gaussian plume model is used to estimate radiation doses from routine or accidental release of airborne radioactive material. Routine releases of tritium have been used as a test of the overall uncertainty associated with these estimates. The ration of concentration to release rate at distances from the two principal release points to each of six site boundary sampling locations has been calcuated using local meteorological data… more
Date: February 19, 1980
Creator: Lindeken, C. L.; Silver, W. J.; Toy, A. J. & White, J. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Environmental monitoring at the Lawrence Livermore National Laboratory. 1984 annual report

Description: A strict effluent-control program that emphasizes controlling effluents at the source has been in effect since LLNL began operation. The Environmental Monitoring program evaluates the effectiveness of these measures, documents whether effluents from LLNL and Site 300 operations are within applicable standards, and estimates the impact of these operations on the environment. Sensitive monitoring equipment is used that can detect radioactive and nonradioactive pollutants at environmental backgrou… more
Date: February 1, 1985
Creator: Griggs, K.S.; Myers, D.S. & Buddemeier, R.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radionuclide transport in sandstones with WIPP brine

Description: Retardation factors (R) have been measured for the transport of /sup 3/H, /sup 95m/Tc, and /sup 85/Sr in WIPP brine using St. Peter, Berea, Kayenta, and San Felipe sandstone cores. If tritium is assumed to have R=1, /sup 95m/Tc has R=1.0 to 1.3 and therefore is essentially not retarded. Strontium-85 has R = 1.0 to 1.3 on St. Peter, Berea, and Kayenta, but R=3 on San Felipe. This is attributed to sorption on the matrix material of San Felipe, which has 45 volume % matrix compared with 1 to 10 vo… more
Date: February 1, 1981
Creator: Weed, H.C.; Bazan, F.; Fontanilla, J.; Garrison, J.; Rego, J. & Winslow, A.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Cryogenic Distillation: a Fuel Enrichment System for Near-Term Tokamak-Type D-T Fusion Reactors

Description: The successful operation and economic viability of deuterium-tritium- (D-T-) fueled tokamak-type commercial power fusion reactors will depend to a large extent on the development of reliable tritium-containment and fuel-recycle systems. Of the many operating steps in the fuel recycle scheme, separation or enrichment of the isotropic species of hydrogen by cryogenic distillation is one of the most important. A parametric investigation was carried out to study the effects of the various operating… more
Date: February 1980
Creator: Misra, Balabhadra & Davis, J. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TMIST-2 Transport Test

Description: 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 … more
Date: February 1, 2008
Creator: Longhurst, Glen R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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WASTE CHARACTERIZATION OF POLYMERIC COMPONENTS EXPOSED TO TRITIUM GAS

Description: A recent independent review led to uncertainty about the technical basis for characterizing the residual amount of tritium in polymer components used in the Savannah River Site Tritium Facilities that are sent for waste disposal. A review of a paper published in the open literature firmly establishes the basis of the currently used characterization, 10 Ci/cc. Information provided in that paper about exposure experiments performed at the DOE Mound Laboratory allows the calculation of the current… more
Date: February 15, 2008
Creator: Clark, E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrologic Data and Evaluation for Model Validation Wells, MV-1, MV-2, and MV-3 near the Project Shoal Area

Description: In 2006, a drilling campaign was conducted at the Project Shoal Area (PSA) to provide information for model validation, emplace long-term monitoring wells, and develop baseline geochemistry for long term hydrologic monitoring. Water levels were monitored in the vicinity of the drilling, in the existing wells HC-1 and HC-6, as well as in the newly drilled wells, MV-1, MV-2 and MV-3 and their associated piezometers. Periodic water level measurements were also made in existing wells HC-2, HC-3, HC… more
Date: February 14, 2007
Creator: Lyles, B.; Oberlander, P.; Gillespie, D.; Donithan, D.; Chapman, J. & Healey, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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