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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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TCT hybrid preconceptual blanket design studies

Description: The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal d… more
Date: January 1, 1978
Creator: Aase, D. T.; Bampton, M. C. C.; Doherty, T. J.; Leonard, B. R.; McCann, R. A.; Newman, D. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation experiment for lithium ceramics

Description: Solid breeder materials are required in D-T fusion reactor blankets to convert fusion neutrons to tritium and thermal energy while providing some neutron shielding for the magnets. Lithium compounds such as Li/sub 2/O, LiAlO/sub 2/, Li/sub 4/SiO/sub 4/ and Li/sub 2/ZrO/sub 3/ have been proposed as solid breeder materials. Tritium is necessary to maintain the fuel supply for the D-T fusion reaction. No high burnup irradiation performance data is available for these materials in a neutron environ… more
Date: March 1, 1982
Creator: Hollenberg, G.W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tritium half-life

Description: Least squares analyses of calorimetric measurements made at Mound Laboratory on two tritide compounds over a period of 18 y were performed to determine the half-life of tritium. A half-life of 12.3232 +- 0.0043 mean solar years was obtained.
Date: December 22, 1977
Creator: Rudy, C. R. & Jordan, K. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrology and geochemistry of thermal ground water in southwestern Idaho and north-central Nevada

Description: The study area occupies about 14,500 square miles in southwestern Idaho and north-central Nevada. Thermal ground water occurs under artesian conditions, in discontinuous or compartmented zones, in igneous or sedimentary rocks of Tertiary age. Ground-water movement is generally northward. Temperatures of the ground water range from about 30/sup 0/ to more than 80/sup 0/C. Chemical analyses of water from 12 wells and 9 springs indicate that nonthermal waters are a calcium bicarbonate type; therma… more
Date: December 1, 1980
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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Tritium storage development. Progress report No. 12, April--June 1977. [In metal hydride; polymer impregnated tritiated concrete]

Description: Laboratory work was continued on hydriding of zirconium sponge and rod under varying conditions of temperature (400 to 900/sup 0/C) and pressure (0-1000 torr) to determine optimum conditions for the formation of hydrides with desirable mechanical properties. Titanium sponge and rod were also hydrided for comparison. Zirconium and titanium samples containing tritium were prepared and initial leach data were obtained. Leach rates for zirconium in distilled water ranged from 1.1 x 10/sup -6/ to 4.… more
Date: January 1, 1976
Creator: Colombo, P
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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H-Area Seepage Basins

Description: During the third quarter of 1990 the wells which make up the H-Area Seepage Basins (H-HWMF) monitoring network were sampled. Laboratory analyses were performed to measure levels of hazardous constituents, indicator parameters, tritium, nonvolatile beta, and gross alpha. A Gas Chromatograph Mass Spectrometer (GCMS) scan was performed on all wells sampled to determine any hazardous organic constituents present in the groundwater. The primary contaminants observed at wells monitoring the H-Area Se… more
Date: December 1, 1990
Creator: Stejskal, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Enhanced tritium transport and release by solids modification

Description: To improve the tritium release characteristics of lithium ceramics, we are investigating the effects of dopants on tritium transport and release. Prior work has suggested a correlation between tritium and lithium diffusion in lithium-containing ceramics. This correlation has led us to propose a mechanism for tritium diffusion in which the tritium diffuses in the form of a lithium vacancy-triton complex. If this is the case, one should be able to increase the tritium diffusivity by increasing th… more
Date: January 1, 1989
Creator: Kopasz, J. P.; Tam, S. W. & Johnson, C. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Design of a continuous duty cryopump

Description: A continuous duty cryopump system was designed and developed that comprises a self-contained cryopump for installation into a vacuum chamber, and a microprocessor controller for automatic operation. This deuterium pump has two units in a single housing, arranged so that one is pumping while the other is being regenerated. Liquid helium-cooled, finned sections in each unit pump deuterium by condensation, and a third pump integral within the cryopump housing collects the regenerated gas. A microp… more
Date: May 1, 1985
Creator: Sedgley, D.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot cell studies of tritium removal from and dissolution of an irradiated thoria fuel

Description: Tritium removal and dissolution studies on an irradiated thoria-based fuel were conducted in the High Level Caves at the Savannah River Laboratory (SRL). The objectives of these studies were to define the effects of key process-related parameters on tritium evolution and subsequent dissolution. The test program at SRL determined the effects on tritium removal of particle size, heating temperature, oxidation, and agitation. ThO/sub 2//UO/sub 2/ (95%/5%) fuel from the Elk River Reactor, irradiate… more
Date: January 1, 1980
Creator: Pickett, J.B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Some effects on the kinetics of muon-catalyzed fusion

Description: Two important stages in the kinetics of muon-catalyzed d-t fusion are discussed: (1) atomic thermalization and hyperfine-state relaxation preceding molecular formation and (2) muon stripping and x-ray production if sticking occurs after nuclear fusion. Thermalization is accurately treated by Monte Carlo simulation. It is shown that thermalization and triplet quenching of the ..cap alpha mu.. atom may not finish before dt..mu.. formation in low-tritium targets, but that epithermal transients are… more
Date: January 1, 1986
Creator: Cohen, J.S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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TRITOX: a multiple parameter evaluation of tritium toxicity

Description: The increased use of nuclear reactors for power generation will lead to the introduction of tritium into the environment. The need for assessing possible immediate and long-term effects of exposure to this tritium led to the development of a broad program directed towards evaluating the possible somatic and genetic effects of continuous exposure to tritiated water (HTO). Among the parameters measured are the genetic, cytogenetic, reproductive efficiency, growth, nonspecific lifetime shortening,… more
Date: January 1, 1982
Creator: Carsten, A.L.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Tritium in fusion reactor components

Description: When tritium is used in a fusion energy experiment or reactor, several implications affect and usually restrict the design and operation of the system and involve questions of containment, inventory, and radiation damage. Containment is expected to be particularly important both for high-temperature components and for those components that are prone to require frequent maintenance. Inventory is currently of major significance in cases where safety and environmental considerations limit the expe… more
Date: January 1, 1980
Creator: Watson, J S; Fisher, P W & Talbot, J B
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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Tritium module for ITER/Tiber system code

Description: A tritium module was developed for the ITER/Tiber system code to provide information on capital costs, tritium inventory, power requirements and building volumes for these systems. In the tritium module, the main tritium subsystems/emdash/plasma processing, atmospheric cleanup, water cleanup, blanket processing/emdash/are each represented by simple scaleable algorithms. 6 refs., 2 tabs.
Date: January 1, 1988
Creator: Finn, P. A.; Willms, S.; Busigin, A. & Kalyanam, K. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Kinetics of the radiation-induced exchange reactions of H/sub 2/, D/sub 2/, and T/sub 2/: a review

Description: Mixtures of H/sub 2/--T/sub 2/ or D/sub 2/--T/sub 2/ will exchange to produce HT or DT due to catalysis by the tritium ..beta.. particle. The kinetics of the reaction D/sub 2/ + T/sub 2/ = 2DT may play an important role in designing liquid or solid targets of D/sub 2/--DT--T/sub 2/ for implosion fusion, and distillation schemes for tritium cleanup systems in fusion reactors. Accordingly, we have critically reviewed the literature for information on the kinetics and mechanism of radiation-induce… more
Date: January 6, 1978
Creator: Pyper, J.W. & Briggs, C.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance of BNL-TSTA compound cryopump

Description: A compound cryopump using cryocondensation pumping for hydrogen isotopes and cryosorption pumping with coconut charcoal as adsorbent for helium was designed. This compound cryopump was subsequently built (by Janis Research, Stoneham, MA) and has been tested at Brookhaven, fulfilling the design requirements and are delivered to Tritium Systems Test Assembly (TSTA) Vacuum Facility at Los Alamos Scientific Laboratory (LASL) for on-line operations.
Date: January 1, 1980
Creator: Hseuh, H. C. & Worwetz, H. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Separation of tritium from gaseous and aqueous effluent systems

Description: Three processes are discussed for separating tritium from gaseous and aqueous effluent systems: separation in the gas phase using Pd-25 wt percent Ag alloy diffusion membranes; electrolytic separation in the aqueous phase using ''bipolar'' electrodes; and the countercurrent exchange of tritium-containing hydrogen gas with water on catalytic surfaces combined with separation by direct electrolysis. (LK)
Date: January 1, 1977
Creator: Kobisk, E. H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Assessment of tritium breeding requirements for fusion power reactors

Description: This report presents an assessment of tritium-breeding requirements for fusion power reactors. The analysis is based on an evaluation of time-dependent tritium inventories in the reactor system. The method presented can be applied to any fusion systems in operation on a steady-state mode as well as on a pulsed mode. As an example, the UWMAK-I design was analyzed and it has been found that the startup inventory requirement calculated by the present method significantly differs from those previou… more
Date: December 1, 1983
Creator: Jung, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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