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The solubility of uranium hexafluoride in perfluoroethers

Description: The polyperfluoroethers are compatible with uranium hexafluoride (UF/sub 6/) and are suitable for use in diffusion pumps and in mechanical vacuum pumps which rely on oil as both the lubricant and the seal. The UF/sub 6/ is soluble in all fluids with which it is compatible. Because a number of vacuum pumps in the BOP facilities of the GCEP plant employ these perfluoroether oils as the working fluid and have oil chambers which are large, questions have been raised as to the relationships governing the solubility of UF/sub 6/ in these materials and the maximum quantities of UF/sub 6/ which could be dissolved in these oils under credible accident conditions. This report summarizes these solubility relations and the interaction of the UF/sub 6/ solubility and the pumping capability of this type of vacuum pump. It will be shown that, whereas the solubility of UF/sub 6/ in Fomblin Y25 fluoroether fluid under a UF/sub 6/ pressure of 760 torr and at the pump operating temperature of 160/sup 0/F is about 500 g of UF/sub 6/ per liter of oil, the system controls are such as to isolate the system from the pumps before the quantity of UF/sub 6/ dissolved in the perfluoroether exceeds about 10 g of UF/sub 6/ per liter of oil. 13 refs., 7 figs.
Date: July 15, 1984
Creator: Barber, E. J.
Partner: UNT Libraries Government Documents Department
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EDS coal liquefaction process development: Phase V. Quarterly technical progress report, January 1-March 31, 1984

Description: This report is the twenty-first Quarterly Technical Progress Report for US Department of Energy Cooperative Agreement No. DE-FC05-77ET10069 for EDS Coal Liquefaction Process Development Phase V. A detailed comparison of RCLU, CLPP, and ECLP yields has been initiated. This study builds off previous yield modeling results, which found that RCLU, CLPP, and ECLP yields were generally consistent given the scatter of the data, although some differences were noted. These pilot unit yield differences have now been quantified, and operating/configurational differences which account for some of them have been identified. Preliminary yield comparison results after correcting for these known process differences between the pilot plants indicate that: RCLU and CLPP yields are generally consistent; ECLP's conversion is about 5 lb/100 lb DAF coal lower than RCLU/CLPP at comparable operating conditions; and work has been initiated to define the EDS slurry preheater feed system design (based on slurry distributor manifold guidelines and coking correlation predictions, which influence furnace pass control issues such as slurry flow measurement). EDS hydrotreated naphtha showed a low level of systemic toxicity to rats exposed to the vapor six hours per day, five days per week for thirteen weeks.
Date: July 1, 1984
Partner: UNT Libraries Government Documents Department
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EP-toxicity testing of mercury removal resin grout

Description: To determine which category a waste will fit into, the EPA requires a classification test. The test, EP-toxicity, consists of a physical integrity test followed by an extraction. For the case of the mercury removal resin grout, the mercury concentration in the extract cannot exceed 0.2 mg/L if the waste is to be classified as ``solid waste.`` Otherwise, the waste is classified as ``hazardous.`` Simulated process solutions were used to load the mercury removal resin. The resin was solidified with the addition of cement and water using a formulation based on grout formulations typically used to solidify power reactor ion exchange resins. Envirodyne Engineers of St. Louis, Missouri, an EPA sanctioned laboratory, performed the EP-toxicity test for the two samples. One sample was a blank which was made with unloaded resin. For the formulation tested, the EP-toxicity test results showed that the mercury removal resin grout does not fit into the ``hazardous waste`` category.
Date: July 18, 1984
Creator: Mersman, K. E.
Partner: UNT Libraries Government Documents Department
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MORSE Monte Carlo radiation transport code system. [Sample problems]

Description: For a number of years the MORSE user community has requested additional help in setting up problems using various options. The sample problems distributed with MORSE did not fully demonstrate the capability of the code. At Oak Ridge National Laboratory the code originators had a complete set of sample problems, but funds for documenting and distributing them were never available. Recently the number of requests for listings of input data and results for running some particular option the user was trying to implement has increased to the point where it is not feasible to handle them on an individual basis. Consequently it was decided to package a set of sample problems which illustrates more adequately how to run MORSE. This write-up may be added to Part III of the MORSE report. These sample problems include a combined neutron-gamma case, a neutron only case, a gamma only case, an adjoint case, a fission case, a time-dependent fission case, the collision density case, an XCHEKR run and a PICTUR run.
Date: July 2, 1984
Creator: Emmett, M.B.
Partner: UNT Libraries Government Documents Department
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1984 Federal Interim Storage fee study: a technical and economic analysis

Description: JAI examined alternative methods for structuring charges for Federal Interim Storage (FIS) services were examined and the conclusion reached that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, and (4) impact aid payments made in accordance with section 136(e) of the Act. The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under-or over-estimation in the costs used to calculate the Initial Payment of the fee including savings due to rod consolidation), (2) module costs (i.e., storage casks, drywells, or silos), and (3) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management and impact aid). Charges for the transport of spent fuel from the reactor site to FIS facilities would be separately assessed at cost since these will be specific to each reactor site and destination.
Date: July 1, 1984
Creator: E.R. Johnson Associates, Inc
Partner: UNT Libraries Government Documents Department
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Project licensing plan for UMTRA (Uranium Mill Tailings Remedial Action) sites

Description: The purpose of the Uranium Mill Tailings Remedial Action (UMTRA) Project Licensing Plan is to establish how a disposal site will be licensed, and to provide responsibilities of participatory agencies as legislated by the Uranium Mill Tailings Radiation Control Act (UMTRCA) of 1978 (Public Law 95-604). This Plan has been developed to ensure that the objectives of licensing are met by identifying the necessary institutional controls, participatory agency responsibilities, and key milestones in the licensing process. The Plan contains the legislative basis for and a description of the licensing process ( Process'') for UMTRA sites. This is followed by a discussion of agency responsibilities, and milestones in the Process. The Plan concludes with a generic timeline of this Process. As discussed in Section 2.1, a custodial maintenance and surveillance plan will constitute the basis for a site license. The details of maintenance and surveillance are discussed in the Project Maintenance and Surveillance Plan (AL-350124.0000). 5 refs., 4 figs.
Date: July 1, 1984
Partner: UNT Libraries Government Documents Department
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Earth Sciences Division annual report 1983

Description: Research is reported on: reservoir engineering and hydrogeology, geomechanics, geophysics, and geochemistry. Separate entries were prepared for 67 research activities.
Date: July 1, 1984
Partner: UNT Libraries Government Documents Department
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Mirror Advanced Reactor Study (MARS). Final report. Volume 2. Commercial fusion synfuels plant

Description: Volume 2 contains the following chapters: (1) synfuels; (2) physics base and parameters for TMR; (3) high-temperature two-temperature-zone blanket system for synfuel application; (4) thermochemical hydrogen processes; (5) interfacing the sulfur-iodine cycle; (6) interfacing the reactor with the thermochemical process; (7) tritium control in the blanket system; (8) the sulfur trioxide fluidized-bed composer; (9) preliminary cost estimates; and (10) fuels beyond hydrogen. (MOW)
Date: July 1, 1984
Creator: Donohue, M.L. & Price, M.E. (eds.)
Partner: UNT Libraries Government Documents Department
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Report of the Long-Range Planning Committee

Description: This is the final report of the Long-Range Planning Committee of the Lawrence Livermore National Laboratory. It describes the make-up, purpose, working assumptions, and activities of the Committee and discusses the work done by the Committee on defense matters, energy, a number of additional topics, and future long-range planning activities.
Date: July 1, 1984
Partner: UNT Libraries Government Documents Department
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Low-temperature geothermal assessment of the Jordan Valley Salt Lake County, Utah

Description: Two known low-temperature areas (Warm Springs fault and Crystal Hot Springs) are located in the Jordan Valley, but the primary purpose of this report is to locate other low-temperature resources not previously identified. Geothermal reconnaissance techniques utilized in this study include a temperature survey and chemical analysis of wells and springs, and temperature-depth measurements in holes of opportunity. Also, further site specific gravity modelling for the Warm Springs fault geothermal area and initial modelling for the entire valley were also conducted. Areas identified as having potential low-temperature geothermal resources at depth are: (1) the north-central valley area; (2) an east-west portion of the central valley; and (3) a north-south oriented area extending from Draper to Midvale. Each of these areas exhibits ground-water temperatures 20/sup 0/C or greater. Each area has thermal wells with common ion characteristics similar to both Crystal Hot Springs and the Warm Springs fault geothermal systems. Significant concentrations of Sr, Li, B, and F are present in many of these wells.
Date: July 1, 1984
Creator: Klauk, R.H.
Partner: UNT Libraries Government Documents Department
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Frequencies of chromosomal aberrations and sister chromatid exchanges in the benthic worm Neanthes arenaceodentata exposed to ionizing radiation

Description: Traditional bioassays are unsuitable for assessing sublethal effects from ocean disposal of low-level radioactive waste because mortality and phenotypic responses are not anticipated. We compared the usefulness of chromosomal aberration and sister chromatid exchange (SCE) induction as measures of low-level radiation effects in a sediment-dwelling marine worm, Neanthes arenaceodentata. The SCEs, in contrast to chromosomal aberrations, do not alter the overall chromosome morphology and in mammalian cells appear to be a more sensitive indicator of DNA alterations caused by environmental mutagens. Newly hatched larvae were exposed to two radiation-exposure regimes of either x rays at a high dose rate of 0.7 Gy (70 rad)/min for as long as 5.5 min or to /sup 60/Co gamma rays at a low dose rate of from 4.8 x 10/sup -5/ to 1.2 x 10/sup -1/ Gy (0.0048 to 12 rad)/h for 24 h. After irradiation, the larvae were exposed to 3 x 10/sup -5/M bromodeoxyuridine (BrdUrd) for 28 h (x-ray-irradiated larvae) or for 54 h (/sup 60/Co-irradiated larvae). Larval cells were examined for the proportion of cells in first, second, and third or greater division. Frequencies of chromosomal aberrations and SCEs were determined in first and second division cells, respectively. Results from x-ray irradiation indicated that dose-related increases occur in chromosome and chromatid deletions, but a dose of equal or greater 2 Gy (equal to or greater than 200 rad) was required to observe a significant increase. Worm larvae receiving /sup 60/Co irradiation showed elevated SCE frequencies with a significant increase of 0.6 Gy (60 rad). We suggest that both SCEs and chromosomal aberrations may be useful for measuring effects on genetic material induced by radiation. 56 references, 7 figures, 9 tables.
Date: July 1, 1984
Creator: Harrison, F.L. & Rice, D.W. Jr., Moore, D.H.
Partner: UNT Libraries Government Documents Department
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Mirror Advanced Reactor Study (MARS). Final report. Volume 1-B. Commercial fusion electric plant

Description: Volume 1-B contains the following chapters: (1) blanket and reflector; (2) central cell shield; (3) central cell structure; (4) heat transport and energy conversion; (5) tritium systems; (6) cryogenics; (7) maintenance; (8) safety; (9) radioactivity, activation, and waste disposal; (10) instrumentation and control; (11) balance of plant; (12) plant startup and operation; (13) plant availability; (14) plant construction; and (15) economic analysis.
Date: July 1, 1984
Creator: Donohue, M.L. & Price, M.E. (eds.)
Partner: UNT Libraries Government Documents Department
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Thermophysical properties of working fluids for binary geothermal cycles. Final report

Description: The following are presented: thermodynamic properties of isobutane and isobutane-isopentane mixtures; a scaled fundamental equation for mixtures of isobutane and isopentane near gas-liquid critical line; and viscosities of hydrocarbons and their mixtures. (MHR)
Date: July 1, 1984
Creator: Diller, D.E.; Gallagher, J.S.; Kamgar-Parsi, B.; Morrison, G.; Levelt Sengers, J.M.H.; Sengers, J.V. et al.
Partner: UNT Libraries Government Documents Department
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Optimization of design and control strategies for geothermal space heating systems. Final report

Description: The efficient design and operation of geothermal space heating systems requires careful analysis and departure from normal design practices. Since geothermal source temperatures are much lower than either fossil fuel or electrical source temperatures, the temperature of the delivered energy becomes more critical. Also, since the geothermal water is rejected after heat exchange, it is necessary to extract all of the energy that is practical in one pass; there is no second change for energy recovery. The present work examines several heating system configurations and describes the desired design and control characteristics for operation on geothermal sources. Specific design methods are outlined as well as several generalized guidelines that should significantly improve the operation of any geothermally heated system.
Date: July 1, 1984
Creator: Batdorf, J. A. & Simmons, G. M.
Partner: UNT Libraries Government Documents Department
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Proton laser accelerator by means of the inverse free electron laser mechanism

Description: The inverse free electron laser accelerator is considered to be a potential high gradient electron accelerator. In this accelerator electrons oscillating in the magnetic field of a wiggler can gain energy from a strong laser beam propagating collinearly. The same mechanism of acceleration can work for protons and all other heavier particles. One can expect that the proton acceleration will be less effective, as it is more difficult to wiggle a heavier particle. It is indeed so, but this less efficient coupling of the proton and laser beam is partly compensated by the negligible radiative losses. These losses impose restrictions on the electron acceleration above 100 Gev. 6 references, 2 figures.
Date: July 1, 1984
Creator: Zakowicz, W.
Partner: UNT Libraries Government Documents Department
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Thermal conductivities for sintered and sphere-pac Li/sub 2/O and. gamma. /sup -/LiAlO/sub 2/ solid breeders with and without irradiation effects

Description: Thermal conductivities (k, k/sub eff/) have been estimated for sintered and sphere-pac Li/sub 2/O and ..gamma..-LiAlO/sub 2/ with and without neutron irradiation effects. The estimation is based on (1) data from unirradiated UO/sub 2/, Li/sub 2/O, and ..gamma..-LiAlO/sub 2/; (2) data from irradiated dielectric insulator materials; and (3) relatively simple physical models. Comparison of model predictions with limited ex- and in-reactor data found reasonable agreement, thus lending credence for their use in design applications. The impact of thermal conductivities on tritium breeding and power generation in fusion solid-breeder blankets is briefly highlighted.
Date: July 1, 1984
Creator: Liu, Y. Y. & Tam, S. W.
Partner: UNT Libraries Government Documents Department
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KMSF x-ray laser experiments. Task No. 2. Final report

Description: This report summarizes work done at KMS Fusion, Inc. in support of the x-ray laser experimental program at Lawrence Livermore National Laboratory. It follows an earlier report of Task No. 1 of the subject purchase order. As in that report, most of the original data has been reviewed by the LLNL technical staff, with much of it transferred to LLNL for analysis. Consequently, this report does not include a detailed presentation of the data.
Date: July 1, 1984
Creator: Charatis, G.
Partner: UNT Libraries Government Documents Department
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Underground pumped hydroelectric storage

Description: Underground pumped hydroelectric energy storage was conceived as a modification of surface pumped storage to eliminate dependence upon fortuitous topography, provide higher hydraulic heads, and reduce environmental concerns. A UPHS plant offers substantial savings in investment cost over coal-fired cycling plants and savings in system production costs over gas turbines. Potential location near load centers lowers transmission costs and line losses. Environmental impact is less than that for a coal-fired cycling plant. The inherent benefits include those of all pumped storage (i.e., rapid load response, emergency capacity, improvement in efficiency as pumps improve, and capacity for voltage regulation). A UPHS plant would be powered by either a coal-fired or nuclear baseload plant. The economic capacity of a UPHS plant would be in the range of 1000 to 3000 MW. This storage level is compatible with the load-leveling requirements of a greater metropolitan area with population of 1 million or more. The technical feasibility of UPHS depends upon excavation of a subterranean powerhouse cavern and reservoir caverns within a competent, impervious rock formation, and upon selection of reliable and efficient turbomachinery - pump-turbines and motor-generators - all remotely operable.
Date: July 1, 1984
Creator: Allen, R. D.; Doherty, T. J. & Kannberg, L. D.
Partner: UNT Libraries Government Documents Department
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E-Division activities report

Description: E (Experimental Physics) Division carries out basic and applied research in atomic and nuclear physics, in materials science, and in other areas related to the missions of the Laboratory. Some of the activities are cooperative efforts with other divisions of the Laboratory, and, in a few cases, with other laboratories. Many of the experiments are directly applicable to problems in weapons and energy, some have only potential applied uses, and others are in pure physics. This report presents abstracts of papers published by E (Experimental Physics) Division staff members between July 1983 and June 1984. In addition, it lists the members of the scientific staff of the division, including visitors and students, and some of the assignments of staff members on scientific committees. A brief summary of the budget is included.
Date: July 1, 1984
Creator: Barschall, H.H. (comp.)
Partner: UNT Libraries Government Documents Department
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Characterization of emergency preparedness at DOE contractor facilities

Description: A study of emergency preparedness capabilities at DOE facilities was initiated following the incident at the Three Mile Island (TMI) Nuclear Power Station. It was designed to parallel but expand on a study on emergency preparedness instrumentation that was conducted in 1970 by Pacific Northwest Laboratory. The 1970 survey findings led to the publication of four reports on performance criteria for radiological emergency instrumentation. Three of these reports - BNWL-1635 (Selby et al. 1972), BNWL-1742 (Anderson et al. 1974) and BNWL-1857 (Andersen et al. 1976) - addressed the criteria for emergency instrumentation at reactors, mixed oxide fuel fabrication plants, and fuel reprocessing plants, respectively. The fourth report, BNWL-1991 (Bramson et al. 1976), addressed evaluation testing and calibration methodology for these instruments. This report is presented in three parts. Part One is a review of the BNWL documents to determine whether they are applicable to state-of-the-art instrument capabilities. The Appendix to Part One provides a comparison between the instrument performance criteria established in BNWL-1991 to applicable American National Standards Institute (ANSI) standards for portable survey and contamination meters, installed radiation and area monitors, effluent monitors, calibration techniques, criticality detection systems, alarm systems, and direct reading dosimeters. Part Two compares the 1970 survey results with the 1980 survey results to identify trends in emergency preparedness. Part Three is a discussion of the results of the 1980 emergency preparedness survey and the supporting data for each of the 15 modules. 8 references. (ACR)
Date: July 1, 1984
Creator: Gillings, J. C.; Murphy, B. L.; Corbit, C. D.; MacLellan, J. A.; Essig, T. H.; Higby, D. P. et al.
Partner: UNT Libraries Government Documents Department
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Mirror Advanced Reactor Study (MARS). Final report. Volume 1-A. Commercial fusion electric plant

Description: Volume 1-A contains the following chapters: (1) plasma engineering, (2) magnets, (3) ecr heating systems, (4) anchor ion-cyclotron resonance heating system, (5) sloshing ion neutral beam, (6) end cell structure, (7) end plasma technology, (8) fueling, (9) startup ion cyclotron resonant heating systems, and (10) end cell radiation analysis. (MOW)
Date: July 1, 1984
Creator: Donohue, M.L. & Price, M.E. (eds.)
Partner: UNT Libraries Government Documents Department
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Mechanical Engineering Department technical abstracts

Description: The Mechanical Engineering Department publishes abstracts twice a year to inform readers of the broad range of technical activities in the Department, and to promote an exchange of ideas. Details of the work covered by an abstract may be obtained by contacting the author(s). General information about the current role and activities of each of the Department's seven divisions precedes the technical abstracts. Further information about a division's work may be obtained from the division leader, whose name is given at the end of each divisional summary. The Department's seven divisions are as follows: Nuclear Test Engineering Division, Nuclear Explosives Engineering Division, Weapons Engineering Division, Energy Systems Engineering Division, Engineering Sciences Division, Magnetic Fusion Engineering Division and Materials Fabrication Division.
Date: July 1, 1984
Partner: UNT Libraries Government Documents Department
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Modelling and assessment of advanced processes for integrated environmental control of coal-fired power plants. Technical progress report

Description: The key objective of this research is the development of a computer based model for the assessment of integrated environmental control (IEC) systems for conventional and advanced coal fired power plant designs. Efforts during the period April 1-June 30, 1984 focused on, (1) testing of a preliminary integrated model linking pre-combustion and post-combustion control options for conventional plants; (2) documentation of the analytical models of existing control technology options; (3) development and preliminary testing of a second model design for the propagation and analysis of uncertainty; and (4) development of new analytical models needed for IEC assessments. Activities and accomplishments in each of these areas are described. 4 references, 13 figures, 4 tables.
Date: July 1, 1984
Creator: Barrett, J. G.; Bloyd, C. N.; McMichael, F. C. & Rubin, E. S.
Partner: UNT Libraries Government Documents Department
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Mathematical modeling and evaluation of radionuclide transport parameters from the ANL Laboratory Analog Program

Description: Computer model simulation is required to evaluate the performance of proposed or future high-level radioactive waste geological repositories. However, the accuracy of a model in predicting the real situation depends on how well the values of the transport properties are prescribed as input parameters. Knowledge of transport parameters is therefore essential. We have modeled ANL's Experiment Analog Program which was designed to simulate long-term radwaste migration process by groundwater flowing through a high-level radioactive waste repository. Using this model and experimental measurements, we have evaluated neptunium (actinide) deposition velocity and analyzed the complex phenomena of simultaneous deposition, erosion, and reentrainment of bentonite when groundwater is flowing through a narrow crack in a basalt rock. The present modeling demonstrates that we can obtain the values of transport parameters, as added information without any additional cost, from the available measurements of laboratory analog experiments. 8 figures, 3 tables.
Date: July 1, 1984
Creator: Chen, B.C.J.; Hull, J.R.; Seitz, M.G.; Sha, W.T.; Shah, V.L. & Soo, S.L.
Partner: UNT Libraries Government Documents Department
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