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Enhanced oil recovery by CO/sub 2/ foam flooding. Annual report, October 1, 1982-September 30, 1983
The objective is to identify commercially available additives which are effective in reducing the mobility of carbon dioxide, CO/sub 2/, thereby improving its efficiency in the recovery of tertiary oil, and which are low enough in cost to be economically attractive. During the past year significant progress has been made in developing a commercial method of reducing the mobility of carbon dioxide in enhanced oil recovery processes. Four basic chemical structures, listed below, appear to show most promise for gas mobility control: (1) ethoxylated adducts of C/sub 8/ - C/sub 14/ linear alcohols; (2) sulfate esters of ethoxylated C/sub 9/ - C/sub 16/ linear alcohols; (3) low molecular weight co-polymers of ethylene oxide and propylene oxide; and (4) synthetic organic sulfonates. With the exception of the sulfonates, the above types are compatible with normal oil field brines, unaffected by the presence of crude oil and stable under conditions common in a petroleum reservoir. The second significant result during the year involves identification of several sulfonate structures that have high potential for mobility control for carbon dioxide. Commercial sulfonate additives are available that appear optimum for reservoirs where freshwater will be used to inject the surfactant solution. They can also be …
Date:
December 22, 1983
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Technician support for operation and maintenance of large fusion experiments: the tandem mirror experiment upgrade (TMX-U) approach
As experiments continue to grow in size and complexity, a few technicians will no longer be able to maintain and operate the complete experiment. Specialization is becoming the norm. Subsystems are becoming very large and complex, requiring a great deal of experience and training for technicians to become qualified maintenance/operation personnel. Formal in-house and off-site programs supplement on-the-job training to fulfill the qualification criteria. This paper presents the Tandem Mirror Experiment-Upgrade (TMX-U) approach to manpower staffing, some problems encountered, possible improvements, and safety considerations for the successful operation of a large experimental facility.
Date:
December 1, 1983
Creator:
Mattson, G.E.
Object Type:
Article
System:
The UNT Digital Library
Catalytic steam gasification of bagasse for the production of methanol
Pacific Northwest Laboratory (PNL) tested the catalytic gasification of bagasse for the production of methanol synthesis gas. The process uses steam, indirect heat, and a catalyst to produce synthesis gas in one step in fluidized bed gasifier. Both laboratory and process development scale (nominal 1 ton/day) gasifiers were used to test two different catalyst systems: (1) supported nickel catalysts and (2) alkali carbonates doped on the bagasse. This paper presents the results of laboratory and process development unit gasification tests and includes an economic evaluation of the process. 20 references, 6 figures, 9 tables.
Date:
December 1, 1983
Creator:
Baker, E.G. & Brown, M.D.
Object Type:
Article
System:
The UNT Digital Library
Formation of H/sup -/ by charge transfer in alkaline-earth vapors
Progress since the last symposium on the study of H/sup -/ formation by charge transfer in alkaline-earth vapors is reported. High yields are obtained at low energies, in agreement with theoretical predictions.
Date:
December 5, 1983
Creator:
Schlachter, A.S. & Morgan, T.J.
Object Type:
Article
System:
The UNT Digital Library
Proceedings of the Fifth Annual Participants' Information Meeting: DOE Low-Level Waste Management Program
The meeting consisted of the following six sessions: (1) plenary session I; (2) disposal technology; (3) characteristics and treatment of low-level waste; (4) environmental aspects and performance prediction; (5) overall summary sessions; and (6) plenary session II. Fifty two papers of the papers presented were processed for inclusion in the Energy Data Base. (ATT)
Date:
December 1, 1983
Creator:
unknown
Object Type:
Article
System:
The UNT Digital Library
Hot gas cleanup using solid supported molten salt for integrated coal gasification/molten carbonate fuel cell power plants. Topical report, October 1982-December 1983
Battelle, Pacific Northwest Laboratories is developing a solid supported molten salt (SSMS) hot gas cleanup process for integrated coal gasification/molten carbonate fuel cell (MCFC) power plants. Exploratory and demonstration experiments have been completed to select a salt composition and evaluate its potential for simultaneous hydrogen sulfide (H/sub 2/S) and hydrogen chloride (HCl) removal under the conditions projected for the MCFC plants. Results to date indicate that equilibrium capacity and removal efficiencies may be adequate for one step H/sub 2/S and HCl removal. Regeneration produced a lower H/sub 2/S concentration than expected, but one from which sulfur could be recovered. Bench scale experiments will be designed to confirm laboratory results, check carbonyl sulfide removal, refine dual cycle (sulfide-chloride) regeneration techniques and obtain data for engineering/economic evaluation and scale-up. 8 references, 24 figures, 7 tables.
Date:
December 1, 1983
Creator:
Lyke, S. E.; Sealock, L. J. Jr. & Roberts, G. L.
Object Type:
Report
System:
The UNT Digital Library
Ion cyclotron radio frequency systems and performance on the tandem mirror experiment-upgrade (TMX-U)
High power ion cyclotron radio frequency (ICRF) systems are now gaining greater attention than before as prime driver ion heating systems. Lawrence Livermore National Laboratory (LLNL) has installed a 200 kW high frequency (HF) transmitter system on its Tandem Mirror Experiment-Upgrade (TMX-U). This paper describes the system, antenna, controls, and monitoring apparatus. The transmitter operates into a high Q antenna installed in the central cell region of the experiment. It incorporates a dual-port feedback system to automatically adjust the transmitter's output power and allow the maximum consistent with the plasma loading of the antenna. Special techniques have been used to measure, in real-time, the dynamically changing loading values presented by the plasma. From the measurements, the antenna impedance can be optimized for specified plasma density.
Date:
December 1, 1983
Creator:
Moore, T. L.; Molvik, A. W.; Cummins, W. F.; Pedrotti, L. R.; Henderson, A. L.; Karsner, P. G. et al.
Object Type:
Article
System:
The UNT Digital Library
Heavy ion drivers for inertial confinement fusion
The advantages of heavy ion beams as a way of delivering the needed energy and power to an inertial fusion target are surveyed. The existing broad technology base of particle accelerators provides an important foundation for designing, costing, and evaluating proposed systems. The sequence of steps needed for the verification of the heavy ion approach is described; recent research results are even more encouraging than had been assumed hitherto.
Date:
December 1, 1983
Creator:
Keefe, D.
Object Type:
Article
System:
The UNT Digital Library
Assessment of tritium breeding requirements for fusion power reactors
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 previously calculated. The effect of reactor-parameter changes on the required tritium breeding ratio is also analyzed for a variety of reactor operation scenarios.
Date:
December 1, 1983
Creator:
Jung, J.
Object Type:
Report
System:
The UNT Digital Library
Kinetic analysis of dynamic PET data
Our goal is to quantify regional physiological processes such as blood flow and metabolism by means of tracer kinetic modeling and positron emission tomography (PET). Compartmental models are one way of characterizing the behavior of tracers in physiological systems. This paper describes a general method of estimating compartmental model rate constants from measurements of the concentration of tracers in blood and tissue, taken at multiple time intervals. A computer program which applies the method is described, and examples are shown for simulated and actual data acquired from the Donner 280-Crystal Positron Tomograph.
Date:
December 1, 1983
Creator:
Knittel, B.
Object Type:
Report
System:
The UNT Digital Library
Microwave measurement test results of circular waveguide components for electron cyclotron resonant heating (ECRH) of the Tandem Mirror Experiment-Upgrade (TMX-U)
Development of high-power components for electron cyclotron resonant heating (ECRH) applications requires extensive testing. In this paper we describe the high-power testing of various circular waveguide components designed for application on the Tandem Mirror Experiment-Upgrade (TMX-U). These include a 2.5-in. vacuum valve, polarizing reflectors, directional couplers, mode converters, and flexible waveguides. All of these components were tested to 200 kW power level with 40-ms pulses. Cold tests were used to determine field distribution. The techniques used in these tests are illustrated. The new high-power test facility at Lawrence Livermore National Laboratory (LLNL) is described and test procedures are discussed. We discuss the following test results: efficiency at high power of mode converters, comparison of high power vs low power for waveguide components, and full power tests of the waveguide system. We also explain the reasons behind selection of these systems for use on TMX-U.
Date:
December 1, 1983
Creator:
Williams, C.W.; Rubert, R.R.; Coffield, F.E.; Felker, B.; Stallard, B.W. & Taska, J.
Object Type:
Article
System:
The UNT Digital Library
High performance, suppressed-fission ICF hybrid
The neutronics aspects of an ICF hybrid concept are discussed. The breeding blanket consists of a beryllium neutron multiplier, metallic thorium fertile fuel and a liquid-lithium coolant. The fertile fuel fraction is 30 vol%, which is much higher than previous one-zone, suppressed-fission hybrid concepts. Fission in the bred /sup 233/U is suppressed by competition from tritium breeding reactions in /sup 6/Li. The total breeding ratio, T + F, is 2.05, and the total neutron energy deposited is 41.1 MeV per DT neutron. The 800-MW (fusion) hybrid produces approx. 3500 kg of /sup 233/U per full-power-year.
Date:
December 1, 1983
Creator:
Meier, W. R.
Object Type:
Article
System:
The UNT Digital Library
Assessment of the response of spent fuel transports to malevolent acts
This paper describes the results of a program conducted at Sandia National Laboratories (SNL) for the US Department of Energy to provide an experimental data base for more accurately assessing the radiological consequences from a hypothetical sabotage attack on a spent fuel shipping cask. The primary objectives of the program were limited to: (1) evaluating the effectiveness of selected high explosive devices (HED) in breaching full-size spent fuel casks, (2) quantifying and characterizing relevant aerosol properties of the released fuel, and (3) using the resulting experimental data to evaluate the radiological health consequences resulting from a hypothetical sabotage attack on a spent fuel shipping cask in a densely populated area. Subscale and full-scale experiments in conjunction with an analytical modeling study were performed to meet the programmatic objectives. The data from this program indicate that the Urban Studies greatly overestimated the impact of malevolent acts directed at spent fuel casks in urban environs. From that standpoint this work could be the basis of additional regulatory revisions of the NRC physical protection requirements. In a larger sense this work can also be the basis of more credible worst case analyses since it defines the actual result of an event which is …
Date:
December 20, 1983
Creator:
Sandoval, R.P.
Object Type:
Article
System:
The UNT Digital Library
Thermionic cogeneration burner assessment study performance analysis results
The purpose of this contract was to (1) test and evaluate two of the more important engineering aspects of designing and building thermionic cogeneration burners (TCB's); (2) make a cost and performance estimate of the TCB; and identify and evaluate industries where TCB's could be installed and where that the electrical power (dc) produced by the TCB's would be used directly in the process. The results of the performance analysis are detailed.
Date:
December 1, 1983
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Superconducting (radiation hardened) magnets for mirror fusion devices
Superconducting magnets for mirror fusion have evolved considerably since the Baseball II magnet in 1970. Recently, the Mirror Fusion Test Facility (MFTF-B) yin-yang has been tested to a full field of 7.7 T with radial dimensions representative of a full scale reactor. Now the emphasis has turned to the manufacture of very high field solenoids (choke coils) that are placed between the tandem mirror central cell and the yin-yang anchor-plug set. For MFTF-B the choke coil field reaches 12 T, while in future devices like the MFTF-Upgrade, Fusion Power Demonstration and Mirror Advanced Reactor Study (MARS) reactor the fields are doubled. Besides developing high fields, the magnets must be radiation hardened. Otherwise, thick neutron shields increase the magnet size to an unacceptable weight and cost. Neutron fluences in superconducting magnets must be increased by an order of magnitude or more. Insulators must withstand 10/sup 10/ to 10/sup 11/ rads, while magnet stability must be retained after the copper has been exposed to fluence above 10/sup 19/ neutrons/cm/sup 2/.
Date:
December 7, 1983
Creator:
Henning, C. D.; Dalder, E. N. C.; Miller, J. R. & Perkins, J. R.
Object Type:
Article
System:
The UNT Digital Library
Fuel systems for compact fast space reactors
About 200 refractory metal clad ceramic fuel pins have been irradiated in thermal reactors under the 1200 K to 1550 K cladding temperature conditions of primary relevance to space reactors. This paper reviews performance with respect to fissile atom density, operating temperatures, fuel swelling, fission gas release, fuel-cladding compatibility, and consequences of failure. It was concluded that UO/sub 2/ and UN fuels show approximately equal performance potential and that UC fuel has lesser potential. W/Re alloys have performed quite well as cladding materials, and Ta, Nb, and Mo/Re alloys, in conjunction with W diffusion barriers, show good promise. Significant issues to be addressed in the future include high burnup swelling of UN, effects of UO/sub 2/-Li coolant reaction in the event of fuel pin failure, and development of an irradiation performance data base with prototypically configured fuel pins irradiated in a fast neutron flux.
Date:
December 1, 1983
Creator:
Cox, C.M.; Dutt, D.S. & Karnesky, R.A.
Object Type:
Article
System:
The UNT Digital Library
Fusion power demonstration - a baseline for the mirror engineering test reactor
Developing a definition of an engineering test reactor (ETR) is a current goal of the Office of Fusion Energy (OFE). As a baseline for the mirror ETR, the Fusion Power Demonstration (FPD) concept has been pursued at Lawrence Livermore National Laboratory (LLNL) in cooperation with Grumman Aerospace, TRW, and the Idaho National Engineering Laboratory. Envisioned as an intermediate step to fusion power applications, the FPD would achieve DT ignition in the central cell, after which blankets and power conversion would be added to produce net power. To achieve ignition, a minimum central cell length of 67.5 m is needed to supply the ion and alpha particles radial drift pumping losses in the transition region. The resulting fusion power is 360 MW. Low electron-cyclotron heating power of 12 MW, ion-cyclotron heating of 2.5 MW, and a sloshing ion beam power of 1.0 MW result in a net plasma Q of 22. A primary technological challenge is the 24-T, 45-cm bore choke coil, comprising a copper hybrid insert within a 15 to 18 T superconducting coil.
Date:
December 2, 1983
Creator:
Henning, C. D.; Logan, B. G.; Neef, W. S.; Dorn, D.; Clarkson, I. R.; Carpenter, T. et al.
Object Type:
Article
System:
The UNT Digital Library
Pressure bump instability in very large cold bore storage rings
Calculations have been done to estimate the circulating current necessary to induce the onset of a pressure bump instability in a cold bore storage ring. For a wide range of storage ring parameters, the instability threshold current is more than an order of magnitude higher than the operating current. 4 references, 2 tables.
Date:
December 1, 1983
Creator:
Limon, P.
Object Type:
Article
System:
The UNT Digital Library
Radiation-induced electrical breakdown of helium in fusion reactor superconducting magnet systems
A comprehensive theoretical study has been performed on the reduction of the electrical breakdown potential of liquid and gaseous helium under neutron and gamma radiation. Extension of the conventional Townsend breakdown theory indicates that radiation fields at the superconducting magnets of a typical fusion reactor are potentially capable of significantly reducing currently established (i.e., unirradiated) helium breakdown voltages. Emphasis is given to the implications of these results including future deployment choices of magnet cryogenic methods (e.g., pool-boiling versus forced-flow), the possible impact on magnet shielding requirements and the analogous situation for radiation-induced electrical breakdown in fusion RF transmission systems.
Date:
December 2, 1983
Creator:
Perkins, L.J.
Object Type:
Article
System:
The UNT Digital Library
Calculation of density profiles in tandem mirrors fueled by pellets
We have modified the LLNL radial transport code TMT to model reactor regime plasmas, fueled by pellets. The source profiles arising from pellet fueling are obtained from existing pellet ablation models. Because inward radial diffusion due to inverted profiles must compete with trapping of central cell ions in the transition region for tandem mirrors, pellets must penetrate fairly far into the plasma. In fact, based on our radial calculations, a pellet with a velocity of 10 km/sec cannot sustain the central flux tubes; a velocity more like 100 km/sec will be necessary. We also find that the central cell radial diffusion must exceed classical by about a factor of 100.
Date:
December 2, 1983
Creator:
Campbell, R. B. & Gilmore, J. M.
Object Type:
Article
System:
The UNT Digital Library
Answers to questions about updated estimates of occupational radiation doses at Three Mile Island, Unit 2
The purpose of this question and answer report is to provide a clear, easy-to-understand explanation of revised radiation dose estimates which workers are likely to receive over the course of the cleanup at Three Mile Island, Unit 2, and of the possible health consequences to workers of these new estimates. We will focus primarily on occupational dose, although pertinent questions about public health and safety will also be answered.
Date:
December 1, 1983
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Neutron therapy facility at the Institute of High Energy Physics, Academia Sinica
The 10 MeV proton linac which was designed as preinjector for the Beijing 50 GeV Proton Synchrotron (BPS) was completed by the end of 1982. Because of the economic readjustment in the People's Republic of China the BPS project was cancelled. Then, the Institute of High Energy Physics decided to increase the energy of the linac from 10 MeV to 35.5 MeV. This increase will take place using the primary five megawatts RF system of the 10 MeV linac. This 35.5 MeV proton linac will be used for research in radiomedicine and radiobiology in general and in particular for research in fast neutron therapy and radiopharmaceutical production. This project has been approved by the Academia Sinica.
Date:
December 1, 1983
Creator:
Zhu, Y.C.
Object Type:
Report
System:
The UNT Digital Library
Field testing of fugitive dust control techniques at a uranium mill tailings pile - 1982 Field Test, Gas Hills, Wyoming.
A field test was conducted on a uranium tailings pile to evaluate the effectiveness of 15 chemical stabilizers for control of fugitive dust from uranium mill tailings. A tailings pile at the Federal American Partners (FAP) Uranium Mill, Gas Hills, Wyoming, was used for the field test. Preliminary laboratory tests using a wing tunnel were conducted to select the more promising stabilizers for field testing. Fourteen of the chemical stabilizers were applied with a field spray system pulled behind a tractor; one--Hydro Mulch--was applied with a hydroseeder. A portable weather station and data logger were installed to record the weather conditions at the test site. After 1 year of monitoring (including three site visits), all of the stabilizers have degraded to some degree; but those applied at the manufacturers' recommended rate are still somewhat effective in reducing fugitive emissions. The following synthetic polymer emulsions appear to be the more effective stabilizers: Wallpol 40-133 from Reichold Chemicals, SP-400 from Johnson and March Corporation, and CPB-12 from Wen Don Corporation. Installed costs for the test plots ranged from $8400 to $11,300/ha; this range results from differences in stabilizer costs. Large-scale stabilization costs of the test materials are expected to range from $680 …
Date:
December 1, 1983
Creator:
Elmore, M.R. & Hartley, J.N.
Object Type:
Report
System:
The UNT Digital Library
First wall and limiter lifetime in pulsed tokamak reactors
This study concentrates on the structural integrity of certain reactor subsystems under cyclic operation to answer the question: how long a burn pulse is needed to achieve the benefits of steady-state operation. Component lifetime in the steady-state is limited by three effects: radiation damage, disruptions, and sputtering erosion. Cyclic operation modifies one of these (the number of disruptions may increase with the number of burn cycles) and introduces a fourth life limit, thermal fatigue. Our design strategy is to determine the structure and coating thicknesses which maximize component lifetime against all life limitations. After calculating disruption damage (vaporization, melting) for candidate materials we present the lifetime analysis for different structures.
Date:
December 1, 1983
Creator:
Ehst, D.; Majumdar, S.; Cha, Y. & Hassanein, A.
Object Type:
Article
System:
The UNT Digital Library