Phase I of the Near-Term Hybrid Vehicle Program. Final report (open access)

Phase I of the Near-Term Hybrid Vehicle Program. Final report

Heat engine/electric hybrid vehicles offer the potential of greatly reduced petroleum consumption, compared to conventional vehicles, without the disadvantages of limited performance and operating range associated with pure electric vehicles. This report documents a hybrid vehicle design approach which is aimed at the development of the technology required to achieve this potential, in such a way that it is transferable to the auto industry in the near term. The development of this design approach constituted Phase I of the Near-Term Hybrid Vehicle Program. The major tasks in this program were: mission analysis and performance specification studies; design tradeoff studies; and preliminary design. Detailed reports covering each of these tasks are included as appendices to this report. A fourth task, sensitivity studies, is also included in the report on the design tradeoff studies. Because of the detail with which these appendices cover methodology and results, the body of this report has been prepared as a brief executive summary of the program activities and results, with appropriate references to the detailed material in the appendices.
Date: September 10, 1979
Creator: unknown
System: The UNT Digital Library
Tokamak Fusion Test Reactor (TFTR) neutral beam line vacuum chamber cover structural analysis (open access)

Tokamak Fusion Test Reactor (TFTR) neutral beam line vacuum chamber cover structural analysis

The Tokamak Fusion Test Reactor (TFTR) vacuum chamber cover is sealed by 0-rings without the aid of mechanical fasteners. Under vacuum loading and component weights, the edges lifted no more than 0.005 in. (by a SAP4 computer code analysis). This report explains the model used for this investigation and, in addition, shows the maximum deflection expected at the center of the cover is less than 0.047 in. Also, no stresses are expected to exceed 13,700 psi.
Date: September 10, 1979
Creator: Humphrey, D.L. & Pedrotti, L.R.
System: The UNT Digital Library
Measurements, error analyses, and calculations of water and steam individual mass flow rates, velocities, and related flow parameters obtained from single-phase and two-phase prototype tests of the PKL instrumented spool pieces for the US NRC-RSR 3-D program (open access)

Measurements, error analyses, and calculations of water and steam individual mass flow rates, velocities, and related flow parameters obtained from single-phase and two-phase prototype tests of the PKL instrumented spool pieces for the US NRC-RSR 3-D program

The operation of the emergency core cooling system and its related steam-binding problems in pressurized water reactors are the subject of a cooperative study by the United States, Germany, and Japan. Lawrence Livermore Laboratory and EG and G, Inc., San Ramon Operations, are responsible for the design, hardware, and software of the 80.8-mm and 113-mm spool piece measurement systems for the German Primarkreislauf (PKL) Test Facility at Kraftwerk Union in Erlangen, West Germany. Four PKL spool pieces each containing a flow turbine, drag screen, three-beam densitometer, and pressure and temperature probes were constructed and tested to measure single-phase and two-phase steam and water flow parameters. Individual phase velocities, mass flow rates, and densities were calculated from the analytical relationships presented. These calculated and measured parameters were compared to those parameters determined from the test facility instrumentation at Wyle Laboratories. Error analyses were performed, and individual test results were presented for both horizontal and vertical flows. The various flow regimes tested included annular mist, slug, froth, stratified wavy, and homogeneous flow of water or superheated steam.
Date: September 10, 1979
Creator: Stein, W.
System: The UNT Digital Library
Internal Technical Report, Program Plan for Conversion of Biomass to Liquid Fuel Using Geothermal Energy (open access)

Internal Technical Report, Program Plan for Conversion of Biomass to Liquid Fuel Using Geothermal Energy

Due to the decreased supply of petroleum and the large quantity of import oil, there exists sufficient economic justification to develop a biomass-liquid fuel industry. Geothermal energy uniquely fits the biomass production and conversion requirements. To accelerate industrial development of biomass-to-liquid fuel conversion using geothermal energy, a national program is required. Because of the INEL's unique experience in moderate-temperature geothermal applications, they should take the lead in this program. Based on an extensive survey of the biomass conversion field, areas of needed work were identified and a program plan was developed. This plan separates the INEL role into two parts. (1) Commercial Support--Existing technology can be commercially applied to provide a portion of the liquid fuel needs. To accelerate development, INEL needs to provide technical and management support to existing programs such as direct assistance, loan guarantees, PONs, and PRDAs. (2) Technical Development--Application of new geothermal technology in the production and conversion of biomass can increase the quantity of domestically produced liquid fuel. The program plan identifies needed work down to the task level. Three cost account levels are identified: (1) Biomass-to-Liquid Fuel Technology, (2) Biomass-to-Liquid Fuel Advanced Technology Demonstration, and (3) Biomass-to-Liquid Fuel Commercial Support. The end item is …
Date: September 10, 1979
Creator: Chaney, R. E.; Jacoby, J. K. & LaRue, D. M.
System: The UNT Digital Library
Corrosion of delta plutonium in Rocky Flats tap water (open access)

Corrosion of delta plutonium in Rocky Flats tap water

Corrosion rates were established by measuring the weight loss of a sample completely immersed in tap water for specified periods of time. Tests were conducted for periods ranging from 21 to 1824 hours at ambient temperature in sealed 125-ml containers. The weight changes observed revealed that the corrosion of delta plutonium by tap water in a closed system occurs through two separate processes. Each results in a different average corrosion rate. Initially a typical diffusion-controlled surface reaction was observed which resulted in an average corrosion rate of 0.264 mg(cm/sup 2/.h). The second corrosion process begins when cracking and flaking of the corrosion product layer occurs. This results in an increase in the corrosion rate to 0.52 mg/(cm/sup 2/.h). 3 figures, 2 tables.
Date: September 10, 1979
Creator: Hodges, A. E., III; Reynolds, J. J. & Haschke, J. M.
System: The UNT Digital Library