A glass direct contact heat exchange column was operated in the laboratory. The column was operated at atmospheric pressure using hot water and normal hexane. Column internals testing included an empty column, sieve trays, disk-and-doughnut trays, and two types of packing. Operation was very smooth in all cases and the minimum temperature approaches varied from less than 1/sup 0/C for packing to 13/sup 0/C for the empty column. High heat transfer rates were obtained in all cases, however, columns should be sized on the basis of liquid and vapor traffic. The solubilities of hydrocarbons were determined for normal hexane, pentane and butane in water and sodium chloride and calcium chloride brines at various temperatures. The values seem to be internally consistent and salt content was found to depress hydrocarbon solubility. Laboratory stripping tests showed that gas stripping can be used to remove hydrocarbon from reject hot water from the direct contact heat exchange column. Although the gas volumes required are small, stripping gas requirements cannot be accurately predicted without testing. A computer program was used to study the effect of operating variables on the thermodynamic cycle efficiencies. Optimum efficiencies for the moderate brine conditions studied were obtained with isopentane as …

An overview is presented of the national geologic disposal program for the safe and efficient isolation of nuclear wastes resulting from the commercial nuclear reactor fuel cycle. Investigations being pursued by the Office of Waste Isolation including schedules, tentative budgets, and proposed participants are outlined. (LK)

Using electric fields to diminish end losses from open magnetic plasma confinement systems is equivalent to magnetically shielding the grid wires of an electrostatic plasma confinement device. Electrostatically plugged magnetic cusps confine electrons magnetically in the perpendicular direction and electrostatically in the parallel direction, and ions are purely electrostatically confined in both directions. Theoretical estimates have been made of confinement times, electron density, plasma potential, and plasma temperatures. Experimentally, plasmas with n = 5 x 10/sup 12/ cm/sup -3/, T/sub i/ = 1 keV, tau = 5 msec, have been confined by cusp fields of about 10 kG with applied voltages approximately 10 kV. Fusion reactors with (fusion power)/(injection power) identical with Q approximately 5 appear feasible using B approximately 80 kG, applied voltage approximately 300 kV, if extrapolations from present experiments hold. Electrostatically plugged cusps are similar in some ways to Tandem Mirrors, to Tormac, and to SURMAC plasma confinement systems.

Progress is summarized in LMFBR safety studies related to the characterization of sodium fires and fission products. Included are sections on SOMIX Code development, sodium splash dispersal, aerosol leakage, aerosol model improvement, characterization of aerosol source term, large scale molten fuel tests, fuel and fission product release from burning sodium, and iodine attenuation. (DG)

Textural properties, including porosity and density, of rock samples collected from Cenozoic volcanic fields in the western U.S. were studied. Resistivity and acoustic wave speed measurements were also made. (JGB)

ORTAP was developed to predict the dynamic behavior of the high temperature gas cooled reactor (HTGR) Nuclear Steam Supply System for normal operational transients and postulated accident conditions. It was developed for the Nuclear Regulatory Commission (NRC) as an independent means of obtaining conservative predictions of the transient response of HTGRs over a wide range of conditions. The approach has been to build sufficient detail into the component models so that the coupling between the primary and secondary systems can be accurately represented and so that transients which cover a wide range of conditions can be simulated. System components which are modeled in ORTAP include the reactor core, a typical reheater and steam generator module, a typical helium circulator and circulator turbine and the turbine generator plant. The major plant control systems are also modeled. Normal operational transients which can be analyzed with ORTAP include reactor start-up and shutdown, normal and rapid load changes. Upset transients which can be analyzed with ORTAP include reactor trip, turbine trip and sudden reduction in feedwater flow. ORTAP has also been used to predict plant response to emergency or faulted conditions such as primary system depressurization, loss of primary coolant flow and uncontrolled removal …

During 1976, new Mirror Program plans have been laid out to take into account the significant advances during the last 18 months. The program is now focused on two new mirror concepts, field reversal and the tandem mirror, that can obtain high Q, defined as the ratio of fusion power output to the neutral-beam power injected to sustain the reaction. Theoretically, both concepts can attain Q = 5 or more, as compared to Q = 1 in previous mirror designs. Experimental planning for the next 5 years is complete in broad outline, and we are turning attention to what additional steps are necessary to reach our long-range goal of an experimental mirror reactor operating by 1990. Highlights of the events that have led to the above circumstance are listed, and experimental program plans are outlined.

A report is presented covering the activities undertaken by Gary Operating Company, as well as by the major subcontractors, Atlantic Richfield, Union, and Intercomp. The major activity at this time is Phase II, Task 1, the Micellar-Polymer Systems selection from the two competing designs being developed by Atlantic Richfield and Union Oil. This activity comes to closure with Decision Point 2 in August.

The LLL MCS-8/80 microcomputer system is a modular, general-purpose microcomputer system based on the 8008 and 8080 microprocessors. This engineering note discusses the similarities and differences between the various printed-circuit memory modules available for use with the MCS-8/80 system.

A system is described in which neutron interaction data are collected from nuclear physics laboratories throughout the world, organized, evaluated, and then stored for easy access in a computer network. Computer codes that use the data to solve neutron interaction problems were also developed. The system supplies reliable up-to-date data, selects specific types of data on request, provides output in a variety of forms (reports, microfiche, microfilm), and functions rapidly and efficiently. 3 figures.

The tests conducted on the /sup 1///sub 5/-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N2)-driven air clearing phase tests discussed here were performed to obtain the air/water-induced dynamic vertical load function and to determine the response of a 90/sup 0/ sector of a 360/sup 0/ torus structure.

Absolute rate coefficients for the reaction of O-atoms and H-atoms with formaldehyde were determined over the temperature range of 250 o 500 K. Rate parameters were determined from plots of log k vs. 1/T which were found to follow the linear Arrhenius behavior. These results are compared with those of previous studies and further discussed in terms of a formaldehyde conversion mechanism.

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A scenario is developed which depicts the transition, during the period from 1980 to 1997, of mainline freight railroads in the US from diesel to electric power. Progress in developing an econometric model of the market penetration of electric-powered vehicles in the US to the year 2010 is reported. (LCL)

This report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts that should minimize or eliminate the identified barriers. The identified barriers include: (1) design and construction interfacing problems; (2) problems relating to the selection and use of permanent materials and construction methods; (3) construction coordination and communication problems; and (4) problems associated with manpower availability and productivity;

This is the fourteenth Monthly Technical Progress Report submitted under ERDA Contract No. EY-77-C-02-4207, formerly Contract No. E(49-18)-2237. As such it continues the coverage of the activities undertaken by Gary Operating Company, as well as by the major subcontractors, Atlantic Richfield, Union Oil and Intercomp. The work described covers the tasks for: Micellar-Polymer Systems Selection and Evaluation, Site Development, Pilot Performance Predictions and Fluid Distribution Facilities. The major activity at this time is Phase II, Task 1, the Micellar-Polymer Systems Selection as between the two competing designs being developed by Atlantic Richfield and Union Oil. This activity came to closure with Decision Point 2 on August 24, 1977.

This report documents the development of a computerized data base on the long-term performance of the Indian Creek Total Energy System, and it is intended to be a user's manual for the data base and the accompanying energy-balance computer program. The data base may be used as a standard of comparison for the performance predicted by energy-system-simulation software. The TES became operational in 1972 to meet the projected electrical, space conditioning, and domestic hot water needs for the garden-type apartment complex. The dual-fuel engine are provided with both gas and No. 2 oil connections. Heat from the exhaust flues is extracted in the heat recovery units. Following the introductory chapter, Chapter II provides a description and background history on the highly instrumented and efficiently operated Indian Creek Total Energy System. Also included in Chapter II is a discussion of the instrumentation used to monitor the performance of the total energy system. Chapter III provides a detailed description of the data base, including the methodology used to supply missing data. Chapter IV develops the energy balance equations and relates them to the computer program and the data base. Chapter V presents the results of exercising the energy balance computer model driven …

The work described covers the tasks for: Micellar-Polymer Systems Selection and Evaluation, Site Development, Pilot Performance Predictions, Fluid Distribution Facilities, and Log-Inject-Log Tests. (DLC)

The script of a demonstration videotape made to show the possibilities of coupling rod lenses to low-light video systems to observe internal flow conditions is presented. The illustrations accompanying the text were photographed directly from the video screen. Some up-dated comments appear as footnotes to the original script and a description of the multiscan low-light television system developed to measure velocity is included in the epilogue. The combination of rod lens and low-light video system makes it possible to observe dynamic events in hitherto inaccessible volumes. The pressure and temperature capabilities of the rod lens make it applicable to many engineering uses. This system, in conjunction with electronic image enhancement systems, provides a new dimension in engineering analysis.

The use of calorimeters for measuring laser output energies and powers is reviewed, primarily for the period 1975 to 1977 since preparation of earlier reviews.

The paper follows the history of a neutral atom or molecule into a plasma--ionization, dissociation, radiation,--until it becomes a set of charged particles moving in the electromagnetic fields of the plasma system. The various useful forms of the method of averaging are displayed and applied to calculation of constants of motion. The breakdown of these constants is discussed along with some of the implications for fusion systems.

The purpose of this test was to demonstrate that the system accumulator for the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) fulfilled the requirements of the test procedure (TP 400) test objectives. The results of the expulsion testing performed on the system accumulator are presented.

To determine the radiation attenuation characteristics of liquid air (109 g/cm/sup 2/ thick) for 14 MeV neutrons from a central D-T source in a 10 kL vessel, radiation dose measurements were made using a large tissue-equivalent ion chamber external to the vessel. The shielding characteristics of steel spherical shells were also investigated. Experimental results were analyzed and compared with TARTNP Monte Carlo code calculations. Degradation of the ion chamber's response to high-energy neutrons was established and incorporated into the analysis. The dose attenuation factor for the unshielded detector was measured to be 0.073, compared with the calculated value of 0.081. The shielded detector signals were reduced only modestly; with a 10-cm-thick shell, the signal from the filled vessel dropped twofold.

The verification methods which shall be used in the development program to be conducted on the Kilowatt Isotope Power System (KIPS) Jet Condenser to verify adequate orifice thermal performance are described. The purpose of the test procedure is to determine which orifice elements achieve satisfactory thermal performance to assure adequacy for Ground Demonstration System (GDS) Testing.