Progress in LMFBR safety studies on accident debris behavior is reported under the following subtask titles: high-temperature-concentration aerosols, large-scale molten fuel tests, sodium release tests, and risk analysis.

Progress is reported for a program whose goals are to demonstrate an experimental Upgraded gas turbine-powered automobile which meets the 1978 Federal Emissions Standards, has significantly improved fuel economy, and is competitive in performance, reliability, and potential manufacturing cost with the conventional piston engine-powered, compact-size American automobile. This is the concluding progress report for this program; it covers the period from May 1, 1978 to January 31, 1979. The next formal report will be the final report, which is currently in process. Activity during this reporting period has continued to emphasize development towards correcting a power deficiency in the Upgraded Engine. Efforts are also being directed towards reducing fuel usage through improved heat recovery and towards improving the mechanical reliability and control of the engine.

This report summarizes the technical progress in the following areas of study: (1) low-frequency instabilities; (2) high-frequency microinstabilities; (3) nonlinear effects and radiative processes; (4) ideal and resistive, linear and nonlinear, MHD numerical studies of tokamak plasma configurations; (5) numerical studies of the implosion dynamics and post-implosion anomalous transport properties of high-density pinches; (6) development of computer codes for solving complex dispersion relations; and (7) nonlocal eigenvalue problems for microstability analysis.

Full-scale near-surface heater experiments are presently being conducted by Sandia Laboratories in the Conasauga Formation at Oak Ridge, Tennessee, and in the Eleana Formation on the Nevada Test Site, Nevada. The purposes of these experiments are: (1) to determine if argillaceous media can withstand thermal loads characteristic of high level waste; (2) to provide data for improvement of themomechanical modeling of argillaceous rocks; (3) to identify instrumentation development needed for further in situ testing; and (4) to identify unexpected general types of behavior, if any. The basic instrumentation of these tests consists of a heater in a central hole, surrounded by arrays of holes containing various instrumentation. Temperatures, thermal profiles, vertical displacements, volatile pressurization, and changes in in situ stresses are measured in each experiment as a function of time, and compared with pretest modeling results. Results to date, though in general agreement with modeling results assuming conductive heat transfer within the rock, indicate that the presence of even small amounts of water can drastically affect heat transfer within the heater hole itself, and that small amounts of upward convection of water may be occurring in the higher temperature areas of the Conasauga experiments.

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A numerical model of a regional ground-water flow system (not site specific) was coupled with a material transport model in order to study the influence of porosity and distribution coefficients in bedded media. The effects on model performance were discerned from long-term material transport simulations. Model performance was based on initial breakthrough time, average breakthrough time, and the standard deviation of the breakthrough curve at a discharge surface. Large differences in model performance occurred when the distribution coefficient was changed less than an order of magnitude, while small differences resulted from changing porosity several orders of magnitude.

Sandia`s Particle Beam Fusion Program is investigating several driver options, based on pulsed power technology, with the goal of demonstrating a practical ignitor for Inertial Confinement Fusion (ICF) Reactors. The interrelated aspects of power conditioning and compression, beam-target interaction, and target ignition are being studied. The issues of efficiency, reliability and multiple pulse capability are being integrated into the program to provide a viable approach to an experimental power reactor. On a shorter time scale the authors expect to derive important military-related benefits from attendant research and facility development. The two most important advantages of pulsed power driven fusion are the inherent low cost and high efficiency of high current particle accelerators. However, comparison of the relative merits of particle beams and focused laser beams must include many other factors such as beam transport, and target coupling, as well as target design and fabrication. These issues are being investigated to determine if the perceived practical benefits of particle beam fusion can indeed be realized. The practical considerations are exemplified in a comparison of the leading ICF drivers. The plan being followed by Sandia involves using the Electron Beam Fusion Accelerator (EBFA) to meet three objectives by 1985: significant burn using …

The interactions of a quartz monzonite, an argillite, an alluvium, and several tuffs with various radionuclides in selected phreatic waters have been studied. The sorption--desorption hehavior of Sr, Tc(VII), Cs, Ba, Ce, Eu, U(VI), Pu, and Am under ambient and 70{sup 0}C temperature conditions has been measured.

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Candidate alloys for a Very High Temperature Reactor (VHTR) Nuclear Process Heal (NPH) and Direct Cycle Helium Turbine (DCHT) applications in terms of the effect of the primary coolant exposure and thermal exposure were evaluated. (FS)

Information is given for each of the following topics: (1) requirements for experimental fusion power reactors, (2) tritium requirements, (3) sources of T, (4) T availability from DOE production reactors, (5) T availability from heavy-water reactors, (6) T availability from light-water reactors, (7) T availability from fuel reprocessing plants, (8) natural Li requirements and availability, (9) /sup 6/Li requirements and availability, and (10) availability of /sup 3/He or /sup 4/He. (MOW)

Development of a process for producing high-purity silicon by zinc reduction of silicon tetrachloride in a fluidized bed of seed particles to yield a free-flowing granular product is reviewed. Progress in finalizing the design of a 50 MT/year experimental process facility is reported. (MHR)

Chemical inhomogeneities produced during arc melting of uranium--6 weight percent niobium alloy normally persist during fabrication of the ingot to a finished product. An investigation was directed toward producing a more homogeneous product (approx. 13.0-mm plate) by a combination of mechanical working and homogenization. Ingots were cast, forged to various reductions, homogenized under different conditions, and finally rolled to 13.0-mm-thick plate. It was concluded that increased forging reductions prior to homogenization resulted in a more homogeneous plate. Comparison of calculated and experimentally measured niobium concentration profiles indicated that the activation energy for the diffusion of niobium in uranium--niobium alloys may be lower than previously observed.

This report provides calculated LOCE lifetimes of the LOFT reactor vessel components. For each component, lifetime is defined as the greatest number of LOCE transient cycles and/or other non-LOCE transient cycles such that cumulative usage factor does not exceed 1.0. The results are presented in tabular form. The results indicate that transients other than LOCE transients govern with or instead of LOCE transients for some components. The other transients are shown in the results.

Graphs of neutron cross sections and related parameters for the LLL ENDL are presented. LLL and others use the evaluated nuclear data given here for neutron transport and related calculations. This document presents data contained in the library as of October 31, 1978. Evaluations of 79 nuclides/elements have been changed since the 1976 edition. Five tables discuss the information in the report, while the cross sections themselves are included on six microfiche.

The stress analysis performed on the 1''-SSS-3-E piping system inside containment penetration S-11C is described. Deadweight, thermal expansion, and seismic loads were considered. Results of this analysis show that the subject pipe system will meet ASME Boiler and Pressure Vessel Code, Section III, Class 2 Requirements provided that additional supports (S3 and S6) are installed as recommended.

Abstract: The 3" IA-296-AB line from the containment penetration S-5B was analyzed to ASME Code, Subsection NC (Class 2) criteria. This section of piping is part of the Containment Isolation System; the model considered the line from penetration S-5B outward through a series of elbows and through the third isolation valve. Results of this analysis show that the section of line described will meet Class 2 requirements if additional supports are installed at three locations, as described in the body of this report.

A stress analysis was performed on the Primary Coolant Addition and Control Piping System to determine if it met the conditions of the ASME Code, Section III, for Class 2 components. Results indicate that the Addition and Control System does not meet Section III criteria as the system is now installed. Only hanger (support) modifications are required to bring the stresses within the limits set forth in the Code. A design temperature of 459/sup 0/F was assumed for the analysis. The specified design temperature of 650/sup 0/F has been revised by ECRA's L-5713 and L-5714.

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The objective of this research program is to investigate the technical and economic feasibility of producing solar-cell-quality sheet silicon by coating one surface of carbonized ceramic substrates with a thin layer of large-grain polycrystalline silicon from the melt. During the past year, the cell development task of the low-cost solar array project has also sponsored work leading to the solution of solar-cell-oriented problems unique to silicon-on-ceramic material. This work is described also. Fracture toughness and thermal shock measurements were made on various mullite compositions. The dip-coater experimentation involved using a variety of crucible positions and gas flow rates to improve coating speeds. The construction of the continuous coating facility was completed. Many modifications to the original design have been made to obtain better control of the temperature profile of the coater. An experimental dip-coater has been completed. The goal of this effort is to increase coating speeds to from 0.15 to 0.3 cm/sec without sacrificing material quality. The best slotted SOC cell fabricated to date has a 7.5 percent conversion efficiency (antireflective-coated, AM1, total area 4.1 cm/sup 2/). A standardized cell fabrication process was developed for slotted and unslotted SOC solar cells. Modeling activities have concentrated on three major areas: …

This quarterly basin activities report is a summation of three months drilling and testing activities in the primary study areas of the WGSP; these include the Greater Green River Basin, the Northern Great Plains Province, the Piceance Basin, and the Uinta Basin. Additional low permeability sandstone areas are listed and located geographically. Activities in each primary study area are summarized under core program and dilling activity. (JRD)

This edition of the WGSP status report summarizes September 1978 progress of the government-sponsored projects directed towards increasing gas production from the low-permeability gas sands of the western United States. Background information is provided in the September 1977 Status Report, NVO/0655-100. The Williston Basin Symposium was held in Billings, Montana, the 24th through the 27th of September 1978. The USGS continued work on characterization and assessment of the resource in the four primary study areas and completed the 1978 field work in the Sand Wash and Green River Basins. CER Corporation is evaluating a Twin Arrow drill site, located on the Douglas Creek Arch for the possibility of obtaining core, and preparations are being made for the Logging Program meeting to be held at the CER offices the latter part of October, 1978. The design phase for the pressure coring system has been completed and work is progressing on the fabrication and testing of the improved system. The National Laboratories and Energy Technology Centers continued work on mathematical model development, new tools and instrumentation systems, data analysis techniques and rock mechanics. Work continued on the field tests and demonstrations aspect of the WGSP. Bids sent to several service companies by …