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.

None

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 …

An assessment of land available at nuclear power stations was performed in an to determine the limitations land availability would impose on the implementation of reject heat utilization system.

Separate abstracts are included for development programs for electronic equipment involved with plasma research, data processing, uranium environmental surveys, and geothermal surveys.

The following program plan elements are described: barriers to commercialization, cost/benefit analysis for exploration assessment technology (hydrothermal systems), goals, objectives, technical plan, management plan, budget, and procurement plan. (MHR)

The stress analysis performed on the 4''-WH-237-E piping system inside containment penetration S-17B is presented. Deadweight, thermal expansion, and seismic loads were considered. Results of this analysis show that the subject piping system will meet ASME Code, Section III, Class 2 requirements.

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A technical basis for assessing the true safety margins of containment structures involved with MARK I boiling water reactor reevaluation activities is presented. It is based on the results of a plane-strain, large displacement, elasto-plastic, finite-element analysis of a thin cylindrical shell subjected to external and internal pressure pulses. An analytical procedure is presented for estimating the ultimate load capacity of the thin shell structure, and subsequently, for quantifying the design margins of safety for the type of loads under consideration. For defining failure of structures, a finite strain failure criterion is derived that accounts for multiaxiality effects.

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Fabrication of experimental breeder reactor fuel pellets by the common cold-press-and-sinter technique for irradiation testing in EBR-II is discussed. Fuel types include mixed thoria-plutonia, UO/sub 2/ enriched with 22 weight percent /sup 233/U in U, UO/sub 2/ enriched with thirty-four weight percent /sup 235/U in U, and mixed urania-plutonia.

Transuranium elements have been introduced to the environment by a variety of ways including fallout from weapons testing, leakage from nuclear power reactors, waste effluent from nuclear fuel processing and leakage of radioactive waste from ocean dump sites. Several methods of curium detection and analysis in samples from marine ecosystems are contrasted and discussed in this paper.

High energy neutron irradiations have been performed on Nb/sub 3/Sn superconductors to assess their behavior in a fusion reactor environment. Irradiations were performed at 4.2/sup 0/K and property measurements were made without warming the samples. The critical current I/sub c/ increased with irradiation to a level about 50% above the unirradiated value at the highest fluences reached in our experiments. These results are compared with the results of other low temperature irradiations of Nb/sub 3/Sn.

The purpose of this document is to describe in both programmatic and technical terms the methodology that the US Department of Energy will use to commercialize a molten carbonate fuel cell power plant. Responsibility for the planning and management of the program resides in the molten carbonate fuel cell program office at the Argonne National Laboratory which reports to the Assistant Director for Fuel Cells in the Division of Fossil Fuel utilization of DOE/FE. The actual development of technology is carried out by selected contractors. The technology development phase of the program will culminate with the construction and operation of two demonstration power plants. The first power plant will be an industrial cogeneration plant which will be completed in 1987. The other power plant will be a baseload electric power plant to be completed in 1989.