The objective of this program was: to evaluate for photovoltaic applications the use of the compound parabolic concentrator design as a field collector--in conjunction with a primary focusing concentrator. The primary focusing concentrator may be a parabolic reflector, an array of Fresnel mirrors, a Fresnel lens, or some other type; Select several candidate configurations of such compound systems (focusing concentrators/CPC field collectors); Perform an analytic evaluation of the technical performance of these systems; and identify the most promising configurations and perform a cost effectiveness study pertinent to coupling CPC concentrators to solar cells. (WDM)

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The program objective is to evolve and define an accessory drive system that will minimize system power consumption of driven accessories on an internal combustion engine in a passenger automobile. The initial three program phases established concept feasibility, determined potential fuel savings, and selected a drive system design for concept mechanization. During this quarter the major program accomplishments were: selection of candidate belt-drive concepts; completion of Phase III baseline vehicle drive systems physical and operational envelopes; completion of analysis for a mechanically controlled direct-operated belt drive with input programming; and completion of design layout and analysis for a hydromechanically controlled, servo-operated belt drive with output-speed sensing. (LLL)

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Six one-million-gallon double shell waste storage tanks will be constructed for safe and reliable containment and storage of high-level radioactive wastes. The design and safety features of these tanks are discussed including: architecture; structure; primary and secondary tanks; reinforced concrete tank; tank dome penetrations; processing and transfer facilities; piping; auxiliary equipment; pumps; slurry distributors; and ventilation. (DC)

For the past two decades, programs have been conducted to develop ZrH reactor space power systems. Present development plans for reactor space system components are geared to the development of off-the-shelf standardized reactor components which can be used without modification in either Brayton, thermoelectric (TE), or organic Rankine power systems over a power range of 3 to 15 kW(e). In recent years, national energy programs have highlighted the need to increase production of oil and gas from domestic sources. The US oil and ocean engineering industries are developing subsea production methods and equipment for recovering petroleum from deep water and ice-covered regions. There is the need for a subsea power source for highly reliable, unattended operation. Preliminary studies indicate that ZrH reactor subsea power systems may offer advantages in deep water sites remote from surface support facilities, in regions of severe surface or icing conditions, and in areas of critical environmental problems. A number of major US oil companies have indicated a potential need for a subsea nuclear power system for future offshore operations and have expressed their interest in a concept based on the ZrH reactor and an organic Rankine power conversion system (PCS). Work pursued during FY 1975 …

During the fall of 1974 and early winter of 1975, cracks have been discovered in the 4 in. bypass lines of several Boiling Water Reactors (BWR's) in the United States. Further, similar cracks were discovered at two BWR's in Japan during the same period. More recently, cracks have been discovered in the core spray piping and in a furnace-sensitized "safe end" and adjacent "dutchman" at the Dresden Nuclear Power Station, Unit No. 2. Although inspections at all other U.S. BWR's have not disclosed further instances of cracking in core spray piping, leaking cracks have been found in the core spray piping of two BWR's overseas. Metallurgical examinations of these cracks are not yet complete. The following observations have been made to date. All cracks (except those in the furnace-sensitized safe end and dutchman) occurred in seamless type 304 stainless steel piping or in elbows fabricated from such piping, in the outer heat affected zone of either field or shop welds, in lines isolated from the main primary coolant flow during full power operation, except for the not yet examined cracks in the Monticello bypass lines. The cracks are exclusively intergranular, and occur in metal that has been lightly sensitized by …

Progress is reported for a program to demonstrate by 1976 an experimental 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, standard size American automobile. A fuel control system is being developed to allow program evaluation of a very promising low emissions, single stage, fixed geometry proprietary burner. Ceramic regenerators are under test in the free-rotor vehicle, and some have completed 30 hours of performance evaluation. Three-dimensional ceramic regenerator transient thermal and structural analysis programs are operational. Initial friction and wear test fixture results show that zirconium oxide fully stabilized by yttrium oxide is an effective substitute for nickel oxide in a plasma sprayed seal. A preprototype control system was adapted for variable inlet guide vane control in a vehicle installation. An evaluation of the free-rotor accessory drive concept in a vehicle showed no serious mechanical integrity problems. Simplifications are being made to the water injection system; significant metallurgical analysis of observed erosion/corrosion problems was accomplished. Variable inlet guide vane aerodynamic loss characteristics were determined. Generally satisfactory results with linerless insulation are resulting in extended use and …

A large Leitz Universal Toolmakers' Microscope, Model UWM, was modified for use in an explosive environment defined by the National Electric Code as a rating of Class II, Group G. Use of the explosion-proof (EP) microscope provided a means for dimensionally measuring delicate pressed explosive material without contacting the material and subjecting it to possible contamination and mechanical destruction. Inexpensive design concepts, material, and hardware were used to effect the modifications of explosion-proofing. The accuracy, sensitivity, and repeatability of the Toolmakers' Microscope were not altered by the modification. (auth)

Measurements of the /sup 14/N/sup 15/N//sup 14/N/sup 14/N and /sup 16/O/sup 18/O//sup 16/O/sup 16/O Raman intensity ratios have been made in air samples and pure gas samples. A high-resolution double monochromator was used with a C31034A-02 PM tube to count the photons scattered from a low-powered laser beam (1--2 watts). Standard high-speed modular electronics (approximately 10 ns resolution) were used to process the output pulses. The ..delta..J = 0 vibrational bands of /sup 14/N/sup 15/N and /sup 16/O/sup 18/O were observed to be essentially free of all interference except dark noise of approximately 3 counts/sec. The adjacent rotational structure of /sup 14/N/sup 14/N and /sup 16/O/sup 16/O showed no appreciable overlap with the ..delta..J = 0 bands of interest. Detailed spectra, comparison of the Raman intensity ratios with mass spectrometer isotope ratios, and Raman cross section data for /sup 14/N/sup 15/N and /sup 16/O/sup 18/O are presented. The applicability of Raman scattering as a technique for precision measurement of isotope ratios is discussed.

In the past several years, the Lawrence Livermore Laboratory CLYDE code has been revised and modified extensively. Processing of photon production was incorporated, and the processing of higher-order S/sub n/ transfer matrices was speeded up. A Doppler broadening option was also added. On the other hand, the CLYDE routines that process evaporation models and cumulative probability distributions (I = 5,6) were deleted. The processing of Monte Carlo output was spun off into a separate code, CTART. 3 figures, 11 tables. (auth)

A broad range of problems in the legal and institutional environment which hampers the development of the geothermal industry is discussed. The topics include: the development of geothermal energy; pre-leasing procedures--public vs. private assessment; exploratory permits and related strategies; the rate of geothermal leasing-past and future; compensation strategies; lessee qualifications; lands available for leasing; noncompensatory lease terms; ongoing leasehold and production requirements; problems of ''secondary'' geothermal uses; and water law conflicts. (LBS)

Progress is summarized in experimental and analytical investigations of the neutronics and photonics of benchmark mockups of LMFBR blankets. During the reporting period work was devoted primarily to a wide range of analytical/numerical investigations, including blanket fuel management/economics studies, evaluation of improved blanket designs, and assessment of state-of-the-art methods for gamma heating calculations. Experimental work included preparations for resumption of MIT Reactor operations, primarily fabrication of improved steel reflector assemblies for blanket mockups, and development of an improved radiophotoluminescent readout device for LiF thermoluminescent detectors. The most significant finding was that the neutronic and economic performance of radial blanket assemblies are essentially independent of core size (rating) for radially-power-flattened cores. Hence the methodology and results of current experiments and calculations should be valid for the large commercial LMFBR's of the future.

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The initial results of a comparative study of the radiation strengthening and damage structures produced in Cu and Nb by D-T fusion and fission reactor neutrons are described. The radiation strengthening produced by a given fluence of fusion neutrons above about 10$sup 17$n/cm$sup 2$ is equal to that produced by a fluence of fission reactor neutrons (E greater than 0.1 MeV) ten times as great. This difference is about twice as large as would be expected if the strengthening scaled with damage energy or dpa. Initial transmission electron microscopy observations of the damage structures in fusion and fission reactor neutron irradiated copper indicate that the same type of primary structural defects, vacancy and interstitial point defect clusters and small dislocation loops with a/3 (111) and a/2 (110) Burgers vectors, are produced in both cases. The difference in the radiation strengthening produced by fusion and fission reactor neutrons in Cu appears to result from a substantially greater rate of accumulation of damage, in the form of point defect clusters, during irradiation with fusion neutrons than during irradiation with fission reactor neutrons plus a significant difference in the size and spatial distributions of the damage clusters. (auth)

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