As now being explored for fusion applications confinement systems based on the mirror principle embody two kinds of plasma regimes. These two regimes are: (a) high-beta plasmas, stabilized against MHD and other low frequency plasma instabilities by magnetic-well fields, but characterized by non-Maxwellian ion distributions; (b) near-Maxwellian plasmas, confined electrostatically (as in the tandem mirror) or in a field-reversed region within the mirror cell. Common to both situations are the questions of anomalous transport owing to high frequency instabilities in the non-maxwellian portions of the plasmas. This report will summarize the status of theory and of experimental data bearing on these questions, with particular reference to the high temperature regimes of interest for fusion power.

The verification and adjustment of plant models for decay heat removal analysis using a mix of engineering judgment and formal techniques from control theory are discussed. The formal techniques facilitate dealing with typical test data which are noisy, redundant and do not measure all of the plant model state variables directly. Two pretest examples are presented.

An enclosed 10-acre old-field plot treated in June 1969, with chlorine-36 labeled DDT was sampled each year from 1969 through 1974 to monitor the fate of the insecticide in the soil and biota. In order to provide data on compartmentalization of DDT in the vegetation, invertebrates and vertebrates inhabiting the plot, sampling was carried out to estimate both body burdens of DDT and biomass of populations. Another aspect of this study, the determination of rates of accumulation of residues by invertebrates and vertebrates, has been reported previously (Forsyth and Peterle 1973; Forsyth et al. 1975; Peterle 1975). This report describes (a) temporal patterns of DDT residues in soil and biota from 1969 through 1974 and (b) quantities of DDT held in the soil and biotic compartments of the ecosystem. Part II of the report is concerned with translocation and accumulation of/sup 14/C-DDT.

Coring of Well R-109 (Washington County, Ohio) was accomplished in August 1976. A total of 25 samples were collected. Hydrocarbon gas analyses indicate that higher chain hydrocarbon gases (C/sub 2/-C/sub 5/) make up a significant portion of total hydrocarbons in the shales, but methane is still the dominant single gas. Distinct relationships exist between the carbon and hydrocarbon gas contents, showing increase in hydrocarbon gas contents with increasing carbon. Similar relationships between hydrogen and hydrocarbon gas contents exist, though they are not as pronounced. Gas contents appear not to be related to the bulk densities in any quantitative manner, though organic contents (carbon and hydrogen) seem to be related to bulk density values much more clearly. R-109 shales are virtually impermeable to gases and other fluids, as attempted helium gas permeability measurements indicated extremely small (< 10/sup -12/ Darcy) permeability values.

A code used for simulation of classical radial transport in the 2XIIB experiment has been modified to simulate radial transport in TMX. Results have been obtained using classical transport coefficients and also using very simple trial neoclassical resonant transport coefficients. Comparison of the results obtained with solely classical transport and with both classical and neo-classical transport indicate that neoclassical transport depresses the ion density by approximately 5%. The central cell ion temperature is increased by approximately by the neo-classical transport, as is the electron temperature.

The probabilistic approach to nuclear reactor safety is playing an increasingly significant role. For the liquid-metal fast breeder reactor (LMFBR) in particular, the ultimate application of this approach could be to determine the probability of achieving the goal of a specific line-of-assurance (LOA). Meanwhile a more pressing problem is one of quantifying the uncertainty in a calculated consequence for hypothetical core disruptive accident (HCDA) using large codes. Such uncertainty arises from imperfect modeling of phenomenology and/or from inaccuracy in input data. A method is presented to determine the confidence level in consequences calculated by a large computer code due to the known uncertainties in input invariables. A particular application was made to the initial time of pin failure in a transient overpower HCDA calculated by the code MELT-IIIA in order to demonstrate the method. A probability distribution function (pdf) for the time of failure was first constructed, then the confidence level for predicting this failure parameter within a desired range was determined.

Forged HP 9-4-20 steel exhibits a high yield strength (1240 MPa (180 ksi)), a high fracture toughness (K/sub Ic/) (120 MN/m/sup 3/2/ (110 ksi ..sqrt..in)), in good weldability. The alloy was studied to determine some of its corrosion and stress-corrosion characteristics, especially after welding. Potentiodynamic-polarization studies established that pitting of the steel was most severe when the chloride ion concentration was high and the pH of the solution was low. Higher potentials (approaching 1 V) caused increased corrosion rates also. Pitting of the welded samples was not preferential to any part of the weld and was uniform on both the base metal and weld. Dead-weight stress-corrosion tests demonstrated that welding did not increase susceptibility of the alloy to stress corrosion. The specimens failed in a ductile manner from the increased tensile load as the cross-sectional area was reduced by dissolution of the metal in the corrosive solution.

The objective of this program was to evaluate mullite in contact with molten silicon to be used as a substrate for Honeywell&#x27;s Silicon-On-Ceramic process and as a container for melting solar grade silicon. A further requirement was to fabricate respective substrates and containers. To maintain solar grade silicon purity levels, the mullite must generally introduce less than 10/sup 15/ atoms/cc of impurities. To evaluate the mullite-molten silicon interaction, a series of bodies were made with variations in density, alumina-silica ratio and glass-crystalline ratio. These materials were tested in a sessile drop technique. None of the variations stood up to extended exposure to molten silicon sufficiently to be recommended as a contaner material. However, directional solidification experiments by Jet Propulsion Laboratory suggest that, under proper conditions, contamination of the silicon by mullite containers can be minimized. To improve an already good thermal expansion match between mullite and silicon, compositional variations were studied. Altering of the alumina-silica ratio was determined to give a continuously varying thermal expansion. Thus, a composition can be selected to give the desired thermal expansion match with silicon.

A comparison is made between three different dynamic analysis methods commonly used in the analysis of nuclear facilities. The methods are applied to a typical non-reactor type nuclear facility; namely, an early configuration of the High Performance Fuel Laboratory which was to have been designed and constructed to house an automated fuel process line on the Hanford Reservation near Richland, Washington. The fuel to be handled was mixed plutonium and uranium in powder and pellet form which, therefore, required design for severe earthquake and tornado conditions. The structure is a two-story reinforced concrete shear wall building with a high bay on one end. The comparison is made for earthquake motion in the lateral horizontal direction only. The first method employs a three degree of freedom spring mass system with the masses lumped at the three floor and roof slab levels. After shears are obtained they are distributed to the shear walls in proportion to their stiffnesses. Floor and roof slabs are assumed rigid but eccentricities are accounted for in the shear distribution. The second method utilizes a pseudo three-dimensional stick model. The shear walls and horizontal floor and roof diaphram are modeled as three dimensional beam elements using the SAP …

Progress in all tasks is reviewed briefly. Charts which represent the monthly reports are included. The appendices include: a summary of additional needs, heat pump model description, heat pump model preliminary results, an interim report, and simplified methodologies. (MHR)

Major emphasis during the period was centered on improving the material properties of electrodeposited CdTe. Using newly devised means for peeling thin CdTe films off the ITO-coated glass substrates, it was possible to accurately measure material density and electrical resistivity. Density proved to be 40% below the bulk CdTe figure of about 6 gm/cm/sup 3/, while resistivity of supposedly doped CdTe films exceeded 10/sup 5/..cap omega.. - cm. These findings prompted initiation of a beneficial change in plating procedures which increased the thin film polycrystalline CdTe density to the bulk value while, at the same time, good columnar growth was obtained. Films made under the old plating process were made into Schottky diodes showing good uniformity and V/sub oc/ values generally exceeding 0.5V. Short circuit current of the best of these was 9.5mA/cm/sup 2/ despite the fact that light entered through a thick gold film and was strongly attenuated.

A computer controlled ultrasonic scanning system and a data acquisition and analysis system have been developed to perform the inservice inspection of welds in stainless steel sodium piping in the Fast Flux Test Facility. The scanning equipment consists of a six axis motion mechanism and control system which allows full articulation of an ultrasonic transducer as it follows the circumferential pipe welds. The data acquisition and analysis system consists of high speed ultrasonic waveform digitizing equipment, dedicated processors to perform on-line analysis, and data storage and display equipment.

Progress is reported in research on the following subjects: gas chromatographic/mass spectrometric analysis of thermal degradation products from wood and composite burns; corrosion in the experimental ducting of the fire test cell; on-line x-ray fluorescence analysis of transition metals in waste water: Phase II; fire environmental tests for self-contained breathing apparatus; developments in neutron spectrometry; and, intermediate energy x-ray spectra for general shielding calculations. (JGB)

The physical properties of brittle materials are of interest because of the rapidly expanding use of these material in high-pressure and shock wave techology, e.g., geophysics and explosive compaction as well as military applications. These materials are characterized by unusually high sonic velocities, have large dynamic impedances and exhibit large dynamic yield strengths.

In conclusion, it may be stated that: Recycle processing of SRC-I coal extract produced an equilibrium recycle solvent containing 9 weight percent hydrogen after two recycle passes in the PDU; no refractory 850/sup 0/F+ material was detected when recycling 500/sup 0/F+ material; an 850/sup 0/F+ conversion of approximatly 87 weight percent (based on fresh SRC-I feed) was obtained during recycle processing at temperatures of 790 to 810/sup 0/F; a distillate product (390 to 850/sup 0/F) containing &lt; 0.3 weight percent nitrogen was routinely obtained during recycle processing at the above noted high conversion; and in the recycle mode of processing coal extract at 780/sup 0/F, a catalyst addition rate of one pound of catalyst per ton of moisture-free coal gave an 850/sup 0/F+ conversion of 62 weight percent (based on fresh SRC-I feed) and a nitrogen content in the distillate fraction (390 to 850/sup 0/F) of 0.36 weight percent.

Over 50 neutral beam sources (NBS) of the joint Lawrence Berkeley Laboratory (LBL)/Lawrence Livermore Laboratory (LLL) design have been manufactured, since 1973, in the LLL Neutral Beam Source Facility. These sources have been used to provide start-up and sustaining neutral beams for LLL mirror fusion experiments, including 2XIIB, TMX, and Beta II. Experimental prototype 20-kV and 80-kV NBS have also been designed, built, and tested for the Mirror Fusion Test Facility (MFTF). (MOW)

A diametral extensometer was developed and employed during temperature ramp tests with the Fuel Cladding Transient Tester (FCTT). Plastic strain measurements were performed using unirradiated 20% cold-worked AISI 316 stainless steel tubing ramped at 5.6 and 111/sup 0/C/s with internal pressures from 3.4 to 93.1 MPa. Results demonstrated that plastic deformation can occur at stresses well below the conventional 0.2% yield strength and that most deformation in such tests occurs in the final 50/sup 0/C before failure. Postirradiation tests were performed on fuel pin cladding irradiated to 5.8 x 10/sup 22/ n/cm (E &gt; 0.1 MeV) with irradiation temperatures to 540/sup 0/C. The tests showed that, for test pressures of 17.2 MPa or less, the stress-strain behavior was unchanged from unirradiated material behavior although the strains at failure were greatly decreased.

Progress is summarized in the following areas: fissile build-up in internal blankets, reference cores, and power peaking.

Studies are described which were performed for the Near Term Hybrid Vehicle program to determine passenger car usage patterns and to correlate these trip mission characteristics with vehicle design and performance specifications. (LCL)

United States defense nuclear wastes are presently in tank storage, largely as sludges comprising Fe, Mn, Ni, U and Na oxides and hydroxides, together with 0.5 to 5 percent of fission products and actinides (exclusive of uranium). The relative proportions of Al, Fe, Mn, Ni, U and Na in the sludges from different tanks vary considerably, except that (Fe + Al + Mn) are by far the major components and Fe is more abundant than Mn. Typical compositions of some calcined sludges from Savannah River are given. This paper briefly describes how the SYNROC process, utilizing straightforward technology, can be readily adapted to the problem of defense waste immobilization, yielding a dense, inert, ceramic waste-form, SYNROC-D. Two classes of processes are discussed - one designed to immobilize sludges containing normal amounts of sodium and the other designed for otherwise similar sludges which are, however, strongly depleted in sodium as a result of more efficient washing procedures.

Exposure to noise, H{sub 2}S, NH/sub 3/, hazardous chemicals and wastes, and heat are the major occupational health hazards associated with geothermal energy development - from drilling to power production. Exposures to these agents, although not unique to geothermal energy development, occur in situations peculiar to the industry. Reports show that occupational illnesses associated with geothermal energy development are increasing, while the corresponding rates from all power production are decreasing. Most of those related to geothermal energy result from the H{sub 2}S-abatement systems used in response to environmental pollution regulations.

NOAA/DOE has selected three concepts for a baseline design of the cold water pipe (CWP) for OTEC plants: (1) a FRP CWP of sandwich wall construction suspended from the Applied Physical Laboratory/John Hopkins University (APL/JHU) barge at a site 200 miles east of the coast of Brazil using a horizontal deployment scheme; (2) an elastomer CWP suspended from the APL/JHU barge off the southeast coast of Puerto Rico using either a horizontal or vertical deployment scheme; and (3) a polyethylene CWP (single or multiple pipe) suspended from the Gibbs and Cox spar at the Puerto Rico site using a horizontal deployment scheme. TRW has developed a baseline design for each of these configurations. This volume of the report includes the following appendices: (A) fiberglass reinforced plastic cold water pipe (specification and drawingss); (B) specification for polyethylene CWP; (C) elastomer pipe drawings; (D) drawings for OTEC 10/40 hull/CWP transitions; (E) structural design of OTEC 10/40 CWP support and CWP transitions; (F) universal transition joint for CWP; (G) dynamic spherical seal of CWP; (H) at-sea deployment loads - surface towing loads; (I) OTEC 10/40 CWP deployment up-ending loads; (J) cost estimates for OTEC 10/40 hull/CWP transitions; and (K) OTEC 10/40 CWP deployment …

The second phase of a contract between the California Energy Commission and the G.R.I.P.S. Commission (Geothermal Research Information and Planning Services) is reported. The activities include: environmental studies; information exchange; funding proposals; and administration of GRIPS. (MHR)

Effective intrusion protection for uninhabited sites scattered widely throughout a large geographic area can be a difficult and expensive proposition. When the sites are important enough to require continuous surveillance, the problem is even worse. Roving patrols are not effective, and conventional alarms don't provide enough information to allow a meaningful response. Television systems have possibilities but also disadvantages: the usual system is both costly and inflexible. This paper describes our solution to the problem: a cost effective instrusion protection system used to simultaneously protect many sites scattered over many square miles, with realtime surveillance from a central point. The system is based on a state-of-the-art FM CATV concept that is capable of providing surveillance for multiple sites, is modular in design for quick setup, flexible, and easily maintained. A electronic motion detector is incorporated for each site under surveillance, with a visual and audible alarm to alert the observer at the central control console. The observer can then bring the intruded site up on a large-screen monitor for detailed assessment. The system is relatively economical as all equipment is commercially available and all installation is straight-forward and follows usual CATV construction practices.