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)

Measurement of /sup 129/I at low levels is required for effluent control, environmental assessment and tracer studies in the natural environment. Low level /sup 129/I analysis has also been used for measurement of natural-fission-produced /sup 129/I in minerals and ores as well as meteorites. The most sensitive method for /sup 129/I measurements is neutron activation analysis of iodine separated from a suitable sample. Minimum sample processing prior to neutron activation is desirable in order to reduce chances of sample contamination with uranium or /sup 129/I. A potential interference in the activation analysis method is the production of /sup 129/I (/sup 130/I) from Te impurities in the irradiated ampoule. Procedures have been developed and applied to measurement of the magnitude of the potential Te interference. One-tenth of a microgram of Te in the irradiated ampoule is sufficient to produce interference in the analysis. This is detectable by either radiochemical Te measurements or by /sup 131/I detection in the iodine fraction from the irradiated ampoule. This paper discusses the procedures and results of Te interference studies in /sup 129/I activation analysis. The interference was found to be insignificant for most analyses. 5 tables.

The findings of the 1977 State Geothermal Resources Task Force are divided into four main categories: well siting, power plant siting; environmental problems; and miscellaneous areas. California's 1978 legislation is described using the same categories. The key difficulties still harassing the state's geothermal industry are described including: control over air quality at the Geysers; powerplant finance; a binary cycle demonstration; federal land use decisions; and miscellaneous concerns. (MHR)

The specifics of the permitting process, land access, power plant siting, water law, and other legal or institutional barriers or conflicts are presented for each of the most highly regarded target electric prospects in the five Pacific Rim states: California, Hawaii, Alaska, Oregon, and Wasington. (MHR)

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.

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.

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.

A study of depository recharge and repressurization has been reviewed. Specific consideration has been given to the validity of two initial assumptions in that study. The first was a decision to ignore lateral flow and end effects into the depository. The second was a decision to ignore thermal effects. The review has been made with particular concern to assessing the sufficiency of the Golder model for estimation of worst-case (minimum) recharge-repressurization time (RRT) in a bedded salt depository. It has been concluded that several errors by Golder may have little net effect on this worst case scenario. Combination of lateral flow and thermal effects may, however, reduce the value of the Golder model for estimation of minimum RRT in a bedded salt facility. Several subjects for further model development are suggested, though the availability of data to support such models is not addressed.

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.

Lawrence Livermore Laboratory (LLL) is conducting research on the seismic risk of nuclear power plants through the Seismic Safety Margins Research Program (SSMRP). Phase I of the SSMRP will include a study of an existing plant and site. Results are presented of a study of existing and planned nuclear power plants in the United States. Selection criteria were developed and a recommendation for a specific plant for the SSMRP Phase I effort is given. Power plant characteristics including types of nuclear steam supply steam, containment structure, electric power capacity, geographic location, site seismicity, and foundation soil properties were evaluated.

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 > 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.

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 …

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 standard colorimetric procedure for thorium was improved by using lanthanum carrier precipitation of thorium fluoride, conversion to sulfate, and colorimetric measurement with thoron. Four types of anion-exchange resins were evaluated using breakthrough capacity, elution volume, and the neptunium-plutonium ratios in both wash solutions and ion-column eluates as criteria, and 100 to 200 mesh Dowex 1 x 4 resin had the most favorable separation characteristics. Use of commercially available aqueous cleaner followed by water and acetone rinses was found to be superior to other techniques for cleaning uranium samples prior to carbon analysis. The substitution of sodium bisulfate for potassium pyrosulfate in the fusion procedure has lead to a more efficient dissolution process for oxide samples undergoing plutonium assay and the determination of uranium impurities. Sealed-capillary differential thermal analysis experiments were performed to assess the relative reactivities of iron, stainless steel, copper, beryllium, aluminum, and plutonium with trichloroethylene, methyl chloroform, and Freon TF. Results obtained by a method involving reduction of plutonium with titanium (III) chloride followed by titration with standard cerium (IV) sulfate solution are comparable to those obtained by an established amperometric-titration method.

In an attempt to correlate x ray reflectivity with carbon mirror surface quality the relative reflectivity of five mirrors of different smoothness and optical flatness is compared. Measured and theoretical reflectivity values are in agreement for mirror smoothness <30 A and optical flatness <1000 A. Other correlation could not be established. 4 references.

Experiments such as the 2XIIB experiment at Livermore have established the ability of mirror systems to confine high temperature, high density plasmas at central beta values exceeding unity. Given these results the next tasks for the mirror approach are to explore means for increasing the energy gain factor Q and to scale up the plasma volume, both of these requirements deriving from economic constraints. This report discusses means for increasng Q, including recent improvements in the tandem mirror concept and design studies of the field-reversed mirror in the context of upcoming and proposed scaled-up mirror experiments.

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)

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)

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.

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.

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)

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.

The design of an apparatus which will allow direct detection of stable fractional elementary charges if present on matter at the level of 10/sup -24/ per nucleon is described in detail. This method depends upon production of a highly uniform and parallel stream of conductive spheres which are charge analyzed by passage through a static electric deflecting field. 6 references.

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.