Umtanum Ridge in south-central Washington is the topographic expression of a complex anticline within the Yakima Fold system in the Miocene Columbia River Basalt Group. The Yakima Fold system, which is partly contained within the Hanford Site, is an example of a layered basalt sequence folded near the surface of the earth. The Pasco Basin stratigraphic nomenclature is used in this repot. Rockwelll Hanford Operations, under contract to the US Department of Energy, is investigating the feasibility of therminal high-level nuclear waste storage in mined repositories in basalt beneath the Hanford Site. Because thereis essentially no basalt within the Site that has not been involved in some folding, any potential location for a repository will be either on the limbs or near the hinge zone of a Yakima Fold structure. Umtanum Ridge is the best exposed Yakima Fold structure in the vicinity of the Site for studying the nature and three-dimensional style of deformation of a multilayered basalt sequence. The structural geometry, distribution of strain within the Umtanum structure and deformational mechanisms of the Umtanum Ridge are discussed.

An electromagnetic shower detector consisting of lead glass blocks and scintillator hodoscopes was constructed. During calibration runs detector resolutions were measured for single incident electrons. Performance of the detector for ..pi../sup 0/ and multi-photon showers, including sizable backgrounds, was studied during actual data runs. This detector was used in Fermilab Experiment 451.

This review briefly describes the laser system, spatial filter, computer control system, and the 46 cm disk amplifier. (MOW)

Data relative to proton and pion production produced in central collisions have been reviewed by S. Nagamiya. Therefore, the production of complex fragments is emphasized here. A presentation is made of experimental data on d, t, /sup 3/He emission and their discussion in terms of the existing models. The size of fireball derived from the analysis of complex fragments is compared to the results of pion interferometry experiment. Interesting features observed in the distribution of charged particles once an heavy fragment has been detected are reported. Finally, suggestions of phenomena to study with a 4..pi.. detector are given.

Recent experimental approaches for measurement of dry surface fluxes of sulfur compounds are reviewed and discussed with emphasis on surface layer studies. Evidence indicates that natural surfaces are sources as well as sinks for sulfur. Field results are related to requirements and implications in future studies of surface sulfur fluxes.

The shaping and plasma characteristics of doublet plasmas in Doublet III with high-Z limiters are described. Typical steady-state parameters at B/sub T/ = 24 kG are I/sub p/ = 1.5 MA, V/sub loop/ = 1.6 V, T/sub e/(O) = 1.0 keV, anti n/sub e/ = 4 x 10/sup 13/ cm/sup -3/, Z/sub eff/ = 2, q(O) approx. 1 and tau /sub E//sup e/(O) = 20 msec. Electron energy confinement and maximum plasma density are in agreement with standard circular tokamak empirical scaling laws. Chromium and molybdenum appear to be the dominant high-Z plasma contaminants, with relative concentrations of approx. 10/sub -4/. The central power balance does not appear to be dominated by high-Z impurity radiation.

Surface states on germanium p-i-n junctions have been investigated using deep level transient spectroscopy (DLTS) and collimated beams of 60 keV gamma-rays. The DLTS spectra have a characteristic signature for each surface treatment but the spectra are complex and not readily interpretable as to suitability for radiation detectors. Collimated gamma-ray beams give a direct measure of surface channel effects and typeness. Hydrogenated amorphous germanium (a-Ge:H) was explored as a surface layer to adjust the electrical state and passivate the surface. Our measurements show that these layers produce flat band conditions, introduce no additional noise and appear to be stable against a variety of ambients.

Two decades ago many people thought that there was very little left to occupy the researcher in the numerical initial-value problem for ordinary differential equations, but there has since been an enormous increase in the effort devoted to this problem and related software. The question is whether everything is finally done so that more difficult areas can be studied. The development of numerical solution techniques is examined from the identification of a problem to the never-final preparation of automatic codes for the solution of classes of similar problems. A number of ODE problems that are only a part of the way along this path of development are discussed. These problems include ones with highly oscillatory solutions, ones with frequent discontinuities, and ones in which very little accuracy is needed (and which should be integrated at low cost). 4 figures.

The main objectives of the 3rd Annual Biomass Energy Systems Conference were (1) to review the latest research findings in the clean fuels from biomass field, (2) to summarize the present engineering and economic status of Biomass Energy Systems, (3) to encourage interaction and information exchange among people working or interested in the field, and (4) to identify and discuss existing problems relating to ongoing research and explore opportunities for future research. Abstracts for each paper presented were edited separately. (DC)

A new centroid finding method for all detectors where the signal charge is collected or induced on strips of wires, or on subdivided resistive electrodes, is presented. The centroid of charge is determined by convolution of the sequentially switched outputs from these subdivisions or from the strips with a linear centroid finding filter. The position line width is inversely proportional to N/sup 3/2/, where N is the number of subdivisions.

Particulate material collected by filtration from the north Equatorial Pacific Ocean has been analyzed for plutonium and other radionuclides. Different filter pore size, types of filter substrates, flow rates, and sample volumes were evaluated. Retention of /sup 239 +240/Pu was found to vary with the sample volume filtered and was not greatly affected by the type of filter substrate, flow rate, or porosity tested. About 7 +- 3% of the /sup 239 +240/Pu activity in north Equatorial Pacific surface water is found with the particulate material filtered from 120 liters of water, while less than 1% is retained on samples with volume of 20,000-70,000 liters. Clearly an understanding of these results is necessary to correctly assess the quantity of plutonium, other radionuclides and trace elements associated with and transported by particulate material in the marine environment.

Setting performance criteria for systems that safeguard special nuclear material (SNM) involves many considerations: characteristics of adversaries attempting to divert SNM, safeguards response to attempts, costs of safeguards systems, and the consequences of diverted SNM. This paper describes an Aggregated Systems Model which is designed to assist decision makers integrate and evaluate consistently these diverse factors. Results from applying the model to a hypothetical facility handling SNM are summarized. The paper also describes a new performance criterion designed to measure the effectiveness of a safeguard system in deterring adversaries.

The giant dipole (GD) parameters of peak energy, width, and cross section were satisfactorily correlated for elements from V to Bi, assuming two overlapping peaks with a separation dependent on deformation. The energy dependence of the GD resonance is assumed to have a Breit-Wigner form, but with an energy-dependent width. The resulting gamma-ray strength function model is used to predict neutron capture cross sections and gamma-ray spectra for isotopes of Ta, Os, and Au. 23 references.

A survey was made of the instruments used for the determination of low energy beta radioactivity. Techniques commonly used are gas flow proportional counting, liquid scintillation counting, solid scintillation counting, and internal ionization chamber counting, solid state detector counting, and radiochemical separation followed by counting using one of the preceeding techniques. The first four techniques were examined and compared with each other. The sensitivities of the techniques were compared on the basis of the detection limits quoted for instruments described in the technical and reviewed literature. The detection limits were then related to the occupational and public individual maximum levels for air and water. Attention is focused primarily on the continuous monitoring of air for /sup 3/H and /sup 85/Kr, a medium energy ..beta..-emitter. It is clear that several continuous air monitoring instruments are readily available for measuring low energy ..beta.. concentrations, even in presence of certain other activity, at occupational levels. However, these instruments do not typically have sensitivities comparable to the public individual levels. Moreover, their capabilities for giving results in real time and for differentiating among the radionuclides actually present is limited.

The two DOE-owned facilities at Hanford, the Fuels and Materials Examination Facility (FMEF), and the Fusion Materials Irradiation Test Facility (FMIT), are described. The performance measurement systems used at these two facilities are next described. (DLC)

It appears that neutral beam heating will be the most viable method of raising the temperature of a plasma for some time to come. In fact, neutral beams may continue to be one stage of the heating program indefinitely. However, the external field, called the fringe field, of a Tokamak can impair the effectiveness and operation of the ion source and beam. Remember, a Tokamak is a large, air-core transformer coupled with a solenoid. The design process is summarized from start to finish. The source shield is used by way of example. Various parameters are examined and related to the design requirements. The different alloys are compared and the reader can follow the logic for the choice of material.

The meeting discussed the requirements of thermodynamics properties and analytical characterization methods needed for materials encountered in fossil fuel conversion processes. (LTN)

The Folksam office building in Farsta, near Stockholm, has operated since December 1977 with an energy use for direct space heating of only 60 kWh/m/sup 2/ (19,000 Btu/ft/sup 2/), which is only half the Stockholm average for new buildings. To this 60 kWh/m/sup 2/ must be added the typical electric use of another 60 kWh/m/sup 2/ for lights, equipment, fans, etc. Even though Stockholm has 3580 deg-day (C), new Swedish buildings are so well insulated that their temperature floats upwards during most winter working days. In the Folksam building, this surplus heat from 40 full-occupied hours per week is stored in hollow-core concrete slabs, and then is used to compensate for the heat losses during the remaining 128 unoccupied hours. The energy transport/storage system necessary to keep the indoor temperature comfortable, summer and winter, is called Thermodeck, and is described in detail.

Methods for developing reliability and maintainability information and integrating it into availability calculations useful in the design and development of nuclear fuel processing facilities are being investigated. Effective availability (actual productive time) is of greater interest than the more traditional operating availability. Actual productive time calculations allow more precise estimates of redundant equipment and surge storage needs. Judgmental estimates of relability and maintainability from personnel involved in equipment design can be used as interim data to guide developmental efforts. These data can be used in computer modeling of integrated process operations. Simulated process operations can be used to study the effects of various redundant equipment and surge storage configurations on plant effective availability.

A primary objective of the multilaboratory program is to prepare an updated and improved set of dosimetry, damage correlation, and the associated reactor analysis ASTM standards for LWR-PV irradiation surveillance programs. Supporting this objective are a series of analytical and experimental validation and calibration studies in Benchmark Neutron Fields, reactor Test Regions, and operating power reactor Surveillance Positions. These studies will establish and certify the precision and accuracy of the measurement and predictive methods which are recommended for use in these standards. Consistent and accurate measurement and data analysis techniques and methods, therefore, will have been developed and validated along with guidelines for required neutron field calculations that are used to (1) correlate changes in material properties with the characteristics of the neutron radiation field and (2) predict pressure vessel steel toughness and embrittlement from power reactor surveillance data.

A pair of 168/E microprocessors will be used to meet the realtime computing requirements of the SLAC Hybrid Facility. A SNOOP module and 168/E Interface provide the link between the host computer and the microprocessors. By eavesdropping on normal CAMAC read operations, the SNOOP provides a direct data transfer from CAMAC to microprocessor memory. The host computer controls the processors using standard CAMAC programmed I/O to the SNOOP.

Characterization of the fracture system in a repository is important, and its purpose should dictate the scale over which measurements must be made. The results discussed pertain to nearfield behavior of a rock mass and represent a practical limit to the degree to which discrete subsurface discontinuities can be defined by surface mapping and cross-correlation of observational borehole data. Discontinuities on the scale of the rock mass being studied can dominate its response, and should therefore be described according to their influence on the stability of the opening and local groundwater regime. Alternatively, if the size or continuity of a feature is much less than the scale of the rock mass in question, there will be insufficient data with which to validate a discrete characterization, hence a statistical approach is required.

A benchmark for calculation of neutron transport through iron is now available based upon a rigorous Monte Carlo treatment of ENDF/B-IV and ENDF/B-V cross sections. The currents, flux, and dose (from monoenergetic 2, 14, and 40 MeV sources) have been tabulated at various distances through the slab using a standard energy group structure. This tabulation is available in a Los Alamos Scientific Laboratory report. The benchmark is simple to model and should be useful for verifying the adequacy of one-dimensional transport codes and multigroup libraries for iron. This benchmark also provides useful insights regarding neutron penetration through iron and displays differences in fluxes calculated with ENDF/B-IV and ENDF/B-V data bases. (GHT)

Post-shot analysis of targets designed to achieve a diagnosible compression of DT gas to 2. g/cm/sup 3/ or 10 x liquid density is reported. The SHIVA laser provided 15 to 20 TW of 1.06 ..mu..m laser light. Detailed comparisons of diagnostic results with hydro-code calculations are made. Implications for laser light absorption/scattering, thermal conduction, suprathermal electron preheat, implosion symmetry, and pusher-fuel mix are discussed. Uncertainties of the density determination methods are analyzed. Good overall consistency is found, indicating strong support for the successful attainment of 1.-3. g/cm/sup 3/.