This paper presents ideas and speculations on possible diagnostic instrumentation for use in missile flight testing. A plea is made for increased instrumentation efforts. There is some discussion of telemetry methods.

Results are set forth for a continuing reconnaissance-level assessment of promising geothermal sites scattered through California. The studies involve acquisition of new data based upon field observations, compilation of data from published and unpublished sources, and evaluation of the data to identify areas suitable for more intensive area-specific studies. Forty sites were chosen for reporting on the basis of their relative potential for development as a significant resource. The name and location of each site is given, and after a brief synopsis, the geothermal features, chemistry, geology, and history of the site are reported. Three sites are recommended for more detailed study on the basis of potential for use by a large number of consumers, large volume of water, and the likelihood that the resource underlies a large area. (LEW)

This report presents the status of the work performed on a program for test and evaluation of gas cleanup devices for PFBC combined cycle systems. The work was performed during the period September 1, 1981 through November 30, 1981. This is the second quarterly report since the start of the program. Work has continued to restore the pressurized fluidized bed (PFB) technology plant at Wood-Ridge, N.J. to an operational status. Preliminary designs to incorporate each of three advanced gas cleanup devices following a first stage low pressure drop inertial type separator were previously completed. The advanced devices provided by suppliers under a separate DOE contract include a ceramic bag filter, an electrostatic precipitator and an electrostatically enhanced inertial separator. The final design activity necessary to modify the facility for the test of the ceramic bag filter has been completed. Testing of each hot gas cleanup device concurrently with a DOE supplied advanced concept particle sampling system and an alkali metal content measurement system is planned to start in April 1982.

The concept of elastic core stress is used to derive bounds for the maximum inelastic strains in shells of revolution subjected to pressure and cyclic thermal loads in the creep regime. Solutions are obtained for primary membrane stresses of arbitrary biaxiality and thermal bending of arbitrary biaxiality. The stress regimes where previously derived uniaxial solutions can be conservatively used are defined. The new biaxial solutions provide more efficient bounds than the uniaxial solutions for the maximum strains in pressurized spheres and cylinders.

The main objective is to elucidate the mechanisms which control cellular proliferation during wound healing in tissues of the eye.

None

This report describes the results of a detailed literature review of radionuclide transport models applicable to rivers, estuaries, coastal waters, the Great Lakes, and impoundments. Some representatives sediment transport and water quality models were also reviewed to evaluate if they can be readily adapted to radionuclide transport modeling. The review showed that most available transport models were developed for dissolved radionuclide in rivers. These models include the mechanisms of advection, dispersion, and radionuclide decay. Since the models do not include sediment and radionuclide interactions, they are best suited for simulating short-term radionuclide migration where: (1) radionuclides have small distribution coefficients; (2) sediment concentrations in receiving water bodies are very low. Only 5 of the reviewed models include full sediment and radionuclide interactions: CHMSED developed by Fields; FETRA SERATRA, and TODAM developed by Onishi et al, and a model developed by Shull and Gloyna. The 5 models are applicable to cases where: (1) the distribution coefficient is large; (2) sediment concentrations are high; or (3) long-term migration and accumulation are under consideration. The report also discusses radionuclide absorption/desorption distribution ratios and addresses adsorption/desorption mechanisms and their controlling processes for 25 elements under surface water conditions. These elements are: Am, Sb, C, …

This report describes the ability of the Purex Plant to effectively control iodine-129 emissions. Based on historical evidence, the current Purex Plant iodine control system appears capable of meeting the goal of limiting gaseous iodine-129 emissions at the point of discharge to levels stipulated by the Department of Energy (DOE) for an uncontrolled area. Expected decontamination factors (DF`s) with the current system will average about 100 and will be above the calculated DF`s of 2.2 and 87 required to meet DOE yearly average concentration limits for controlled and uncontrolled areas respectively, but below the calculated DF of 352 required for meeting the proposed Environmental Protection Agency (EPA) mass emission limit. Chemical costs for maintaining compliance with the DOE limits will be approximately $166 per metric ton of fuel processed (based on a silver nitrate price of $12.38/oz). Costs will increase in proportion to increases in silver prices.

Two nuclear sites have been under intensive study by the Nevada Applied Ecology Group (NAEG) during 1980 and 1981, NS201 in area 18 and NS219,221 in area 20. In support of the various studies Los Alamos National Laboratory (Group LS-6) has provided consultation and evaluations relative to radionuclide distributions in soils inundated with radioactive debris from those tests. In addition, a referee effort was also conducted in both analysis of replicate samples and in evaluating various data sets for consistency of results. This report summarizes results of several of the data sets collected to test certain hypotheses relative to radionuclide distributions and factors affecting calculations of hypotheses relative to radionuclide distributions and factors affecting calculations of radionuclide inventories and covers the period February 1980 to May 1981.

A single board MC 68000 based computer has been assembled and bench marked against the CDC 7600 running portions of the pattern recognition code used at the MPS. This computer has a floating coprocessor to achieve throughputs equivalent to several percent that of the 7600. A major part of this work was the construction of a FORTRAN compiler including assembler, linker and library. The intention of this work is to assemble a large number of these single board computers in a parallel FASTBUS environment to act as an on-line and off-line filter for the raw data from MPS II and ISABELLE experiments.

An important effect of water submersion on the dynamic response of a structure is the increase in effective damping. The dynamic response of submerged structures is of interest in the nuclear power industry for reasons of operational safety during seismic and other dynamic excitations. In this paper, the added damping contribution that results from the viscosity of water and the dependence of the contribution on structural size are examined. Other factors considered are the applicable range of viscous damping with respect to displacement amplitude and, as far as damping is concerned, how far neighboring members must be from each other to respond as if in open water. An expression is derived for relating the damping value to structural size. Estimated added-damping values for representative fuel elements, fuel bundles, and main steam-pressure-relief-valve lines are given based on our derived expression for added damping.

The question of neutrino mixing is considered within the grand unified field theory. (GHT)

The operation of the major components used for controlling the phase and field level of the PEP RF cavities is described. The control electronics of one RF station is composed of several control loops: each cavity has a tuners' servo loop which maintains the frequency constant and also keeps the fields of each cavity balanced; the total gap voltage developed by a pair of cavities is regulated by a gap voltage controller; finally, the phase variation along the amplification chain, the klystron and the cavities are compensated by a phase lock loop. The design criteria of each loop are set forth and the circuit implementation and test results are presented.

Generic well models have been constructed for eight major geothermal resource areas. The models define representative times and costs associated with the individual operations that can be expected during drilling and completion of geothermal wells. They were made for and have been used to evaluate the impacts of potential new technologies. Their nature, their construction, and their validation are discussed.

The INTOR reactor shield system consists of the blanket, bulk shield, penetration shield, component shield, and biological shield. The bulk shield consists of two parts: (a) the inboard shield; and (b) the outboard shield. The distinction between the different components of the shield system is essential to satisfy the different design constraints and achieve various objectives.

In the unresolved resonance region cross sections are represented with statistical resonance parameters. The average values of these parameters are chosen in order to fit evaluated infinitely dilute group cross sections. The sensitivity of the shielded group cross sections to the choice of mean resonance data has recently been investigated for the case of /sup 235/U and /sup 239/Pu by Ganesan and by Antsipov et al; similar sensitivity studies for /sup 238/U are reported. (WHK)

The meson factories such as the Los Alamos Meson Physics Facility have made possible high fluence medium energy proton beams that can be used for spallation reactions to produce macro quantities of unstable isotopes. Targets of over 10 g/cm/sup 2/ can be exposed to total fluence approaching 1 A-hour resulting in spallation yields in the 0.01-10 mg range for many isotopes of potential interest for nuclear structure studies. With the use of hot cell facilities, chemical processing can isolate the desired material and this coupled with subsequent isotope separation can result in usable quantities of material for nuclear target application. With off-stable isotopes as target materials, conventional nuclear spectroscopy techniques can be employed to study nuclei far from stability. The irradiation and processing requirements for such an operation, along with the isotope production possibilities, are discussed. Also presented are initial experiments using a /sup 148/Gd (t/sub 1/2/ = 75a) target to perform the (p,t) reaction to establish levels in the proposed double magic nucleus /sup 146/Gd.

The model of Newhouse for thermal propagation of long normal regions in thin superconducting films on good thermal conducting substrates has been verified. Measurements show much slower velocities for short regions, but the dependence is compatible with a new model calculation. Stable hot spots are found which agree semi-quantitatively with a modified hot-spot calculation.

This paper describes ongoing research at ORNL to develop a man/machine interface system that can be used to remotely control a system composed of a transporter base and a force-reflecting, servo-controlled manipulator. A unique feature of the concept is the incorporation of totally remote operation. Thus, a major objective is the requirement that an operator have a sense of presence in the remote environment. Man/machine interface requirements for this totally remote operation remain to be developed. Therefore, a simulator is being built to optimize such requirements and the developments are discussed.

Components, subsystems and systems will be subjected to inspection and test as necessary to ensure compliance to applicable specifications, Acceptance Test Procedures and/or customer requirements. Quality Assurance will inspect each component, subsystem and system for selected mechanical and electrical defects. In addition, Quality Assurance will either perform, or verify performance of, and analyze, or verify analysis of, all required field and laboratory tests. If hardware is modified, repaired or replaced after final testing, necessary re-inspection and retest must be performed. Insofar as possible the component, subsystem or system will be released as acceptable upon completion of these activities. When nonconformances are detected during the course of site surveillance activities, MDAC or Gilbert/Commonwealth will initiate a Nonconformance Record for review by MDAC Quality Assurance and Project Engineering personnel. These nonconformances will be identified and dispositioned per MDAC Standard Practices with the advice and concurrence of Gilbert/Commonwealth personnel, if deemed appropriate. MDAC Quality Assurance personnel will witness the pre-operational testing and review the test data.

A preliminary assessment of the impacts resulting from incorporation of flywheel energy storage systems into automotive fleets in a large metropolitan city is described. Specifically, the case of taxicab fleet operation within New York City is examined. Based upon available taxicab operational data, a levelized life-cycle cost comparison between a standard internal combustion engine vehicle in present use as a taxicab and a projected hybrid flywheel-internal combustion engine vehicle (taxicab) has been generated. Energy conservation and environmental benefits are discussed and potential institutional barriers to rapid deployment of flywheel energy storage systems are identified. The results obtained from this study generally emphasize the value of incorporating flywheel energy storage systems into future vehicles designed for taxicab use.

The conditions under which a combined photovoltaic/thermal (PV/T) collector is more cost effective than separate flat-plate photovoltaic and thermal collectors are determined. The annual performance of the separate PV/T system and four different combined PV/T systems are simulated. Based on the equivalent electrical and thermal outputs and the 1986 DOE cost goal for PV modules (70 cents/Wp), the maximum allowable incremental cost to upgrade the conventional thermal collector to a combined PV/T collector is determined. For all of the cases considered in this study, the separate PV/T collectors are more cost effective than the combined PV/T collectors.

The objective of this work is to investigate methods for fabricating, characterizing and transporting cryogenic inertial confinement fusion targets on a continuous basis. A microprocessor-based data acquisition system has been built that converts a complete target image to digital data, which are then analyzed by automated software procedures. The low temperatures required to freeze the hydrogen isotopes contained in a target is provided by a cryogenic cold chamber capable of attaining 15 K. A new method for target manipulation and positioning is studied that employs molecular gas beams to levitate a target and an electrostatic quadrupole structure to provide for its lateral containment. Since the electrostatic target-positioning scheme requires that the targets be charged, preliminary investigation has been carried out for a target-charging mechanism based on ion-bombardment.

An x-ray secondary target method for routine determination of gallium, iron, and nickel in plutonium metal is described that has significant advantages over wet chemical analysis. Coupons requiring minimal preparation for analysis are produced as a breakaway tab on the plutonium ingot. All three elements are determined on the same coupon. Gallium is determined using an arsenic secondary target followed by iron and nickel using a zinc target. The analysis times are 5 minutes for gallium and 15 minutes for the combined iron and nickel. The method of analysis was evaluated in the range of from 0.5 to 1.5% gallium. Iron was investigated over the range of 67 to 3000 ppM and nickel from 64 to 110 ppM.