Some of the ramifications of user needs, user satisfaction, and the survey as a shaper of library policy are discussed. The presentation is in three parts: philosophical thinking on user needs and satisfaction, a modest tutorial on survey methodology, and a brief review of the Sandia National Laboratory Technical Library's use of surveys for information gathering and decision making. (RWR)

The neutral beam development group at ORNL has designed, constructed, and shipped four 50-kV, 100-A sources to PPPL to be used for neutral beam heating of the confined plasma on the PDX tokamak. These sources have higher current capability than scaled-down sources, and they are required to run for 0.5 s as opposed to the 0.3-s requirement for PLT and ISX-B sources. Due to an innovative electrode design, these higher power sources met these requirements and achieved a higher transmission efficiency - 76% of the total input power on target vs 60% for the original ISX-B and modified PLT sources or 40% for the original PLT sources. As a consequence, a power of 2 MW of neutrals to the torus target was achieved; this is a record for measured neutral power and exceeds that of any other power source expected to be used on such advanced tokamaks as TFTR and D-III. A theoretical consideration of the relevant Poisson-Vlasov equations for ions extracted from a plasma was used to optimize the ion optics. Using the same electrode design with a tetraode accelerating structure and a new, indirectly heated cathode, repeatable long pulse, high energy conditions of 70 kV, 7 A, 8 …

A brief review is given of some recent developments in the fields of optical model potentials; level densities; and statistical model, precompound, and direct reaction codes and calculations. Significant developments have occurred in all of these fields since the 1977 Conference on Neutron Cross Sections, which will greatly enhance the ability to calculate high-energy neutron-induced reaction cross sections in the next few years. 11 figures, 3 tables.

The second phase (Hanna IVB) of a coal gasification experiment near Hanna, Wyoming, was completed in September 1979. The experiment attempted to link and gasify coal between process wells spaced 34.3 meters apart. Intermediate wells were positioned between the process wells so that the link could be relayed over shorter distances. Reverse combustion linking was attempted over a 22.9-meter and a 11.4-meter distance of the total well spacing. Thermal activity was generally noted in the upper 3 meters of the coal seam during the link. Two attempts to gasify over the 34.3-meter distance resulted in the propagation of the burn front at the coal overburden interface. Post-burn evaluation indicates fractures as major influencing factors of the combustion process. The Hanna IVB field test provided much insight into influence that geologic features have on in situ coal combustion. The influence of these faults, permeable zones, and cleats, on the air flow patterns can drastically change the overall results of a gasification experiment and should be studied further. The overall results of Hanna IVB were discouraging because of the rapid decline in the heating values for the production gas and the amount of coal gasified. With more complete geologic characerization prior to …

The dependence of projectile double K-vacancy (hypersatellite) x-ray yields on target thickness for ions moving in thin solid targets is examined. For 2.3 MeV/amu Cl ions incident on C foils, the double-to-single K vacancy x-ray yield increases by a factor of 3.5 over the range of thicknesses investigated, reaching values as high as 30%. A quantitative explanation of the observed results is obtained using the three-component model of Gardner et al.

A systematic investigation of K x-ray production for 20-80 MeV Cl ions in collision with thin self-supporting Cu targets has been conducted. Target and projectile characteristic x rays and radiative electron capture (REC) have been measured as a function of target thickness for incident charge states q < z{sub 1} - 2. At 80 MeV data were also obtained for q = z{sub 1}- 1. Large enhancements in both characteristic x-ray production and REC were observed for q = z{sub 1}- 1. Measured x-ray yields were parametrized vs. target thickness using the model of Betz et al. and least squares fits to the data were performed. Target K x-ray production for q<z{sub 1}-2 is described reasonably well by the CPSSR + ECR theory. For q=z{sub 1} - 1 the enhancement in the x-ray yield is predicted quite well by the method of Gray et al· The mean fluorescence yield for the highly stripped Cl ions is determined and found to increase by a factor of about six over the range 20-80 MeV, having a value (~0.1) nearly equal to the single K-vacancy value at 20 MeV. The radiative lifetime for the projectile ions is found to be ~3 x 10{sup …

The compatibility of the inherent features of the high-temperature gas-cooled reactor (HTGR) and the closed-cycle gas turbine combined into a power conversion system results in a plant with characteristics consistent with projected utility needs and national energy goals. These characteristics are: (1) plant siting flexibility; (2) high resource utilization; (3) low safety risks; (4) proliferation resistance; and (5) low occupational exposure for operating and maintenance personnel. System design and evaluation studies on dry-cooled intercooled and nonintercooled commercial plants in the 800-MW(e) to 1200-MW(e) size range are described, with emphasis on the sensitivity of plant design objectives to variation of component and plant design parameters. The impact of these parameters on fuel cycle, fission product release, total plant economics, sensitivity to escalation rates, and plant capacity factors is examined.

Review is presented of the current status of neutron-induced reactions of interest to the fusion community in the 10- to 50-MeV neutron energy range. Although there has been significant activity in this area since the 1977 BNL Symposium on Neutron Cross Sections from 10 to 40 MeV, this review concludes that there are many areas which require more experimentation to obtain the requested accuracy. Examples of various neutron data obtained since 1977 are presented and compared to determine the extent of agreement. An attempt is made to determine what the prospects are for satisfying the fusion data needs defined by the US DOE based upon progress to date.

The development of hydrothermal energy for direct heat applications is being aided by twenty-two demonstration projects that are funded on a cost-sharing basis by the US Department of Energy, Division of Geothermal Energy. These projects are designed to demonstrate the technical and economic feasibility of the direct use of geothermal heat in the United States. Twelve of these projects are administered by the DOE-Idaho Operations Office with technical support from EG and G Idaho, Inc. Engineering and economic data for these projects are summarized in this paper. The data and experience being generated by these projects will be an important basis for future geothermal direct use projects.

A model for H/sup -/, D/sup -/ production by energetic particles reflecting from metal surfaces is discussed. The model employs the energy and angular distribution data derived from the Marlowe code. The model is applied to particles incident normally upon Cs, Ni, and Cs/Ni surfaces.

The data for negative ion reflection yields is analyzed using a backscattering model for the secondary emission coefficient. The enhancement of the secondary emission coefficient is discussed in terms of reflection, formation, and survival probabilities. The yield of negative ions from alkali/transition metal surfaces by low energy atoms emitted from the ion-source discharge is calculated. Volume production of negative ions generated by plasma-surface interactions in a low-work-function-surface bucket-discharge is discussed.

The emphasis in the preceding chapters has been on magnetic confinement of high temperature plasmas. The question of production and heating of such plasmas has been dealt with relatively more briefly. It should not be inferred, however, that these matters must therefore be either trivial or unimportant. A review of the history reveals that in the early days all these aspects of the controlled fusion problem were considered to be on a par, and were tackled simultaneously and with equal vigor. Only the confinement problem turned out to be much more complex than initially anticipated, and richer in challenge to the plasma physicist than the questions of plasma production and heating. On the other hand, the properties of high-temperature plasmas and plasma confinement can only be studied experimentally after the problems of production and of heating to adequate temperatures are solved. It is the purpose of this and the next chapter to supplement the preceding discussions with more detail on two important subjects: neutral-beam injection and radio-frequency heating. These are the major contenders for heating in present and future tokamak and mirror fusion experiments, and even in several proposed reactors. For neutral beams we emphasize here the technology involved, which …

The desire for multisecond beams in the 80-keV/nucleon energy range at 10 MW/module has emphasized the need for technological advances in several areas. At such beam energies, as much as 75% of the initial beam energy is retained in the unneutralized ion components. As a result, two questions immediately come to mind: how can one dispose of this energy; or better still, how can one efficiently recover this energy. The conventional way of treating such a problem is to deflect the ions out of the neutral beam and onto water-cooled plates or beam dumps. This method has worked satisfactorily for 40-keV/nucleon beams in excess of 1.5 MW and approx. 0.5 s. However, the power per unit area to be disposed of in the high power, multisecond beams mentioned above is beyond present-day technology. We have proposed and demonstrated a unique solution to this problem which not only removes the need for beam dumps but also returns from 50 to 80% of the energy contained in the full energy ion component directly and dynamically to the high voltage supply. In fact, the energy in the residual ion component is not expended. The tests were made on a PLT/ISX type beam line …

The 1980 symposium on Instrumentation and Control for Fossil Energy Processes was held June 9-11, 1980, New Cavalier, Virginia Beach, Virginia. It was sponsored by the Argonne National Laboratory and the US Department of Energy, Office of Fossil Energy. Forty-five papers have been entered individually into EDB and ERA; nine papers had been entered previously from other sources. (LTN)

A Workshop on Program Options in Intermediate-Energy Physics sponsored by the US Department of Energy was held at Los Alamos Scientific Laboratory, August 20 to 31, 1979. The scope of the workshop included all laboratories in intermediate-energy physics, worldwide, and all of these sent representatives to the workshop. The workshop addressed itself to the critical questions on nuclear and particle physics and how they can best be investigated by intermediate-energy accelerators. Among the questions that the workshop members considered were: (1) what are the important physics topics which might be understood through research on these accelerators in the next 10 years. These topics include, but are not restricted to, fundamental interactions and symmetries in particle physics, and nuclear modes of motion, structure, and reaction mechanisms; (2) what experiments should be undertaken to carry out the program. What are the kinematical conditions, accuracies, resolutions, and other parameters required to obtain the desired knowledge; (3) which accelerators are best suited for each experiment. What work at other laboratories (low-, intermediate-, or high-energy) could be undertaken to complement and/or supplement the proposed LAMPF program; and (4) what new facility capabilities should be explored for the long-term future. The workshop was divided into small …

Injection of H/sup 0/ into D/sup +/ plasmas with beam power P/sub b/ of up to 1.7 MW has produced rms betas of approx. 4%, volume-averaged betas of approx. 3%, and central betas of approx. 10% in the ISX-B tokamak. Although theoretical calculations indicate that the observed equilibria may be unstable to ballooning modes, no catastrophic loss of confinement has been observed, and beta continues to increase with injection power. In these beam-dominated high-beta discharges the electron and ion energy confinement times are still similar to those obtained with ohmic heating: ion energy confinement is neoclassical within a factor of approx. 2, and electron energy confinement follows the usual Alcator scaling. In high-power injection discharges the character of the magnetohydrodynamic (MHD) behavior changes, the particle confinement time decreases, and the inward impurity transport appears to be inhibited. These effects, however, may not be linked directly to beta.

Volume-produced H/sup -/ ions have been extracted from a multi-cusp ion source by using a standard extraction system. In addition, a molybdenum converter is installed in the source to generate surface-produced H/sup -/ ions. The H/sup -/ ion yield is measured by a mass spectrometer. Without cesium, the production of H/sup -/ ions by the surface process is very small compared with those generated by volume production. However, the presence of cesium can greatly enhance the surface production yield. The energy spectrum shows that the surface-generated H/sup -/ ions contain two distinct groups when cesium is added to the discharge. The energy of one group is essentially that of the sheath potential and appears to be produced by a desorption process. The second group of H/sup -/ ions have slightly higher energies and appear to be formed by a reflection process. Different types of converter materials have also been tested.

Abstracts of individual items from the symposium were prepared separately for the data base. (GHT)

Thirteen papers are included. Separate abstracts were prepared for each one. (MHR)

In order to assist in the study of instrumentation and analytical needs for reprocessing plants, a workshop addressing these needs was held at Oak Ridge National Laboratory from May 5 to 7, 1980. The purpose of the workshop was to incorporate the knowledge of chemistry and of advanced measurement techniques held by the nuclear and radiochemical community into ideas for improved and new plant designs for both process control and inventory and safeguards measurements. The workshop was athended by experts in nuclear and radiochemistry, in fuel recycle plant design, and in instrumentation and analysis. ORNL was a particularly appropriate place to hold the workshop since the Consolidated Fuel Reprocessing Program (CFRP) is centered there. Requirements for safeguarding the special nuclear materials involved in reprocessing, and for their timely measurement within the process, within the reprocessing facility, and at the facility boundaries are being studied. Because these requirements are becoming more numerous and stringent, attention is also being paid to the analytical requirements for these special nuclear materials and to methods for measuring the physical parameters of the systems containing them. In order to provide a focus for the consideration of the workshop participants, the Hot Experimental Facility (HEF) being designed …

Experimental data and theoretical calculations are presented for the mass-transfer rate to rotating disks and rotating rings when laminar, transition, and fully developed turbulent flow exist upon different portions of the surface. Good agreement of data and the model is obtained for rotating disks and relatively thick rotating rings. Results of the calculations for thin rings generally exceed the experimental data measured in transition and turbulent flow. A y{sup +{sup 3}} form for the eddy diffusivity is used to fit the data. No improvement is noticed with a form involving both y{sup +{sup 3}} and y{sup +{sup 3}}.

The current status of ion beam excitation and ionization by high energy electrons and photons is discussed. Recent advances in multiply-charged ion source development are mentioned, and plans for electron-ion and synchrotron-ion crossed beam experiments at Brookhaven National Laboratory are described.

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In order to probe the metal ion coordination site in the human iron transport protein, transferrin, the complexation of a series of metal ions by the chelate analogue ethylene-bis(o-hydroxyphenylglycine) (EHPG) has been studied by difference uv spectroscopy, in which {Delta}{epsilon} values per coordinated phenol have been determined for the metal complex versus the protonated form of the ligand. With the exception of the.Cu {sup 2+} complex, maxima are observed at 242 nm and 290 nm with a minimum at 269 nm. The {Delta}{epsilon} values at 242 fall into two groups. Complexes of divalent metal ions (Zn{sup 2+}, Cu{sup 2+}, Cd{sup 2+}) have 6£ values ranging from 5000 to 6600 M{sup -1} cm{sup -1} whereas larger {Delta}{epsilon} values are observed for complexes of tri- and tetra- valent metal ions (Th{sup 4+}, Ga{sup 3+}, Fe{sup 3+}, • Ho{sup 3+}, Eu{sup 3+}, Er{sup 3+}, Tb{sup 2+}, VO{sup 2+}), 7400 - 8700 M{sup -1} cm{sup -1}. It is known that the transferrin binding sites contain tyrosyl residues, but there has been considerable debate concerning the precise number of tyrosine groups which bind to specific metal ions. Since it has been the common practice to assume the {Delta}{epsilon} values for coordination by all metal ions …