The Holifield Heavy Ion Research Facility has been in routine operation since July 1982. Beams have been provided using both the tandem accelerator alone and a coupled mode in which the Oak Ridge Isochronous Cyclotron is used as an energy booster for tandem beams. The coupled mode has proved to be especially effective and has allowed us to provide a wide range of energetic beams for scheduled experiments. In this report we discuss our operational experience and recent development activities.

A stand-alone control and data acquisition system for pellet injectors has been designed and implemented to support pellet injector development at Oak Ridge Laboratory (ORNL) and to enable ORNL pellet injectors to be installed on various fusion experimental devices. The stand-alone system permits LOCAL operation of the injector from a nearby panel and REMOTE operation from the experiment control room. Major components of the system are (1) an Allen-Bradley PLC 2/30 programmable controller, (2) a VAX minicomputer, and (3) a CAMAC serial highway interface. The programmable logic controller (PLC) is used to perform all control functions of the injector. In LOCAL, the operator interface is provided by an intelligent panel system that has a keypad and pushbutton module programmed from the PLC. In REMOTE, the operator interfaces via a VAX-based color graphics display and uses a trackball and keyboard to issue commands. Communications between the remote and local controls and to the fusion experiment supervisory system are via the CAMAC highway. The VAX archives transient data from pellet shots and trend data acquired from the PLC. Details of the hardware and software design and the operation of the system are presented in this paper. 3 refs., 1 fig.

This report contains the findings of a records search performed to survey the past and present use, storage, and disposal of hazardous materials and wastes at the Lawrence Livermore National Laboratory (LLNL) site. This report provides a point of departure for further planning of environmental protection activities at the site. This report was conducted using the LLNL archives and library, documents from the US Navy, old LLNL Plant Engineering blueprint files, published articles and reports, Environmental Protection Program records, employee interviews, and available aerial photographs. Sections I and II of this report provide an introduction to the LLNL site and its environmental characteristics. Several tenants have occupied the site prior to the establishment of LLNL, currently operated by the University of California for the US Department of Energy. Section III of this report contains information on environmentally related operations of early site users, the US Navy and California Research and Development. Section IV of this report contains information on the handling of hazardous materials and wastes by LLNL programs. The information is presented in 12 sub-sections, one for each currently operating LLNL program. General site areas, i.e., garbage trenches, the traffic circle landfill, the taxi strip, and old ammunition bunkers …

Aging hardware and software and increasing commitments by the Departments of Energy and Defense have led us to develop a new, expanded system to replace the existing Atmospheric Release Advisory Capability (ARAC) system. This distributed, computer-based, emergency response system is used by state and federal agencies to assess the environmental health hazards resulting from an accidental release of radioactive material into the atmosphere. Like its predecessor, the expanded system uses local meteorology (e.g., wind speed and wind direction), as well as terrain information, to simulate the transport and dispersion of the airborne material. The system also calculates deposition and dose and displays them graphically over base maps of the local geography for use by on-site authorities. This paper discusses the limitations of the existing ARAC system. It also discusses the components and functionality of the new system, the technical difficulties encountered and resolved in its design and implementation, and the software methodologies and tools employed in its development.

An x-ray densitometry of wood facility is being established by the Environmental Sciences Division, Oak Ridge Natioanl Laboratory (ORNL). The objective is to apply tree-ring data to determine whether or not there is a fertilizer effect on tree growth from increased atmospheric carbon dioxide since the beginning of the industrial era. Intra-ring width and density data, including ring-mass will be detemined from tree-ring samples collected from sites located throughout the United States and Canada. This report is designed as a guide to assist ORNL scientists in building the x-ray densitometry system. The history and development of x-ray densitometry in tree-ring research is examined and x-ray densitometry is compared with other techniques. Relative wood and tree characteristics are described as are environmental and genetic factors affecting tree growth responses. Methods in x-ray densitometry are examined in detail and the techniques used at four operating laboratories are described. Some ways that dendrochronology has been applied in dating, in wood quality, and environmental studies are presented, and a number of tree-ring studies in Canada are described. An annotated bibliography of radiation densitometry in tree-ring analysis and related subjects is included.

As a part of the siting methodology task for the DOE oil shale project the Los Alamos National Laboratory three-dimensional atmospheric models were used to assess potential environmental problems associated with future development of oil shale energy in Colorado. An area of 200 km x 200 km centered at Brush Creek, Colorado, where the ASCOT conducted extensive meteorological and tracer experiments in September/October 1984, was chosen as an initial simulation area. In this paper, preliminary simulations of the mean wind, turbulence, and nonreactive tracer transport are presented, where very little input data were available. Since data to compare with are not available, we discuss only qualitatively the model capability to produce: (1) complex airflow generated by differential heating and cooling over sloped surfaces; (2) strong diurnal variations in wind speed, wind direction, and atmospheric turbulence; and (3) enhanced daytime ventilation in a valley. The hydrodynamic model used to compute wind and turbulence is reviewed in Section 2 where a brief description of boundary and initial conditions, and numerical procedures are also included. Examples of the computed wind and turbulence distribution are given in Section 3. A random-particle statistical diffusion model is used to simulate tracer transport and diffusion where the …

We report experiments on selective photoionization of atoms containing isomeric nuclei of /sup 197/Hg. Other isomer separation techniques and their limitations are discussed.

May 1983 marked the beginning of an intensive effort to both improve the operating reliability, and improve the performance of the TMX-U Diagnostic Computer System. At that time, the system was handling (acquiring, storing, processing, plotting, displaying, and archiving) about 3 million bytes (Mb) of data per shot, with a 15-minute cycle time between shots. In addition, the system was fairly fragile, with frequent (about 5 times/day) crashes, requiring re-booting. At the present time, the system reliably handles about 5 Mb of data per shot, with a 7-minute cycle time between shots. This improvement was accomplished by a combination of new hardware, rearranging existing hardware, and new or revised software. Hardware changes were made in two areas. First, the shared disks were rearranged into different domains to make more efficient use of locking features. Second, we purchased and installed a solid-state RAM disk emulator (8 megabytes) to provide extremely fast access to lists and files that must be accessed frequently. In the software area, we made improvements in several areas. Initial effort went into finding bugs and optimizing existing code. We developed a template so that we could produce efficient code from applications that had first been developed on a …

The repeating pneumatic hydrogen pellet injector, which was developed at the Oak Ridge National Laboratory (ORNL), has been installed and operated on the Tokamak Fusion Test Reactor (TFTR). The injector combines high-speed extruder and pneumatic acceleration technologies to propel frozen hydrogen isotope pellets repetitively at high speeds. The pellets are transported to the plasma in an injection line that also serves to minimize the gas loading on the torus; the injection line incorporates a fast shutter valve and two stages of guide tubes with intermediate vacuum pumping stations. A remote, stand-alone control and data acquisition system is used for injector and vacuum system operation. In early pellet fueling experiments on TFTR, the injector has been used to deliver deuterium pellets at speeds ranging from 1.0 to 1.5 km/s into plasma discharges. First, single large (nominal 4-mm-dia) pellets provided high densities in TFTR (1.8 x 10/sup 14/ cm/sup -3/ on axis); after conversion to smaller (nominal 2.7-mm-dia) pellets, up to five pellets were injected at 0.25-s intervals into a plasma discharge, giving a line-averaged density of 1 x 10/sup 14/ cm/sup -3/. Operating characteristics and performance of the injector in initial tests on TFTR are presented.

Three pellet injector designs developed by the Oak Ridge National Laboratory (ORNL) are planned for the Tokamak Fusion Test Reactor (TFTR) to reach the goal of a tritium pellet injector by 1988. These are the Repeating Pneumatic Injector (RPI), the Deuterium Pellet Injector (DPI) and the Tritium Pellet Injector (TPI). Each of the pellet injector designs have similar performance characteristics in that they deliver up to 4-mm-dia pellets at velocities up to 1500 m/s with a dsign goal to 2000 m/s. Similar techniques are utilized to freeze and extrude the pellet material. The injector systems incorporate three gun concepts which differ in the number of gun barrels and the method of forming and chambering the pellets. The RPI, a single barrel repeating design, has been operational on TFTR since April 1985. Fabrication and assembly are essentially complete for DPI, and TPI is presently on hold after completing about 80% of the design. The TFTR pellet injector program is described, and each of the injector systems is described briefly. Design details are discussed in other papers at this symposium.

The performance of a pre-prototype of the SLD Warm Iron Calorimeter (WIC) build with proportional tube cathode pad readout has been studied. The calorimeter was found to have an average resolution of 36.7 +- 0.2% for muons at 2.0, 5.0 and 10.5 GeV and 81 +- 2%/..sqrt..E for pion showers at 5.0 and 10.5 GeV. The mean energy found for the pion showers was consistent with a linear dependence on energy within these standard deviations. 4 refs., 6 figs., 3 tabs.

Management options for three generic categories of radioactive mixed waste in commercial low-level wastes have been identified and evaluated. These wastes were characterized as part of a BNL study in which a large number of generators were surveyed for information on potentially hazardous low-level wastes. The general management targets adopted for mixed wastes are immobilization, destruction, and reclamation. It is possible that these targets may not be practical for some wastes, and for these, goals of stabilization or reduction of hazard are addressed. Solidification, absorption, incineration, acid digestion, segregation, and substitution have been considered for organic liquid wastes. Containment, segregation, and decontamination and re-use have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, containment, substitution, chemical reduction, and biological removal have been considered. For each of these wastes, the management option evaluation has necessarily included assessment/estimation of the effect of the treatment on both the radiological and potential chemical hazards present. 10 refs.

We describe a convenient interface between UNIX-based work-stations or minicomputers, and supercomputers such as the CRAY series machines. Using this interface, the user can issue commands entirely on the UNIX system, with remote compilation, loading and execution performed on the supercomputer. The interface is not a remote login interface. Rather the domain of various UNIX utilities such as compilers, archivers and loaders are extended to include the CRAY. The user need know essentially nothing about the CRAY operating system, commands or filename restrictions. Standard UNIX utilities will perform CRAY operations transparently. UNIX command names and arguments are mapped to corresponding CRAY equivalents, suitable options are selected as needed, UNIX directory tree filenames are coerced to allowable CRAY names and all source and output files are automatically transferred between the machines. The primary purpose of the software is to allow the programmer to benefit from the interactive features of UNIX systems including screen editors, software maintenance utilities such as make and SCCS and in general to avail of the large set of UNIX text manipulation features. The interface was designed particularly to support development of very large multi-file programs, possibly consisting of hundreds of files and hundreds of thousands of lines …

This paper is the first of a series which describes the Enrichment Diagnostic System (EDS) developed for the MARS project at Lawrence Livermore National Laboratory. Although EDS was developed for use on AVLIS, the functional requirements, overall design, and specific techniques are applicable to any experimental data acquisition system involving large quantities of transient data. In particular this paper will discuss the techniques and equipment used to do the data acquisition. Included are what types of hardware are used and how that hardware (CAMAC, digital oscilloscopes) is interfaced to the HP computers. In this discussion the author will address the problems encountered and the solutions used, as well as the performance of the instrument/computer interfaces. The second topic the author will discuss is how the acquired data is associated to graphics and analysis portions of EDS through efficient real time data bases. This discussion will include how the acquired data is folded into the overall structure of EDS providing the user immediate access to raw and analyzed data. By example you will see how easily a new diagnostic can be added to the EDS structure without modifying the other parts of the system. 8 figs.

The appropriate approach to risk or hazard assessment can vary considerably, depending on various factors, including the intended application of the results and the time other resources available to conduct the assessment. This paper illustrates three types of interrelated assessments. Although they can be mutually supportive, they have fundamentally different objectives, which require major differences in approach. The example of the overall risk assessment of alternative major energy technologies illustrates the compilation of a wide range of available risk data applicable to these systems. However, major uncertainties exist in the assessments, and public perception of their importance could play an important role in final system evaluations. A more narrowly defined risk assessment, often focusing on an individual component of a larger system, is the most commonly used approach in regulatory applications. The narrow scope allows in-depth analysis of risks and associated uncertainties, but it may also contribute to a loss of perspective on the magnitude of the assessed risk relative to that of the unassessed risks. In some applications, it is useful to conduct semiquantitative degree-of-hazard evaluations as a means of setting priorities for detailed risk assessment. The MAHAS procedure described in this paper provides a means of rapidly ranking …

The Project Surveillance and Maintenance Plan (PSMP) describes the procedures that will be used by the US Department of Energy (DOE), or other agency as designated by the President to verify that inactive uranium tailings disposal facilities remain in compliance with licensing requirements and US Environmental Protection Agency (EPA) standards for remedial actions. The PSMP will be used as a guide for the development of individual Site Surveillance and Maintenance Plans (part of a license application) for each of the UMTRA Project sites. The PSMP is not intended to provide minimum requirements but rather to provide guidance in the selection of surveillance measures. For example, the plan acknowledges that ground-water monitoring may or may not be required and provides the (guidance) to make this decision. The Site Surveillance and Maintenance Plans (SSMPs) will form the basis for the licensing of the long-term surveillance and maintenance of each UMTRA Project site by the NRC. Therefore, the PSMP is a key milestone in the licensing process of all UMTRA Project sites. The Project Licensing Plan (DOE, 1984a) describes the licensing process. 11 refs., 22 figs., 8 tabs.

The main vehicle for bringing the pion to bear on a vast array of problems, has been the meson factories. Today there exist such facilities in Switzerland (SIN), in Canada (TRIUMF), and in the USA (LAMPF). A fourth is just now being completed in the Soviet Union. They are enormous enterprises - the current replacement value of LMPF is $350 million, not including the part devoted to national security problems. But they accommodate hundreds of scientists from around the world and by so doing generate political as well as intellectual and economic capital. Proton facilities, together with heavy-ion accelerators and electron facilities, form a triad on which stands the present edifice of experimental nuclear science. Each leg of this triad is dependent, to a greater or lesser extent, on the other two. However, in terms of versatility, the size of the community it serves, and the relatively short-term application of the knowledge base and people base for which nuclear science is responsible, the meson factory part of the above triad is by no means the least important component. I discuss this component from the standpoint of the facility I know best, namely LAMPF. 33 refs., 36 figs.

An extensive survey was conducted of the geothermal resource potential of Hot Springs Bay Valley on Akutan Island. A topographic base map was constructed, geologic mapping, geophysical and geochemical surveys were conducted, and the thermal waters and fumarolic gases were analyzed for major and minor element species and stable isotope composition. (ACR)

Coal-derived materials from experimental runs of Hydrocarbon Research Incorporated's (HRI) catalytic two-stage liquefaction (CTSL) process were chemically characterized and screened for microbial mutagenicity. This process differs from two-stage coal liquefaction processes in that catalyst is used in both stages. Samples from both the first and second stages were class-fractionated by alumina adsorption chromatography. The fractions were analyzed by capillary column gas chromatography; gas chromatography/mass spectrometry; direct probe, low voltage mass spectrometry; and proton nuclear magnetic resonance spectrometry. Mutagenicity assays were performed with the crude and class fractions in Salmonella typhimurium, TA98. Preliminary results of chemical analyses indicate that >80% CTSL materials from both process stages were aliphatic hydrocarbon and polynuclear aromatic hydrocarbon (PAH) compounds. Furthermore, the gross and specific chemical composition of process materials from the first stage were very similar to those of the second stage. In general, the unfractionated materials were only slightly active in the TA98 mutagenicity assay. Like other coal liquefaction materials investigated in this laboratory, the nitrogen-containing polycyclic aromatic compound (N-PAC) class fractions were responsible for the bulk of the mutagenic activity of the crudes. Finally, it was shown that this activity correlated with the presence of amino-PAH. 20 figures, 9 tables.

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The EE Technical Review has two purposes - to inform readers of various activities within the Electronics Engineering Department and to promote the exchange of ideas. The articles, by design, are brief summaries of EE work. The articles included in this report are as follows: Overview - Nova Control System; Centralized Computer-Based Controls for the Nova Laser Facility; Nova Pulse-Power Control System; Nova Laser Alignment Control System; Nova Beam Diagnostic System; Nova Target-Diagnostics Control System; and Nova Shot Scheduler. The 7 papers are individually abstracted.

The overall objective of this project is to collect, organize, and summarize data concerning anadromous fish culture stations of the Columbia River system for 1981, 1982, and 1983 and to create a data archive system with a means of making this information available to the public.

The Division of Biological and Medical Research at Argonne National Laboratory conducts multidisciplinary research aimed at defining the biological and medical hazards to man from energy technologies and new energy options. These technically oriented studies have a strong base in fundamental research in a variety of scientific disciplines, including molecular and cellular biology, biophysics, genetics, radiobiology, pharmacology, biochemistry, chemistry, environmental toxicology, and epidemiology. This research summary is organized into six parts. The first five parts reflect the Divisional structure and contain the scientific program chapters, which summarize the activities of the individual groups during the calendar year 1984 and the first half of 1985. To provide better continuity and perspective, previous work is sometimes briefly described. Although the summaries are short, efforts have been made to indicate the range of research activities for each group.

Available 14-MeV experimental neutron activation cross sections are compiled and evaluated for the following reactions of interest for nuclear-energy technology applications: /sup 27/Al(n,p)/sup 27/Mg, Si(n,X)/sup 28/Al, Ti(n,X)/sup 46/Sc, Ti(n,X)/sup 47/Sc, Ti(n,X)/sup 48/Sc, /sup 51/V(n,p)/sup 51/Ti, /sup 51/V(n,..cap alpha..)/sup 48/Sc, Cr(n,X)/sup 52/V, /sup 55/Mn(n,..cap alpha..)/sup 52/V, /sup 55/Mn(n,2n)/sup 54/Mn, Fe(n,X)/sup 54/Mn, /sup 54/Fe(n,..cap alpha..)/sup 51/Cr, /sup 59/Co(n,p)/sup 59/Fe, /sup 59/Co(n,..cap alpha..)/sup 56/Mn, /sup 59/Co(n,2n)/sup 58/Co, /sup 65/Cu(n,p)/sup 65/Ni, Zn(n,X)/sup 64/Cu, /sup 64/Zn(n,2n)/sup 63/Zn, /sup 113/In(n,n')/sup 113m/In, /sup 115/In(n,n') /sup 115m/In. The compiled values are listed and plotted for reference without adjustments. From these collected results those values for which adequate supplementary information on nuclear constants, standards and experimental errors is provided are selected for use in reaction-by-reaction evaluations. These data are adjusted as needed to account for recent revisions in the nuclear constants and cross section standards. The adjusted results are subsequently transformed to equivalent cross sections at 14.7 MeV for the evaluation process. The evaluations are performed utilizing a least-squares method which considers correlations between the experimental data. 440 refs., 41 figs., 46 tabs.