The objectives of this effort are (a) to learn the mechanisms by which the Chemical and Electrochemical Coal Cleaning (CECC) process removes pyritic sulfur and ash from coal, (b) to learn more about the operating parameters of the process, (c) to collect engineering information for scale-up of the process, and (d) to test the CECC process on a bench-scale continuous operation.

Although moderate in size, the Booster construction project requires a comprehensive control system. There are three operational modes: as a high intensity proton injector for the AGS, as a heavy ion accelerator and injector supporting a wide range of ions and as a polarized proton storage injector. These requirements are met using a workstation based extension of the existing AGS control system. Since the Booster is joining a complex of existing accelerators, the new system will be capable of supporting multiuser operational scenarios. A short discussion of this system is discussed in this paper.

The main purpose of this training program element is to familiarize personnel involved in hazardous waste management with the goals of RCRA and how they are to be achieved. These goals include: to protect health and the environment; to conserve valuable material and energy resources; to prohibit future open dumping on the land; to assure that hazardous waste management practices are conducted in a manner which protects human health and the environment; to insure that hazardous waste is properly managed thereby reducing the need for corrective actions in the future; to establish a national policy to reduce or eliminate the generation of hazardous waste, wherever feasible. Another objective of this progam element is to present a brief overview of the RCRA regulations and how they are implemented/enforced by the Environmental Protection Agency (EPA) and each of the fifty states. This element also discusses where the RCRA regulations are published and how they are updated. In addition it details who is responsible for compliance with the regulations. Finally, this part of the training program provides an overview of the activities and materials that are regulated. 1 ref.

Kurita and Ueda (1986) presented an example of the long-range transport of pollutants which frequently occurs in summer in Japan light gradient wind conditions. High concentrations of photochemical oxidants were observed in late evenings in the mountainous region approximately 160 km northwest from the large industrial zone located along the Tokyo bay. Pollutants were apparently transported by the large-scale circulations produced by the combination of southwesterly valley winds induced by thermal lows located in the mountain ranges, and southerly sea-breeze circulations in the Pacific Ocean coastal region (Kurita et al., 1985). We wish to stimulate and evaluate the relative importance of these circulations by using a time dependent, three-dimensional mesoscale model, HOTMAC, High Order Turbulence Model for Atmospheric Circulations. 7 refs., 4 figs.

Two microcomputers, a SUN 3 workstation and an IBM/PC-AT with a 32 bit OPUS Clipper board, were used to run a three-dimensional atmospheric code which simulated well the nocturnal drainage winds observed in Rush Valley, approximately 60 km southwest of Salt Lake City, Utah. The performance of the microcomputers was evaluated against the results obtained with a CRAY X-MP. Either microcomputer tested here is powerful enough to conduct extensive research in atmospheric boundary layer modeling.

The United States Department of Energy contracts the Los Alamos National Laboratory to carry out a Nuclear Weapons Test Program in support of the national defense. The program is one of ongoing research to design, build, and test prototype nuclear devices. The goal is to determine what should ultimately be incorporated into the nation's nuclear defense stockpile. All nuclear tests are conducted underground at the Nevada Test Site (NTS). This paper describes the instrumentation and control techniques used by Los Alamos to carry out the tests. Specifically, the contrast between historical methods and new, computer-based technology are discussed. Previous techniques required large numbers of expensive, heavy hardwire cables extending from the surface to the diagnostics rack at the bottom of the vertical shaft. These cables, which provided singular control/monitor functions, have been replaced by a few optical fibers and power cables. This significant savings has been enabled through the adaptation of industrial process control technology using programmable computer control and distributed input/output. Finally, an ongoing process of developing and applying the most suitable instrumentation and control technology to the unique requirements of the Test Program is discussed. 2 refs.

The Waste Certification Facility (WCF) at the Savannah River Plant (SRP) assesses transuranic (TRU) waste in 55-gal drums by x-ray and neutron interrogation prior to shipment to the Waste Isolation Pilot Plant (WIPP) in New Mexico. The facility, equipment, and operation are described. Results of a Probabilistic Risk Assessment (PRA) show that the facility can be operated without undue risk to plant personnel, the public, and the environment. 4 figs.

Software has been developed for ''real-time'' analysis of neutron and gamma data from GRAND-1/fork measurements on spent-fuel assemblies. Three modules compose the software package. The modules are linked through a database system of files. The first module is part of a general data-base processing code. This module prepares input data files with inventory and correction-factor information for the second module. The second module, called OLAF, operates on a computer attached to the GRAND-1 electronics unit. In this second module, neutron and gamma data from spent-fuel assemblies are analyzed to verify consistency in the facility operator declarations for exposure (burnup) and cooling time. From the analysis, potential discrepancies in the measurement data are questioned while equipment is still installed at the facility and is available for additional measurements. During the measurements, data are written to an output file, called a results file, which can be processed by the third module of the software package. In the third module, printed reports summarizing the data and results are prepared, and neutron and gamma data are written to files that are processed by the Deming curve-fitting code. 7 refs., 7 figs., 2 tabs.

Over the past 18 months on the GTA project at Los Alamos, we have been developing tools for building control systems for accelerators. The first tool developed has already demonstrated greatly reduced requirements for conventional computer programming in applying control systems to an accelerator. Even in the early stages, this work has received considerable attention and the system is currently being investigated or used at several other institutes. Further tools are either in the conceptual design, design, or implementation phase. Over the same period, a group at CERN has been developing the ideas and design for a generic software kit for the application of a control system to accelerators. The CERN software kit also addresses the technical management and documentation aspects of control systems. The purpose of the AT Division effort and the CERN kit is to greatly simplify the implementation and lifetime maintenance of an accelerator control system. Experience has shown that accelerator control systems are also applicable to other experimental physics machines. The purpose of the workshop was to explore these ideas and developments as well as other relevant developments in the field, to verify the viability of the concepts, and to develop further the written specifications for …

The results of surveillance tests on the High-Flux Isotope Reactor (HFIR) pressure vessel at the Oak Ridge National Laboratory revealed that a greater than expected embrittlement had taken place after about 17.5 effective full-power years of operation and an operational assessment program was undertaken to fully evaluate the vessel condition and recommend conditions under which operation could be resumed. A research program was undertaken that included irradiating specimens in the Oak Ridge Research Reactor. Specimens of the A212 grade B vessel shell material were included, along with specimens from a nozzle qualification weld and a submerged-arc weld fabricated at ORNL to reproduce the vessel seam weld. The results of the surveillance program and the materials research program performed in support of the evaluation of the HFIR pressure vessel are presented and show the welds to be more radiation resistant than the A212B. Results of irradiated tensile and annealing experiments are described as well as a discussion of mechanisms which may be responsible for enhanced hardening at low damage rates. 20 refs., 22 figs., 5 tabs.

These Proceedings of the October 3-7, 1988, DOE Model Conference are a compilation of the papers that were presented in the technical or poster sessions at the conference. Papers and posters not submitted for publication are not included in the Proceedings. The Table of Contents lists the titles of papers as well as the names of the presenters. These individuals are not, in all cases, the primary authors of the papers published. The actual title pages, appearing later with the papers, show the primary author(s) and all co-authors. The papers in all three volumes of the Proceedings appear as they were originally submitted for publication and have not been edited or changed in any way. Topics included in Volume 1 are Environmental Data Management, Site characterization technology, Wastewater treatment, Waste management in foreign countries, Transuranic waste management, and Groundwater characterization and treatment.

Two laws governing activities in the marine environment are considered in this Reference Book. The Marine Protection, Research, and Sanctuaries Act (MPRSA, P.L. 92-532) regulates ocean dumping of waste, provides for a research program on ocean dumping, and provides for the designation and regulation of marine sanctuaries. The Marine Mammal Protection Act (MMPA, P.L. 92-522) establishes a federal program to protect and manage marine mammals. The Fishery Conservation and Management Act (FCMA, P.L. 94-265) establishes a program to regulate marine fisheries resources and commercial marine fishermen. Because the Department of Energy (DOE) is not engaged in any activities that could be classified as fishing under FCMA, this Act and its regulations have no implications for the DOE; therefore, no further consideration of this Act is given within this Reference Book. The requirements of the MPRSA and the MMPA are discussed in terms of their implications for the DOE.

Separate abstracts were prepared for 26 papers in these proceedings. (LEW)

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site; to describe the conceptual designs for the repository and the waste package and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. Chapter 3 summarizes present knowledge of the regional and site hydrologic systems. The purpose of the information presented is to (1) describe the hydrology based on available literature and preliminary site-exploration activities that have been or are being performed and (2) provide information to be used to develop the hydrologic aspects of the planned site characterization program. Chapter 4 contains geochemical information about the Yucca Mountain site. The …

The Yucca Mountain site in Nevada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended by the Secretary of Energy and approved by the President for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared by the US Department of Energy (DOE) in accordance with the requirements of the Nulcear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining the geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare an environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted …

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

The Yucca Mountain site in Neavada is one of three candidate sites for the first geologic repository for radioactive waste. On May 28, 1986, it was recommended and approved for detailed study in a program of site characterization. This site characterization plan (SCP) has been prepared in accordance with the requirements of the Nuclear Waste Policy Act to summarize the information collected to date about the geologic conditions at the site;to describe the conceptual designs for the repository and the waste package;and to present the plans for obtaining hte geologic information necessary to demonstrate the suitability of the site for a repository, to design the repository and the waste package, to prepare and environmental impact statement, and to obtain from the US Nuclear Regulatory Commission (NRC) an authorization to construct the repository. This introduction begins with a brief section on the process for siting and developing a repository, followed by a discussion of the pertinent legislation and regulations. A description of site characterization is presented next;it describes the facilities to be constructed for the site characterization program and explains the principal activities to be conducted during the program. Finally, the purpose, content, organizing principles, and organization of this site characterization …