The FRAC-UNIX computer code provides a two-dimensional simulation of saturated flow and transport in a fractured porous media. The code incorporates a dual permeability approach in which the rock matrix is modeled as rectangular cells and the fractures are represented as discrete elements on the edges and diagonals of the matrix cells. A single head distribution drives otherwise independent flows in the matrix and in the fractures. Steady-state or transient flow of a single-phase fluid may be simulated. Solute or heat transport is simulated by moving imaginary marker particles in the velocity field established by the flow model, under the additional influence of dispersive and diffusive processes. Sparse-matrix techniques are utilized along with a specially developed user interface. The code is installed a CRAY XMP24 Computer using the UNICOS operating system. The initial version of this code, entitled FRACSL, incorporated the same flow and transport models, but used a commercial software package for the numerics and user interface. This report describes the theoretical basis, approach and implementation incorporated in the code; the mechanics of operating the code; several sample problems; and the integration of code development with physical modeling and field testing. The code is fully functional, for most purposes, …

TOPAZ2D is a two dimensional implicit finite element computer code for heat transfer analysis. This user's manual provides information on the structure of a TOPAZ2D input file. Also included is a material thermal property data base. This manual is supplemented with The TOPAZ2D Theoretical Manual and the TOPAZ2D Verification Manual. TOPAZ2D has been implemented on the CRAY, SUN, and VAX computers. TOPAZ2D can be used to solve for the steady state or transient temperature field on two dimensional planar or axisymmetric geometries. Material properties may be temperature dependent and either isotropic or orthotropic. A variety of time and temperature dependent boundary conditions can be specified including temperature, flux, convection, and radiation. Time or temperature dependent internal heat generation can be defined locally be element or globally by material. TOPAZ2D can solve problems of diffuse and specular band radiation in an enclosure coupled with conduction in material surrounding the enclosure. Additional features include thermally controlled reactive chemical mixtures, thermal contact resistance across an interface, bulk fluid flow, phase change, and energy balances. Thermal stresses can be calculated using the solid mechanics code NIKE2D which reads the temperature state data calculated by TOPAZ2D. A three dimensional version of the code, TOPAZ3D is …

This paper specifies the usage of structural bolts in terms of their design, selection and application, in accordance with the American Institute of Steel Construction (AISC) Eighth Edition. Manual of Steel Construction.'' 1 tab.

Report describing the methodology used to sample and analyze sediment at Ocean City, Maryland as part of a beach nourishment project. During the project, sediment was moved from borrow sites to construct parts of the beach area; both the borrow sites and native beach were tested.

The lecture recital was given November 6, 1989. Five Preludes by Claude Debussy were preformed following a lecture on some important considerations of approaching the pedaling complexities in his solo piano works. In addition to the lecture recital, three other solo piano recitals were performed. The first solo recital consisted of works by Franz Schubert and Robert Schumann, and was performed on November 17, 1980. On March 1, 1982, the second solo recital was presented. This performance consisted of works by J. Brahms, W.A. Mozart, S. Prokofieff, and A. Schoenberg. The third solo recital was performed on November 21, 1988 and included the works of L. van Beethoven. A. Berg, F. Chopin, and C. Debussy. The four programs were recorded on tape and filed with the written version of the lecture as part of the dissertation.

This monthly report summarizes the technical progress and project status for the Hanford Environmental Dose Reconstruction (HEDR) Project being conducted at Pacific Northwest Laboratory (PNL) under the direction of a Technical Steering Panel (TSP). The TSP is composed of experts in numerous technical fields related to this project and represents the interests of the public. The US Department of Energy (DOE) funds the project. The objective of the Hanford Environmental Dose Reconstruction Project is to estimate the radiation doses that populations could have received from nuclear operations at Hanford since 1944. The project is divided into the following technical tasks. These tasks address each of the primary steps in the path from radioactive releases to dose estimates source terms, environmental transport, environmental monitoring data, demographics, agriculture, and food habits, and environmental pathways and dose estimates.

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This document contains information regarding the National Historic Preservation Act and related legislation. The act was designed to protect archaeological and historic resources.

The Vindicator ETW-250 taut wire system combines a physical taut wire barrier with an intrusion detection sensor network. The sensor wires deter and/or slow physical entry into protected areas. The sensors themselves generate an alarm if the sensor wires are pulled, spread, cut, or climbed on. This physical motion is converted into an electrical waveform that is analyzed by the processor. The processor then determines if this motion is within the pre-programmed parameters. If it is not, an alarm is generated through a relay back to the monitoring station. Small changes, such as those caused by temperature, are rejected. Installation and testing are described.

The Software Standards and Documentation Group of the Workshop on Physics and Detector Simulation for SSC Experiments has compiled a list of physics generators, detector simulations, and related programs. This is not meant to be an exhaustive compilation, nor is any judgment made about program quality; it is a starting point or a more complete bibliography. Where possible we have included an author and source for the code. References for most programs are in the final section.

Results of a technical and economic evaluation of application of the Pitt Mill to fine coal grinding are presented. The Pitt Mill is a vertically oriented, batch operated, intermediate energy density (0. 025 kW/lb media), stirred ball mill. The mill grinds coal from coarse sizes (typically 3/16 inch or 4 mesh topsize) to the 10 micron to 20 micron mean particle diameter size range in a single step using a shallow grinding bed containing inexpensive, readily available, course grinding media. Size reduction is efficient because of rapid product circulation through the grinding bed caused by action of a novel circulation screw mounted on the agitator shaft. When a dispersant is employed, the grinding can be carried out to 50% to 60% solids concentration. Use of coarse grinding media offers the possibility of enhanced mineral liberation because size reduction is achieved more by impact shattering than by attrition. The batch method offers the possibility of very close control over product particle size distribution without overproduction of fines. A two- phase program was carried out. In the first phase, Grinding Studies, tests were run to determine a suitable configuration of the Pitt Mill. Machine design parameters which were studied included screw configuration, …

In order to evaluate the effectiveness of Section 11, Division 1, ``Rules for Inservice Inspection of Nuclear Power Plant Components,`` of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended.

This Document contains findings identified during the Tiger Team Compliance Assessment of the Department of Energy's (DOE's) Pinellas Plant, Pinellas County, Florida. The assessment wa directed by the Department's Office of Environment, Safety, and Health (ES H) from January 15 to February 2, 1990. The Pinellas Tiger Team Compliance Assessment is comprehensive in scope. It covers the Environment Safety and Health, and Management areas and determines the plant's compliance with applicable Federal (including DOE), State, and local regulations and requirements.

Preprint database management as done at various centers -- the subject of this workshop -- is hard to separate from the overall activities of the particular center. We therefore present the wider context at the Fermilab Library into which preprint database management fits. The day-to-day activities of the Library aside, the dominant activity at present is that of the ongoing Fermilab Library Automation. A less dominant but relatively time-consuming activity is that of doing more online searches in commercial databases on behalf of laboratory staff and visitors. A related activity is that of exploring the benefits of end-user searching of similar sources as opposed to library staff searching of the same. The Library Automation Project, which began about two years ago, is about to go fully online.'' The rationale behind this project is described in the documents developed during the December 1988--February 1989 planning phase.

In order to evaluate the effectiveness of Section 11, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended.

NIM is a standard modular instrumentation system that is in wide use throughout the world. As the NIM system developed and accommodations were made to a dynamic instrumentation field and a rapidly advancing technology, additions, revisions and clarifications were made. These were incorporated into the standard in the form of addenda and errata. This standard is a revision of the NIM document, AEC Report TID-20893 (Rev. 4) dated July 1974. It includes all the addenda and errata items that were previously issued as well as numerous additional items to make the standard current with modern technology and manufacturing practice.

A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA&PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan`s objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations.

This paper presents the results of a joint Westinghouse Hanford Company (Westinghouse Hanford)-Pacific Northwest Laboratory (PNL) study that considered the feasibility of treating radioactive waste before disposal to reduce the inventory of long-lived radionuclides, making the waste more suitable for geologic disposal. The treatment considered here is one in which waste would be chemically separated so that long-lived radionuclides can be treated using specific processes appropriate for the nuclide. The technical feasibility of enhancing repository performance by this type of treatment is considered in this report. A joint Westinghouse Hanford-PNL study group developed a concept called the Clean Use of Reactor Energy (CURE), and evaluated the potential of current technology to reduce the long-lived radionuclide content in waste from the nuclear power industry. The CURE process consists of three components: chemical separation of elements that have significant quantities of long-lived radioisotopes in the waste, exposure in a neutron flux to transmute the radioisotopes to stable nuclides, and packaging of radionuclides that cannot be transmuted easily for storage or geologic disposal. 76 refs., 32 figs., 24 tabs.

A workstation-based event display program for the Fermilab Tagged Photon Spectrometer (TPS) is described. Fast displays are required to monitor detector elements, observe hit patterns and energy deposition, and to check track reconstruction. Design considerations, novel features, and performance are designed. 5 refs., 4 figs., 1 tab.

One major task of the Nuclear Standards Program funded by the Department of Energy (DOE)-Nuclear Energy (NE) Technology Support Programs is to promote and support the use of standards by providing line managers and standards coordinators with data that facilitates their ability to utilize standards requirements. To meet this task, the Performance Assurance Project Office (PAPO) administers a Performance Assurance Information Program. The task is carried out in accordance with the principle set forth in DOE Order 1300.2, Department of Energy Standards Program,'' December 18, 1980, and DOE memorandum, Implementation of DOE Orders on Quality Assurance, Standards, and Unusual Occurrence Reporting for Nuclear Energy Programs,'' March 3, 1982, and with guidance from the DOE-NE Technology Support Programs. The purpose of this information program is to collect, compile, and distribute program-related information, reports, and publications for the benefit of the DOE-NE program participants.

A certification plan for computer codes used in Safety Analyses and Probabilistic Risk Assessment (PRA) for the operation of the Savannah River Site (SRS) reactors has been prepared. An action matrix, checklists, and a time schedule have been included in the plan. These items identify what is required to achieve certification of the codes. A list of Safety Analysis and Probabilistic Risk Assessment (SA PRA) computer codes covered by the certification plan has been assembled. A description of each of the codes was provided in Reference 4. The action matrix for the configuration control plan identifies code specific requirements that need to be met to achieve the certification plan's objectives. The checklist covers the specific procedures that are required to support the configuration control effort and supplement the software life cycle procedures based on QAP 20-1 (Reference 7). A qualification checklist for users establishes the minimum prerequisites and training for achieving levels of proficiency in using configuration controlled codes for critical parameter calculations.

The whole-pin furnace system is a new in-cell experimental facility constructed to investigate how irradiated fuel pins may fail under potential reactor accident conditions. Extensive checkouts have demonstrated excellent performance in remote operation, temperature control, pin breach detection, and fission gas handling. The system is currently being used in testing of EBIR-II-irradiated Integral Fast Reactor (IFR) metal fuel pins; future testing will include EBR-II-irradiated mixed-oxide fuel pins. 7 refs., 4 figs.

SXLS is an electron synchrotron/storage ring, used as an X-ray lithography source, with a critical wavelength of {lambda}=10 A. It has a circumference of 8.5 m and its main elements are two 180{degree} combined function dipole, four quadrupoles and two sextupoles. The horizontal and vertical tunes are 1.415 and 0.415, respectively. The machine is being constructed in two phases. In Phase 1 and 2 it will run at 200 and 696 Mev using conventional (warm) and superconducting bending magnets, respectively. All other elements, as well as the lattice functions will be the same in the two phases. The constraint that the exit slits impose on the photon beamlines, requires that the source point, that is the closed orbit be controlled to better then {plus minus}3 mm horizontally, {plus minus}2 mm and {plus minus}1 mrad vertically. The following is a study of the expected closed orbit distortion in the ring as well as of the orbit monitor/corrector schemes necessary to correct the orbit. 10 figs.

The technical feasibility of a patented, laser-welded, evacuated insulating window was studied. The window has two edge-sealed sheets of glass separated by 0.5-mm glass spheres spaced 30 mm apart in a regular array. A highly insulating frame is required and several designs were analyzed. The vacuum window's combination of high solar transmittance and low thermal conductance makes it superior to many other windows in cold climates. In the US Pacific Northwest, the vacuum window could save about 6 MJ of heating energy annually per square meter of window in comparison to conventional, double-glazed windows. A large, vacuum laser-welding facility was designed and installed to conduct glass welding experiments and to fabricate full-sized vacuum windows. Experiments confirmed the feasibility of laser-sealing glass in vacuum but identified two difficulties. Under some circumstances, bubbles of dissolved gases form during welding and weaken the seal. Glass also vaporizes and contaminates the laser beam steering mirror. A novel moving metal foil mirror was developed to circumvent the contamination problem, but it has not yet been used to complete welding experiments and fabricate full-sized vacuum windows. 63 refs., 53 figs., 19 tabs.