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Design of a Precast Concrete Stay-in-Place Forming System for Lock Wall Rehabilitation
Report describing the design of forming a system to use pre-cast concrete for rehabilitating damaged walls in locks, as a way to prevent problems with cracking in replacement air-entrained concrete used in standard methods.
Date:
July 1987
Creator:
ABAM Engineers Incorporated
System:
The UNT Digital Library
Sequence dependent structure and thermodynamics of DNA oligonucleotides and polynucleotides: uv melting and NMR (nuclear magnetic resonance) studies
Thermodynamic parameters for double strand formation have been measured for the twenty-five DNA double helices made by mixing deoxyoligonucleotides of the sequence dCA/sub 3/XA/sub 3/G with the complement dCT/sub 3/YT/sub 3/G. Each of the bases A, C, G, T, and I (I = hypoxanthine) have been substituted at the positions labeled X and Y. The results are analyzed in terms of nearest neighbors. At higher temperatures the sequences containing a G)centerreverse arrowdot)C base pair become more stable than those containing only A)centerreverse arrowdot)T. All molecules containing mismatcher are destabilized with respect to those with only Watson-Crick pairing, but there is a wide range of destabilization. Large neighboring base effects upon stability were observed. For example, when (X, Y) = (I, A), the duplex is eightfold more stable than when (X, Y) = (A, I). Independent of sequence effects the order of stabilities is: I)centerreverse arrowdot)C )succ) I)centerreverse arrowdot) A)succ) I)centerreverse arrowdot)T approx. I)centerreverse arrowdot)G. All of these results are discussed within the context of models for sequence dependent DNA secondary structure, replication fidelity and mechanisms of mismatch repair, and implications for probe design. The duplex deoxyoligonucleotide d(GGATGGGAG))centerreverse arrowdot)d(CTCCCATCC) is a portion of the gene recognition sequence of the protein transcription …
Date:
December 1, 1987
Creator:
Aboul-ela, F. M.
System:
The UNT Digital Library
Sodium Waste Technology : a Summary Report
The Sodium Waste Technology (SWT) Program was established to resolve long-standing issues regarding disposal of sodium-bearing waste and equipment. Comprehensive SWT research programs investigated a variety of approaches for either removing sodium from sodium-bearing items, or disposal of items containing sodium residuals. The most successful of these programs was the design, test, and the production operation of the Sodium Process Demonstration Facility at ANL-W. The technology used was a series of melt-drain-evaporate operations to remove nonradioactive sodium from sodium-bearing items and then converting the sodium to storable compounds.
Date:
January 1987
Creator:
Abrams, C. S. & Witbeck, L. C.
System:
The UNT Digital Library
Sodium waste technology: A summary report. [Melt-drain-evaporation-calcination (MEDEC)]
The Sodium Waste Technology (SWT) Program was established to resolve long-standing issues regarding disposal of sodium-bearing waste and equipment. Comprehensive SWT research programs investigated a variety of approaches for either removing sodium from sodium-bearing items, or disposal of items containing sodium residuals. The most successful of these programs was the design, test, and the production operation of the Sodium Process Demonstration Facility at ANL-W. The technology used was a series of melt-drain-evaporate operations to remove nonradioactive sodium from sodium-bearing items and then converting the sodium to storable compounds.
Date:
January 1, 1987
Creator:
Abrams, C. S. & Witbeck, L. C.
System:
The UNT Digital Library
The development of a selective ruthenium catalyst
A micelle technique was developed for preparing supported catalysts with different size ruthenium particles. Ruthenium was stabilized on the support, light ends make was minimized and activity was maximized by adjusting the ruthenium particle size and the metal-support interaction. The most promising catalysts consisted of 10--15 nm ruthenium particles on an alumina-titania support and 4--6 nm ruthenium particles on an alumina support. Stability improvement was determined to be the major catalyst developmental need. Work during the next quarter will focus on the development of a stable ruthenium catalyst.
Date:
January 1, 1987
Creator:
Abrevaya, H.
System:
The UNT Digital Library
The development of a selective ruthenium catalyst. Technical progress report, October 1, 1987--December 31, 1987
A micelle technique was developed for preparing supported catalysts with different size ruthenium particles. Ruthenium was stabilized on the support, light ends make was minimized and activity was maximized by adjusting the ruthenium particle size and the metal-support interaction. The most promising catalysts consisted of 10--15 nm ruthenium particles on an alumina-titania support and 4--6 nm ruthenium particles on an alumina support. Stability improvement was determined to be the major catalyst developmental need. Work during the next quarter will focus on the development of a stable ruthenium catalyst.
Date:
December 31, 1987
Creator:
Abrevaya, H.
System:
The UNT Digital Library
Marker Development
This report is to discuss the marker development for radioactive waste disposal sites. The markers must be designed to last 10,000 years, and place no undue burdens on the future generations. Barriers cannot be constructed that preclude human intrusion. Design specifications for surface markers will be discussed, also marker pictograms will also be covered.
Date:
May 1, 1987
Creator:
Adams, M. R.
System:
The UNT Digital Library
Report to users of ATLAS (Argonne Tandem-Line Accelerator System)
The operation and development of ATLAS are reported, including accelerator improvements. Particularly noted is an upgrade to extend the mass range of projectiles up to uranium and to increase the beam intensity by at least two orders of magnitude for all ions. Meetings are discussed, particularly of the Program Advisory Committee and the User Group Executive Committee. Some basic information is provided for users planning to run experiments at ATLAS, including a table of beams available. The data acquisition system for ATLAS, DAPHNE, is discussed, as are the following experimental facilities: the Argonne-Notre Dame Gamma Ray Facility, a proposal submitted for constructing a large-acceptance Fragment Mass Analyzer. Brief summaries are provided of some recent experiments for which data analysis is complete. Experiments performed during the period from June 1, 1986 to January 31, 1987 are tabulated, providing the experiment number, scientists, institution, experiment name, number of days, beam, and energy. (LEW)
Date:
March 1, 1987
Creator:
Ahmad, I. & Glagola, B. (eds.)
System:
The UNT Digital Library
Plan for glass waste form testing for NNWSI [Nevada Nuclear Waste Storage Investigations]
The purpose of glass waste form testing is to determine the rate of release of radionuclides from breached glass waste containers. This information will be used to qualify glass waste forms with respect to the release requirements. It will be the basis of the source term from glass waste for repository performance assessment modeling. This information will also serve as part of the source term in the calculation of cumulative releases after 100,000 years in the site evaluation process. It will also serve as part of the source term input for calculation of cumulative releases to the accessible environment for 10,000 years after disposal, to determine compliance with EPA regulations. This investigation will provide data to resolve information needs. Information about the waste forms which is provided by the producer will be accumulated and evaluated; the waste form will be tested, properties determined, and mechanisms of degradation determined; and models providing long-term evaluation of release rates designed and tested. 23 refs.
Date:
September 1, 1987
Creator:
Aines, R. D.
System:
The UNT Digital Library
CSDP: The seismology of continental thermal regimes: Final report for period April 1, 1986-April 1, 1987
This report describes progress in the study of both wave propagation in complex structures and source mechanism of geothermal seismic events. The following work was accomplished in the past one-year period: (1) interpretation of long-period events observed at Mt. St. Helens and at the Fenton Hill hot-dry-rock experimental site in terms of seismic radiation from a fluid-filled crack; (2) interpretation of teleseismic data collected in and near the Valles caldera in terms of a model with irregular topography, caldera fill, and magma chamber; (3) interpretation of VSP (Vertical Seismic Profiling) data from the Oroville fault zone by ray tracing and polarization calculation for P, SV, and SH waves in heterogeneous and anisotropic media containing aligned fluid-filled and/or dry cracks; and (4) development of a new powerful method for calculating seismic motions in media with irregular topography and interfaces by the superposition of Gaussian Beams.
Date:
July 1, 1987
Creator:
Aki, K.
System:
The UNT Digital Library
Fluidized-Bed Retorting of Colorado Oil Shale: Topical Report.
In support of the research program in converting oil shale into useful forms of energy, the US Department of Energy is developing systems models of oil shale processing plants. These models will be used to project the most attractive combination of process alternatives and identify future direction for R and D efforts. With the objective of providing technical and economic input for such systems models, Foster Wheeler was contracted to develop conceptual designs and cost estimates for commercial scale processing plants to produce syncrude from oil shales via various routes. This topical report summarizes the conceptual design of an integrated oil shale processing plant based on fluidized bed retorting of Colorado oil shale. The plant has a nominal capacity of 50,000 barrels per operating day of syncrude product, derived from oil shale feed having a Fischer Assay of 30 gallons per ton. The scope of the plant encompasses a grassroots facility which receives run of the mine oil shale, delivers product oil to storage, and disposes of the processed spent shale. In addition to oil shale feed, the battery limits input includes raw water, electric power, and natural gas to support plant operations. Design of the individual processing units was …
Date:
June 1987
Creator:
Albulescu, P. & Mazzella, G.
System:
The UNT Digital Library
San Ignacio (La Tembladera) geothermal site, Departamento de Francisco Morazan, Honduras, Central America: Geological field report
The San Ignacio (La Tembladera) geothermal site is located on the north side of the Siria Valley, Departamento de Francisco Morazan, near the village of Barrosa. Hot springs are located along a northwest-trending fault scarp at the edge of the valley and along north-trending faults that cross the scarp. The rocks in the area are primarily Paleozoic metamorphic rocks, overlain by patches of Tertiary Padre Miguel Group tuffs and alluvial deposits. Movement probably occurred along several faults during latest Tertiary and possibly early Quaternary times. Four spring areas were mapped. Area 1, the largest, is associated with a sinter mound and consists of 40 spring groups. About half of the springs, aligned along a north-south trend, are boiling. Area 2 is a small sinter mound with several seeps. Area 3 consists of a group of hot and boiling springs aligned along a north-trending fault. The springs rise through fractured schists and a thin cover of alluvium. Area 4 is located at the intersection of several faults and includes one of the largest boiling springs in the area.
Date:
June 1, 1987
Creator:
Aldrich, M.J.; Eppler, D.; Heiken, G.; Flores, W.; Ramos, N. & Ritchie, A.
System:
The UNT Digital Library
Assessment of foreign decommissioning technology with potential application to US decommissioning needs
This study was conducted by the Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) to identify and technically assess foreign decommissioning technology developments that may represent significant improvements over decommissioning technology currently available or under development in the United States. Technology need areas for nuclear power reactor decommissioning operations were identified and prioritized using the results of past light water reactor (LWR) decommissioning studies to quantitatively evaluate the potential for reducing cost and decommissioning worker radiation dose for each major decommissioning activity. Based on these identified needs, current foreign decommissioning technologies of potential interest to the US were identified through personal contacts and the collection and review of an extensive body of decommissioning literature. These technologies were then assessed qualitatively to evaluate their uniqueness, potential for a significant reduction in decommissioning costs and/or worker radiation dose, development status, and other factors affecting their value and applicability to US needs.
Date:
September 1, 1987
Creator:
Allen, R.P.; Konzek, G.J.; Schneider, K.J. & Smith, R.I.
System:
The UNT Digital Library
SVI: Super-VIOR interface routines
This document describes a set of routines for a VME DMA module called the Super-VIOR. The Super-VIOR interface routines, also called the SVI routines, are written in PILS and run under a Valet-plus system. These routines enable a program to set up, execute, and monitor DMA operations. The Super-VIOR Interface Routines are written in PILS, a high level language similar to BASIC and Pascal which is powerful and fast enough for most applications. One of the most powerful features of the Valet/PILS system is the ability to set up exception vectors and exception handlers directly in a program. This feature is used to handle interrupts from the MC68450 (a 4 channel, 16 bit DMA controller) and the interface's front panel. This document is divided into ten sections, the first being the introduction. The remaining sections detail the interface registers, channel initiation, polling and interrupts, status reporting, front panel interrupts, the configuration routines, the operation control routines, the status reporting routines, and special comments on the MC68450.
Date:
October 21, 1987
Creator:
Alleva, D.
System:
The UNT Digital Library
VFI: VME/FASTBUS Interface routines
This documents describes the VME/FASTBUS Interface routines (VFI). These routines where designed to enable programs written in PILS running on a MVME 101 under Valet-plus to control a VME/FASTBUS Interface. The routines fall into two general types, control and transaction. The control routines, such as vmec-reset, work directly with the interface's registers. These routines set up and monitor operations between VME and FASTBUS. The transaction routines, such as vfi-write-dat, use the control routines to carry out complete functions on FASTBUS. Most FASTBUS operations are implemented except for the compound routines and some low level routines. This document is divided into seven sections, the first is the introduction. The remaining sections detail the interface's registers, the structure of operation codes, polling and interrupts, status reporting, the control routines, and the transaction routines.
Date:
September 10, 1987
Creator:
Alleva, D.
System:
The UNT Digital Library
VTI: VME/CIPRICO Interface routines
This document details the VME/CIPRICO Interface routines (VII). These routines where designed to allow programs written in PILS running on a MVME 101 under Valet-plus to control a CIPRICO tape controller. The routines fall into two general types. The low level routines, such as vti-make-pb, create the data structures used by the CIPRICO as well as manipulate the CIPRICO's control registers. The high level routines, such as vti-rewind, use the lower level routines to carry out complete functions on tape drives. Most tape operations are implemented except for ring buffer record routines. The creation of ring buffer record lists linked to parameter blocks is possible, but no high level routines are implemented to work with these lists. Memory utilization, parameter block creation and linking, polling and interrupts, status reporting, and the VTI routines are discussed. 2 refs.
Date:
September 4, 1987
Creator:
Alleva, D.
System:
The UNT Digital Library
Progress at LAMPF (Los Alamos Meson Physics Facility): Progress report, January-December 1986
Activities at LAMPF during the year of 1986 are summarized, including brief summaries of experiments in nuclear and particle physics, atomic and molecular physics, materials science, radiation-effects studies, biomedical research and instrumentation, nuclear chemistry, radioisotope production, and theory. The status of an advanced hadron facility currently under study is reported, as well as facility development and accelerator operations. (LEW)
Date:
May 1, 1987
Creator:
Allred, J.C. & Talley, B. (eds.)
System:
The UNT Digital Library
Determination of laser-evaporated uranium dioxide by neutron activation analysis
Safety analyses of nuclear reactors require information about the loss of fuel which may occur at high temperatures. In this study, the surface of a uranium dioxide target was heated rapidly by a laser. The uranium surface was vaporized into a vacuum. The uranium bearing species condensed on a graphite disk placed in the pathway of the expanding uranium vapor. Scanning electron microscopy and X-ray analysis showed very little droplet ejection directly from the laser target surface. Neutron activation analysis was used to measure the amount of uranium deposited. The surface temperature was measured by a fast-response automatic optical pyrometer. The maximum surface temperature ranged from 2400 to 3700/sup 0/K. The Hertz-Langmuir formula, in conjunction with the measured surface temperature transient, was used to calculate the theoretical amount of uranium deposited. There was good agreement between theory and experiment above the melting point of 3120/sup 0/K. Below the melting point much more uranium was collected than was expected theoretically. This was attributed to oxidation of the surface. 29 refs., 16 figs., 7 tabs.
Date:
May 1, 1987
Creator:
Allred, R.
System:
The UNT Digital Library
History of Proton Linear Accelerators
None
Date:
January 1, 1987
Creator:
Alvarez, Luis W.
System:
The UNT Digital Library
Characteristics of soils and saprolite in Solid Waste Storage Area 6
Solid Waste Storage Area 6 (SWSA-6) is one of the disposal sites for solid low-level radioactive waste at Oak Ridge National Laboratory. Soils and saprolites from the site were characterized to provide base line information to initiate assessment for remedial actions and closure plans. Physical, chemical, mineralogical, and engineering analyses were conducted on soil and saprolite samples.
Date:
September 30, 1987
Creator:
Ammons, J. T.; Phillips, D. H.; Timpson, M. E. & Lee, S. Y.
System:
The UNT Digital Library
Characteristics of soils and saprolite in Solid Waste Storage Area 6
Solid Waste Storage Area 6 (SWSA-6) is one of the disposal sites for solid low-level radioactive waste at Oak Ridge National Laboratory. Soils and saprolites from the site were characterized to provide base line information to initiate assessment for remedial actions and closure plans. Physical, chemical, mineralogical, and engineering analyses were conducted on soil and saprolite samples.
Date:
September 30, 1987
Creator:
Ammons, J. T.; Phillips, D. H.; Timpson, M. E. (Tennessee Univ., Knoxville, TN (United States). Dept. of Plant and Soil Science) & Lee, S. Y. (Oak Ridge National Lab., TN (United States))
System:
The UNT Digital Library
New apparatus for direct counting of. beta. particles from two-dimensional gels and an application to changes in protein synthesis due to cell density
A new method is described for scanning two-dimensional gels by the direct counting of ..beta.. particles instead of autoradiography. The methodology is described; results are compared with autoradiographic results; and data are presented demonstrating changed patterns of protein synthesis accompanying changes in cell density. The method is rapid and permits identification of differences in protein abundance of approximately 10% for a substantial fraction of the more prominent proteins. A modulation effect of more than 5 standard deviations, accompanying contact inhibition of cell growth, is shown to occur for an appreciable number of these proteins. The method promises to be applicable to a variety of biochemical and genetic experiments designed to delineate changes in protein synthesis accompanying changes in genome, molecular environment, history, and state of differentiation of the cell populations studied. 13 refs., 8 figs., 4 tabs.
Date:
July 1, 1987
Creator:
Anderson, H.L.; Puck, T.T. & Shera, E.B.
System:
The UNT Digital Library
Core refueling subsystem design description. Revision 1
The Core Refueling Subsystem of the Fuel Handling and Storage System provides the mechanisms and tools necessary for the removal and replacement of the hexagonal elements which comprise the reactor core. The Core Refueling Subsystem is not "safety-related." The Core Refueling Subsystem equipment is used to prepare the plant for element removal and replacement, install the machines which handle the elements, maintain control of air inleakage and radiation release, transport the elements between the core and storage, and control the automatic and manual operations of the machines. Much of the element handling is performed inside the vessel, and the entire exchange of elements between storage and core is performed with the elements in a helium atmosphere. The core refueling operations are conducted with the reactor module shutdown and the primary coolant pressure slightly subatmospheric. The subsystem is capable of accomplishing the refueling in a reliable manner commensurate with the plant availability requirements.
Date:
July 1, 1987
Creator:
Anderson, J.K. & Harvey, E.C.
System:
The UNT Digital Library
Hanford Meteorological Station computer codes: Volume 2, The PROD computer code
At the end of each work shift (day, swing, and graveyard), the Hanford Meteorological Station (HMS), operated by Pacific Northwest Laboratory, issues a forecast of the 200-ft-level wind speed and direction and the weather for use at B Plant and PUREX. These forecasts are called production forecasts. The PROD computer code is used to archive these production forecasts and apply quality assurance checks to the forecasts. The code accesses an input file, which contains the previous forecast's date and shift number, and an output file, which contains the production forecasts for the current month. A data entry form consisting of 20 fields is included in the program. The fields must be filled in by the user. The information entered is appended to the current production monthly forecast file, which provides an archive for the production forecasts. This volume describes the implementation and operation of the PROD computer code at the HMS.
Date:
September 1, 1987
Creator:
Andrews, G. L. & Buck, J. W.
System:
The UNT Digital Library