As an aid to planning future usage of X terminals, the authors measured the network bandwidth used by X terminals on a single Ethernet in a typical application environment at Fermilab. The objectives were twofold. The first objective was to identify the impact of adding one more X terminal onto the CDF Ethernet . The second objective was to determine the maximum number of X terminals allowable on the CDF network. The findings reveal that an X terminal in this environment used, on average, 431 + /{minus}45 bytes/second. This is quite small compared to the utilizable bandwidth of the thinwire Ethernet network (375 Kilobytes/second, equivalent to 30% of total bandwidth). This amounts to an averaged load of .034% on the network per X terminal. This paper addresses the network load solely. It does not address the loads imposed by X terminals on the memory and CPU of the host systems.

As an aid to planning future usage of X terminals, the authors measured the network bandwidth used by X terminals on a single Ethernet in a typical application environment at Fermilab. The objectives were twofold. The first objective was to identify the impact of adding one more X terminal onto the CDF Ethernet . The second objective was to determine the maximum number of X terminals allowable on the CDF network. The findings reveal that an X terminal in this environment used, on average, 431 + /{minus}45 bytes/second. This is quite small compared to the utilizable bandwidth of the thinwire Ethernet network (375 Kilobytes/second, equivalent to 30% of total bandwidth). This amounts to an averaged load of .034% on the network per X terminal. This paper addresses the network load solely. It does not address the loads imposed by X terminals on the memory and CPU of the host systems.

The NEPTUN data discussed in this report are from core uncovery (boil-off) experiments designed to investigate the mixture level decrease and the heat up of the fuel rod simulators above the mixture level for conditions simulating core boil-off for a nuclear reactor under small break loss-of-coolant accident conditions. The first series of experiments performed in the NEPTUN test facility consisted of ten boil-off (uncovery) and one adiabatic heat-up tests. In these tests three parameters were varied: rod power, system pressure and initial coolant subcooling. The NEPTUN experiments showed that the external surface thermocouples do not cause a significant cooling influence in the rods to which they are attached under boil-off conditions. The reflooding tests performed later on indicated that the external surface thermocouples have some effect during reflooding for NEPTUN electrically heated rod bundle. Peak cladding temperatures are reduced by about 30--40C and quench times occur 20--70 seconds earlier than rods with embedded thermocouples. Additionally, the external surface-thermocouples give readings up to 20 K lower than those obtained with internal surface thermocouples (in the absence of external thermocouples) in the peak cladding temperature zone. Some of the boil-off data obtained from the NEPTUN test facility are used for the assessment …

This Grant has marked the beginning of a multi-year study process expected to lead to design and construction of at least one, possibly several hospital-based proton therapy facilities in the United States.

This Grant has marked the beginning of a multi-year study process expected to lead to design and construction of at least one, possibly several hospital-based proton therapy facilities in the United States.

The goal of the investigation presented in this report is to study the inter-relationship between electrical conductivity, oxidation-reduction kinetics, defect structure, and composition of n- and p-type binary and ternary transition metal oxides. The experimental part of the investigation included specimen preparation, thermogravimetric measurements, X-ray diffraction, thermally stimulated current, DTA/TGA, optical absorption, transmission electron microscopy, electrical conductivity, and Seebeck measurements. The systems studied or being studied are LaMnO{sub 3}-LaCrO{sub 3}-LaCrO{sub 3}, (La,Ca)(Mn,Al)O{sub 3}, Y{sub 1-x}Ca{sub x}CrO{sub 3}, YMnO{sub 3}-CaMnO{sub 3}, and LaMnO{sub 3}-CaMnO{sub 3}.

The goal of the investigation presented in this report is to study the inter-relationship between electrical conductivity, oxidation-reduction kinetics, defect structure, and composition of n- and p-type binary and ternary transition metal oxides. The experimental part of the investigation included specimen preparation, thermogravimetric measurements, X-ray diffraction, thermally stimulated current, DTA/TGA, optical absorption, transmission electron microscopy, electrical conductivity, and Seebeck measurements. The systems studied or being studied are LaMnO{sub 3}-LaCrO{sub 3}-LaCrO{sub 3}, (La,Ca)(Mn,Al)O{sub 3}, Y{sub 1-x}Ca{sub x}CrO{sub 3}, YMnO{sub 3}-CaMnO{sub 3}, and LaMnO{sub 3}-CaMnO{sub 3}.

Temperatures were monitored at various locations on DT-18 and PC-1 shipping packages during furnace tests at the Y-12 Plant in Oak Ridge, Tennessee. The furnace tests are intended to simulate hypothetical thermal accident conditions specified in Title 10 CFR, Pt. 71.73 (c)(3). Maximum temperatures of the outer containers ranged from 750 to 965{degrees}C while typical maximum temperatures recorded on the inner containers were 60 to 77{degrees}C. One exceptionally high temperature of 196{degrees}C occurred on the PC-1 inner container. Heating 7.1 models of both the DT-18 and PC-1 packages were developed. Models with and without heat generation in the inner containers were developed for each shipping package. The models with heat generation are intended to simulate condensation and convection of hot vapors generated during the heating of the Celotex{trademark} insulating material used in the packages. In general, the analytical models calculate temperatures for the outer containers which agree well with the test data. The HEATING models with and without heat generation bound the inner container test data. These findings are significant in that they lead to the conclusion that heat is transferred to the inner containers through a mechanism other than conduction alone. The high temperature of 196{degrees}C recorded at the …

Celotex {trademark}, the insulating material used between the outer and inner containers of the DT-18 shipping package, undergoes decomposition, combustion, or both when heated to temperatures exceeding 150{degrees}C. Several DT-18 packages that had previously undergone hypothetical thermal accident testing were opened and Celotex {trademark} charring depths ranging from {1/2} to 1 {1/2} in. were recorded. The majority of char depth data taken was between 3/4 and 1 {1/4} in. One-dimensional HEATING 7.1 models of the DT-18 package were developed. HEATING predicts charring depths of 1 to 1 1/8 in., which are in good agreement with measured values. Both experimental and analytical data indicate that charring is fairly uniform over the DT-18 package. 7 refs.

Temperatures were monitored at various locations on DT-18 and PC-1 shipping packages during furnace tests at the Y-12 Plant in Oak Ridge, Tennessee. The furnace tests are intended to simulate hypothetical thermal accident conditions specified in Title 10 CFR, Pt. 71.73 (c)(3). Maximum temperatures of the outer containers ranged from 750 to 965{degrees}C while typical maximum temperatures recorded on the inner containers were 60 to 77{degrees}C. One exceptionally high temperature of 196{degrees}C occurred on the PC-1 inner container. Heating 7.1 models of both the DT-18 and PC-1 packages were developed. Models with and without heat generation in the inner containers were developed for each shipping package. The models with heat generation are intended to simulate condensation and convection of hot vapors generated during the heating of the Celotex{trademark} insulating material used in the packages. In general, the analytical models calculate temperatures for the outer containers which agree well with the test data. The HEATING models with and without heat generation bound the inner container test data. These findings are significant in that they lead to the conclusion that heat is transferred to the inner containers through a mechanism other than conduction alone. The high temperature of 196{degrees}C recorded at the …

Celotex {trademark}, the insulating material used between the outer and inner containers of the DT-18 shipping package, undergoes decomposition, combustion, or both when heated to temperatures exceeding 150{degrees}C. Several DT-18 packages that had previously undergone hypothetical thermal accident testing were opened and Celotex {trademark} charring depths ranging from {1/2} to 1 {1/2} in. were recorded. The majority of char depth data taken was between 3/4 and 1 {1/4} in. One-dimensional HEATING 7.1 models of the DT-18 package were developed. HEATING predicts charring depths of 1 to 1 1/8 in., which are in good agreement with measured values. Both experimental and analytical data indicate that charring is fairly uniform over the DT-18 package. 7 refs.

Annual report of the Argonne National Laboratory Chemical Technology Division (CMT) discussing the group's activities during 1991. These included electrochemical technology; fossil fuel research; hazardous waste research; nuclear waste programs; separation science and technology; integral fast reactor pyrochemical processes; actinite recovery; applied physical chemistry; basic chemistry research; analytical chemistry; research and development; and computer applications.

This report recommends resident fish substitution projects to partially replace anadromous fish losses caused by construction of Grand Coulee and Chief Joseph Dams. These recommendations involve enhancing the resident fishery in the Pend Oreille River as a substitute for anadromous fish losses. In developing these recommendations we have intentionally attempted to minimize the impact upon the hydroelectric system and anadromous fish recovery plans. In this report we are recommending that the Northwest Power Planning Council direct Bonneville Power Administration to fund the proposed enhancement measures as resident fish substitution projects under the NPPC's Columbia Basin Fish and Wildlife Program. The Pend Oreille River, located in northeast Washington, was historically a free flowing river which supported anadromous steelhead trout and chinook salmon, and large resident cutthroat trout and bull trout. In 1939, Grand Coulee Dam eliminated the anadromous species from the river. In 1955, Box Canyon Dam was constructed, inundating resident trout habitat in the river and creating many back water and slough areas. By the late 1950's the fishery in the reservoir had changed from a quality trout fishery to a warm water fishery, supporting largemouth bass, yellow perch and rough fish (tenth, suckers, squawfish). The object of this study …

Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U[sup 235]. While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document.

We have investigated common mechanisms responsible for fracture connectivity (or lack thereof) for single and multiple sets of fractures. The methods of study were based on detailed field mapping of fractures in layered sedimentary rocks, typical of producing oil and gas reservoirs and on numerical modeling of the concepts developed from the field observations. The crucial mechanisms important for connectivity have been deduced to be fracture propagation across layer interfaces with or without shearing in slightly deformed terrains in the Appalachians Plateau, central New York, and in highly deformed terrains in the Valley and Ridge province of the Appalachians in northeastern Tennessee, northwestern North Carolina and southwestern Maryland. Both of these mechanisms have been simulated by using numerical models which include fracture propagation across interfaces between dissimilar layers, and interactions between parallel faults of various scales. Fluid transport through a single fracture or a fracture network in rock depends strongly on the nature of connections between fracture segments and between the individual fractures. This study has shown that layer interfaces, particularly those with thin shale layers impede fluid flow along fractures in vertical direction, whereas additional fractures between low angle faults along the interfaces enhance it.

We have investigated common mechanisms responsible for fracture connectivity (or lack thereof) for single and multiple sets of fractures. The methods of study were based on detailed field mapping of fractures in layered sedimentary rocks, typical of producing oil and gas reservoirs and on numerical modeling of the concepts developed from the field observations. The crucial mechanisms important for connectivity have been deduced to be fracture propagation across layer interfaces with or without shearing in slightly deformed terrains in the Appalachians Plateau, central New York, and in highly deformed terrains in the Valley and Ridge province of the Appalachians in northeastern Tennessee, northwestern North Carolina and southwestern Maryland. Both of these mechanisms have been simulated by using numerical models which include fracture propagation across interfaces between dissimilar layers, and interactions between parallel faults of various scales. Fluid transport through a single fracture or a fracture network in rock depends strongly on the nature of connections between fracture segments and between the individual fractures. This study has shown that layer interfaces, particularly those with thin shale layers impede fluid flow along fractures in vertical direction, whereas additional fractures between low angle faults along the interfaces enhance it.

The structure and energetics of free radicals, ions, and clusters have been investigated by photoelectron photoion coincidence (PEPICO) and analyzed with ab initio molecular orbital and statistical theory RRKM calculations. In these experiments, molecules are prepared in a molecular beam so that their internal as well as translational energies are cooled to near O K. The coincidence condition between energy analyzed electrons and their corresponding ions insures that the ions are energy selected. The primary experimental information includes ionization and fragment ion appearance energies, and the ion time of flight (TOF) distributions. The latter are obtained by using the energy selected electron as a start signal and the ion as the stop signal. These types of experiments allow us to measure the ion dissociation rates in the 10{sup 4} to 10{sup 7} sec {sup {minus}1} range. Such ions are commonly referred to a metastable ions. In addition, the TOF peak widths are related to the release of translational energy in the ion dissociation process. Perhaps the most important advance during the past year has been in the study of cluster photoionization. We have developed an experimental method for differentiating similar mass cluster ions based on the kinetic energy of the …

The structure and energetics of free radicals, ions, and clusters have been investigated by photoelectron photoion coincidence (PEPICO) and analyzed with ab initio molecular orbital and statistical theory RRKM calculations. In these experiments, molecules are prepared in a molecular beam so that their internal as well as translational energies are cooled to near O K. The coincidence condition between energy analyzed electrons and their corresponding ions insures that the ions are energy selected. The primary experimental information includes ionization and fragment ion appearance energies, and the ion time of flight (TOF) distributions. The latter are obtained by using the energy selected electron as a start signal and the ion as the stop signal. These types of experiments allow us to measure the ion dissociation rates in the 10{sup 4} to 10{sup 7} sec {sup {minus}1} range. Such ions are commonly referred to a metastable ions. In addition, the TOF peak widths are related to the release of translational energy in the ion dissociation process. Perhaps the most important advance during the past year has been in the study of cluster photoionization. We have developed an experimental method for differentiating similar mass cluster ions based on the kinetic energy of the …

A large nuclear detonation at altitudes of several hundred kilometers above the earth distorts the earth's magnetic field and produces a strong magnetohydrodynamic electromagnetic pulse (MHD-EMP). This can adversely affect electrical power systems. In this report, the effects of this nuclear environment on critical facilities connected to the commercial power system are considered. Methods of mitigating the MHD-EMP impacts are investigated, and recommended protection schemes are presented. Guidelines for testing facilities to determine the effects of MHD-EMP and to validate the mitigation methods also are discussed.

A large nuclear detonation at altitudes of several hundred kilometers above the earth distorts the earth`s magnetic field and produces a strong magnetohydrodynamic electromagnetic pulse (MHD-EMP). This can adversely affect electrical power systems. In this report, the effects of this nuclear environment on critical facilities connected to the commercial power system are considered. Methods of mitigating the MHD-EMP impacts are investigated, and recommended protection schemes are presented. Guidelines for testing facilities to determine the effects of MHD-EMP and to validate the mitigation methods also are discussed.

The US Geological Survey and the Idaho Department of Water Resources, in response to a request from the US Department of Energy, sampled 19 sites as part of a long-term project to monitor water quality of the Snake River Plain aquifer from the southern boundary of the Idaho National Engineering Laboratory to the Hagerman area. Water samples were collected and analyzed for manmade pollutants and naturally occurring constituents. The samples were collected from seven irrigation wells, five domestic wells, two springs, one stock well, two dairy wells, one observation well, and one commercial well. Two quality assurance samples also were collected and analyzed. The water samples were analyzed for selected radionuclides, inorganic constituents, organic compounds, and bacteria. None of the radionuclides, inorganic constituents, or organic compounds exceeded the established maximum contaminant levels for drinking water. Most of the radionuclide and inorganic constituent concentrations exceeded their respective reporting levels. All samples analyzed for surfactants and dissolved organic carbon had concentrations that exceeded their reporting level. Toluene concentrations exceeded the reporting level in one water sample. Two samples contained fecal coliform bacteria counts that exceeded established maximum contaminant levels for drinking water.

This report provides a description and initial evaluation of five selected thermal treatment (furnace) technologies, in support of earlier thermal technologies scoping work for application to the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC) buried wastes. The cyclone furnace, molten salt processor, microwave melter, ausmelt (fuel fired lance) furnace, and molten metal processor technologies are evaluated. A system description and brief development history are provided. The state of development of each technology is assessed, relative to treatment of RWMC buried waste.

This report provides a description and initial evaluation of five selected thermal treatment (furnace) technologies, in support of earlier thermal technologies scoping work for application to the Idaho National Engineering Laboratory Radioactive Waste Management Complex (RWMC) buried wastes. The cyclone furnace, molten salt processor, microwave melter, ausmelt (fuel fired lance) furnace, and molten metal processor technologies are evaluated. A system description and brief development history are provided. The state of development of each technology is assessed, relative to treatment of RWMC buried waste.

This report provides an overview of progress during FY 1991 for the Technical Support Program that is part of the ANL Technology Support Activity for DOE, Environmental Restoration and Waste Management (EM). The purpose is to evaluate, before hot start-up of the Defenses Waste Processing Facility (DWPF) and the West Valley Demonstration Project (WVDP), factors that are likely to affect glass reaction in an unsaturated environment typical of what may be expected for the candidate Yucca Mountain repository site. Specific goals for the testing program include the following: (1) to review and evaluate available information on parameters that will be important in establishing the long-term performance of glass in a repository environment; (2) to perform testing to further quantify the effects of important variables where there are deficiencies in the available data; and (3) to initiate long-term testing that will bound glass performance under a range of conditions applicable to repository disposal.