The research completed and in progress for the first period of this grant is reviewed. Specific scattering scenarios for TFTR and JET and ITER were studied. The Lodestar scattering code, SKATR, was upgraded to include anisotropic energetic ion distributions and an analytic diffraction formulation was completed. Research continues on JET studies and upgrading the code for JET and ITER relevant conditions.

The research completed and in progress for the first period of this grant is reviewed. Specific scattering scenarios for TFTR and JET and ITER were studied. The Lodestar scattering code, SKATR, was upgraded to include anisotropic energetic ion distributions and an analytic diffraction formulation was completed. Research continues on JET studies and upgrading the code for JET and ITER relevant conditions.

There is a great need for a rapid and simple means of determining the moisture content in combustible cartridge case (ccc) munitions. Previous studies have demonstrated that accumulation of moisture in ccc rounds, such as the M829, leads to softening of the case wall and weakening of the adhesive joint. Moisture in the ccc can lead to incomplete combustion of the case upon firing the round. Currently, there are no facile methods for measuring the moisture content. A prototype portable meter for non-destructive and rapid estimation of moisture in ccc has been developed. The Munitions Case Moisture Meter Model ORNL-1 demonstrates the feasibility of developing an instrument based on the moisture dependence of dielectric properties, to measure moisture in ccc munitions in storage and in the field. These instruments are simple, inexpensive, lightweight, portable, low-power battery operated, and intrinsically safe. They provide nondestructive, noninvasive, and rapid measurements. Calibration data for the prototype are not available at this time. Therefore, calibration of the meter and the development of a scale reading directly moisture content in munitions rounds could not be completed. These data will be supplied by the US Army from its tests of the meter with actual munitions. However, experimental …

There is a great need for a rapid and simple means of determining the moisture content in combustible cartridge case (ccc) munitions. Previous studies have demonstrated that accumulation of moisture in ccc rounds, such as the M829, leads to softening of the case wall and weakening of the adhesive joint. Moisture in the ccc can lead to incomplete combustion of the case upon firing the round. Currently, there are no facile methods for measuring the moisture content. A prototype portable meter for non-destructive and rapid estimation of moisture in ccc has been developed. The Munitions Case Moisture Meter Model ORNL-1 demonstrates the feasibility of developing an instrument based on the moisture dependence of dielectric properties, to measure moisture in ccc munitions in storage and in the field. These instruments are simple, inexpensive, lightweight, portable, low-power battery operated, and intrinsically safe. They provide nondestructive, noninvasive, and rapid measurements. Calibration data for the prototype are not available at this time. Therefore, calibration of the meter and the development of a scale reading directly moisture content in munitions rounds could not be completed. These data will be supplied by the US Army from its tests of the meter with actual munitions. However, experimental …

The operational performance of a six-pack'' of cermet anodes and corrosion rates was evaluated in a six kA pilot reduction cell at Reynolds' Manufacturing Technology Laboratory. Two separate test periodswere conducted with the cermet anodes; the first period was in conjunction with the Pacific Northwest Laboratory and the second with ELTECH Research Corporation. Both tests used identical NiO-NiFe[sub 2]O[sub 4]-Cu anodes manufactured by Ceramic Magnetics, Inc.. The ELTECH testing involved the in situ coating of the anodes with cerium oxide. Primary evaluations for both test periods were conducted at target conditions of alumina saturation and 0.5 amp/cm[sup 2] anode current density. Individual anodes remained in operation for 25 days during the two and one-half month testing period. Operational difficulties developed throughout the test due to breakage of the anode conductor stems, cracking and breaking of the cermet anodes, unequal anode current distribution, and alumina muck build-up in the cell. These operational problems are discussed as well as an estimate of anode corrosion rates based on metal impurity levels in the aluminum metal pad.

The operational performance of a ``six-pack`` of cermet anodes and corrosion rates was evaluated in a six kA pilot reduction cell at Reynolds` Manufacturing Technology Laboratory. Two separate test periodswere conducted with the cermet anodes; the first period was in conjunction with the Pacific Northwest Laboratory and the second with ELTECH Research Corporation. Both tests used identical NiO-NiFe{sub 2}O{sub 4}-Cu anodes manufactured by Ceramic Magnetics, Inc.. The ELTECH testing involved the in situ coating of the anodes with cerium oxide. Primary evaluations for both test periods were conducted at target conditions of alumina saturation and 0.5 amp/cm{sup 2} anode current density. Individual anodes remained in operation for 25 days during the two and one-half month testing period. Operational difficulties developed throughout the test due to breakage of the anode conductor stems, cracking and breaking of the cermet anodes, unequal anode current distribution, and alumina muck build-up in the cell. These operational problems are discussed as well as an estimate of anode corrosion rates based on metal impurity levels in the aluminum metal pad.

The FLOWTRAN-TF code development effort was initiated in early 1989 as a code to monitor production reactor cooling systems at the Savannah River Plant. This report is a documentation of the various codes that make up FLOWTRAN-TF.

The FLOWTRAN-TF code development effort was initiated in early 1989 as a code to monitor production reactor cooling systems at the Savannah River Plant. This report is a documentation of the various codes that make up FLOWTRAN-TF.

FLOWTRAN-TF was created to analyze an individual Mk22 fuel assembly during a large break Loss Of Coolant Accident (LOCA) scenario involving the Savannah River Site K-reactor after the initial few seconds of the transient. During the initial few seconds reactor cooling is limited by the static or Ledinegg flow instability phenomenon. The predecessor FLOWTRAN code was developed to analyze this portion of a LOCA. In the several seconds following the break, a significant fraction of the reactor coolant inventory leaks out the break, Emergency Cooling System (ECS) flow is initiated, and air enters the primary coolant circulation loops. Reactor fuel assemblies are cooled by a low flowrate air-water downflow. Existing commercial nuclear industry thermal-hydraulic codes were judged inadequate for detailed modeling of a Mk22 fuel assembly because the application involves a ribbed annular geometry, low pressure, downflow and an air-water mixture. FLOWTRAN-TF is a two-phase thermal-hydraulics code of similar technology to existing commercial codes such as RELAP and TRAC but customized for Savannah River Site applications. The main features and capabilities of FLOWTRAN-TF are detailed Mk22 fuel assembly ribbed annular geometry; conjugate heat transfer; detailed neutronic power distribution; three-dimensional heat conduction in Mk22 fuel and target tubes; two-dimensional coolant flow …

FLOWTRAN-TF was created to analyze an individual Mk22 fuel assembly during a large break Loss Of Coolant Accident (LOCA) scenario involving the Savannah River Site K-reactor after the initial few seconds of the transient. During the initial few seconds reactor cooling is limited by the static or Ledinegg flow instability phenomenon. The predecessor FLOWTRAN code was developed to analyze this portion of a LOCA. In the several seconds following the break, a significant fraction of the reactor coolant inventory leaks out the break, Emergency Cooling System (ECS) flow is initiated, and air enters the primary coolant circulation loops. Reactor fuel assemblies are cooled by a low flowrate air-water downflow. Existing commercial nuclear industry thermal-hydraulic codes were judged inadequate for detailed modeling of a Mk22 fuel assembly because the application involves a ribbed annular geometry, low pressure, downflow and an air-water mixture. FLOWTRAN-TF is a two-phase thermal-hydraulics code of similar technology to existing commercial codes such as RELAP and TRAC but customized for Savannah River Site applications. The main features and capabilities of FLOWTRAN-TF are detailed Mk22 fuel assembly ribbed annular geometry; conjugate heat transfer; detailed neutronic power distribution; three-dimensional heat conduction in Mk22 fuel and target tubes; two-dimensional coolant flow …

Objective was to determine the single-particle electronic structure of selected narrow band materials in order to understand the relation between their electronic structures and novel low energy properties, such as mixed valence, heavy Fermions, Kondo effect, insulator-metal transitions, non-Fermi liquid behavior, and high-temperature superconductivity. This program supports photoemission spectroscopy (PES) at various synchrotrons. The progress is reported under the following section titles: ZSA (Zaanen-Sawatzky-Allen) systematics and I-M transitions in 3d transition metal oxides, insulator-metal transitions in superconducting cuprates, Fermi liquid and non-Fermi liquid behavior in angular resolved PES lineshapes, heavy-Fermion and non-Fermi liquid 5f electron systems, and Kondo insulators.

Evaluating perception-based impacts of hazardous waste facilities has become an increasingly important part of socioeconomic impact assessments in recent years. One area of discussion has been the potential effect of risk perceptions on business location decision making. This report evaluates the importance of environmental amenities (broadly defined to include natural, cultural, and recreational features; environmental quality; and other indexes of quality of life) with respect to decisions on locating both manufacturing and business service activities. It discusses the major theoretical and empirical issues that arise in attempting to determine the effects of environmental amenities on the location choices for businesses and business activities. This discussion is followed by a survey of major findings from the academic literature and a review of research by the state of Nevada. A number of recommendations for further research are also provided to help the US Department of Energy`s Office of Civilian Radioactive Waste Management better understand the importance of perception-based impacts in business location decision making and estimate the scale of socioeconomic impacts that would result from siting a high-level waste repository in Nevada.

This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of …

The objectives of this project are to develop a new catalyst, the kinetics for this catalyst, reactor models for trickle bed, slurry and fixed bed reactors, and simulate the performance of fixed bed trickle flow reactors, slurry flow reactors, and fixed bed gas phase reactors for conversion of a hydrogen lean synthesis gas to isobutylene. The goals for the quarter include: (1) Conduct experiments using a trickle bed reactor to determine the effect of reactor type on the product distribution. (2) Use spherical pellets of silica as a support for zirconia for the purpose of increasing surface, area and performance of the catalysts. (3) Conduct exploratory experiments to determine the effect of super critical drying of the catalyst on the catalyst surface area and performance. (4) Prepare a ceria/zirconia catalyst by the precipitation method.

This work strives to develop high average power FELs at voltages below I MV allowing for smaller and less costly power supplies. To achieve operation of an FEL with 100 GHZ [approx lt] f [approx lt] 150 GHz and with relatively modest voltage, we have been investigating the use of small period ([lambda][sub [omega]] [approximately] 1 cm) planar wiggler magnets together with sheet electron beams. The sheet beam geometry allows for an FEL interaction region in the form of a narrow slit with high wiggler field at the center plane where the electrons are concentrated. The total current and power may then be increased without making current density excessive by increasing the wide dimension of the sheet beam. Sheet beam FEL design parameters for both a Proof-of-Principle (PoP) FEL experiment, which is current in progress, and an ITER relevant FEL design are shown. A central issue in the sheet beam FEL concept is propagation of the beam through the interaction region without excessive interception by the walls. In section 2 below we describe a successful experimental demonstration of sheet beam propagation through a 56 period uniform wiggler. Cold testing and initial hot test operation of the (PoP) FEL amplifier are …

This work strives to develop high average power FELs at voltages below I MV allowing for smaller and less costly power supplies. To achieve operation of an FEL with 100 GHZ {approx_lt} f {approx_lt} 150 GHz and with relatively modest voltage, we have been investigating the use of small period ({lambda}{sub {omega}} {approximately} 1 cm) planar wiggler magnets together with sheet electron beams. The sheet beam geometry allows for an FEL interaction region in the form of a narrow slit with high wiggler field at the center plane where the electrons are concentrated. The total current and power may then be increased without making current density excessive by increasing the wide dimension of the sheet beam. Sheet beam FEL design parameters for both a Proof-of-Principle (PoP) FEL experiment, which is current in progress, and an ITER relevant FEL design are shown. A central issue in the sheet beam FEL concept is propagation of the beam through the interaction region without excessive interception by the walls. In section 2 below we describe a successful experimental demonstration of sheet beam propagation through a 56 period uniform wiggler. Cold testing and initial hot test operation of the (PoP) FEL amplifier are also described. …

This project is a continuing multidisciplinary study of middle to Upper Cretaceous marine carbonate and clastic rocks in the Utah-Colorado-Kansas corridor of the old Cretaceous seaway that extended from the Gulf Coast to the Arctic during maximum Cretaceous transgressions. It is collaborative between in the US Geological Survey (W.E. Dean, P.I.) and University researchers led by The Pennsylvania State University(M.A. Arthur, P.I.) and funded by DOE and the USGS, in part. Research focusses on the Greenhom, Niobrara and lower Pierre Shale units and their equivalents, combining biostratigraphic/paleoecologic studies, inorganic, organic and stable isotopic geochemical studies, mineralogical investigations and high-resolution geophysical logging. This research requires unweathered samples and continuous smooth ``exposures`` in the form of cores from at least 4 relatively shallow reference holes (i.e. < 1000m) in transect from east to west across the basin. The major initial effort was recovery in Year 1 of the project of continuous cores from each site in the transect. This drilling provided samples and logs of strata ranging from pelagic sequences that contain organic-carbon-rich marine source rocks to nearshore coal-bearing units. This transect also will provide information on the extent of thermal maturation and migration of hydrocarbons in organic-carbon-rich strata along a burial …

This project is a continuing multidisciplinary study of middle to Upper Cretaceous marine carbonate and clastic rocks in the Utah-Colorado-Kansas corridor of the old Cretaceous seaway that extended from the Gulf Coast to the Arctic during maximum Cretaceous transgressions. It is collaborative between in the US Geological Survey (W.E. Dean, P.I.) and University researchers led by The Pennsylvania State University(M.A. Arthur, P.I.) and funded by DOE and the USGS, in part. Research focusses on the Greenhom, Niobrara and lower Pierre Shale units and their equivalents, combining biostratigraphic/paleoecologic studies, inorganic, organic and stable isotopic geochemical studies, mineralogical investigations and high-resolution geophysical logging. This research requires unweathered samples and continuous smooth exposures'' in the form of cores from at least 4 relatively shallow reference holes (i.e. < 1000m) in transect from east to west across the basin. The major initial effort was recovery in Year 1 of the project of continuous cores from each site in the transect. This drilling provided samples and logs of strata ranging from pelagic sequences that contain organic-carbon-rich marine source rocks to nearshore coal-bearing units. This transect also will provide information on the extent of thermal maturation and migration of hydrocarbons in organic-carbon-rich strata along a burial …

Power emission by fusion products of tokamak plasmas in their ion cyclotron range of frequencies (ICRF) and at their spin-flip resonance frequency is calculated for some specific model fusion product velocity-space distribution functions. The background plasma of say deuterium (D) is assumed to be in equilibrium with a Maxwellian distribution both for the electrons and ions. The fusion product velocity distributions analyzed here are: (1) A monoenergetic velocity space ring distribution. (2) A monoenergetic velocity space spherical shell distribution. (3) An anisotropic Maxwellian distribution with T [perpendicular] [ne] T[parallel]and with appreciable drift velocity along the confining magnetic field. Single dressed'' test particle spontaneous emission calculations are presented first and the radiation temperature for ion cyclotron emission (ICE) is analyzed both for black-body emission and nonequilibrium conditions. Thresholds for instability and overstability conditions are then examined and quasilinear and nonlinear theories of the electromagnetic ion cyclotron modes are discussed. Distinctions between kinetic or causal instabilities'' and hydrodynamic instabilities'' are drawn and some numerical estimates are presented for typical tokamak parameters. Semiquantitative remarks are offered on wave accessibility, mode conversion, and parametric decay instabilities as possible for spatially localized ICE. Calculations are carried out both for k[parallel] = 0 for k[parallel] [ne] …

Power emission by fusion products of tokamak plasmas in their ion cyclotron range of frequencies (ICRF) and at their spin-flip resonance frequency is calculated for some specific model fusion product velocity-space distribution functions. The background plasma of say deuterium (D) is assumed to be in equilibrium with a Maxwellian distribution both for the electrons and ions. The fusion product velocity distributions analyzed here are: (1) A monoenergetic velocity space ring distribution. (2) A monoenergetic velocity space spherical shell distribution. (3) An anisotropic Maxwellian distribution with T {perpendicular} {ne} T{parallel}and with appreciable drift velocity along the confining magnetic field. Single ``dressed`` test particle spontaneous emission calculations are presented first and the radiation temperature for ion cyclotron emission (ICE) is analyzed both for black-body emission and nonequilibrium conditions. Thresholds for instability and overstability conditions are then examined and quasilinear and nonlinear theories of the electromagnetic ion cyclotron modes are discussed. Distinctions between ``kinetic or causal instabilities`` and ``hydrodynamic instabilities`` are drawn and some numerical estimates are presented for typical tokamak parameters. Semiquantitative remarks are offered on wave accessibility, mode conversion, and parametric decay instabilities as possible for spatially localized ICE. Calculations are carried out both for k{parallel} = 0 for k{parallel} {ne} …

High gradient magnetic separation (HGMS) is a physical separation process that is used to extract magnetic particles from mixtures. The technology is used on a large scale in the kaolin clay industry to whiten or brighten kaolin clay and increase its value. Because all uranium and plutonium compounds are slightly magnetic, HGMS can be used to separate these contaminants from non-magnetic soils. A Cooperative Research and Development Agreement (CRADA) was signed in 1992 between Los Alamos National Laboratory (LANL) and Lockheed Environmental Systems and Technologies Company (LESAT) to develop HGMS for soil decontamination. This paper reports progress and describes the HGMS technology.

Investigations of various aspects of heavy-ion collisions were carried out in the framework of the Boltzmann-Langevin Model (BLM). In a previous work, by projection the BLM onto a collective space, a memory-dependent collective transport model was reduced. This model was applied to thermal fission to investigate the influence of the memory effects on the fission dynamics. Some results of the calculations are presented. In addition a reduction of the relativistic BLM to a two-fluid model was carried out, and transport coefficients associated with fluid dynamical variables was carried out. Then this model was applied to investigate equilabration and fluctuation properties in a counter-streaming nuclear fluid.

Investigations of various aspects of heavy-ion collisions were carried out in the framework of the Boltzmann-Langevin Model (BLM). In a previous work, by projection the BLM onto a collective space, a memory-dependent collective transport model was reduced. This model was applied to thermal fission to investigate the influence of the memory effects on the fission dynamics. Some results of the calculations are presented. In addition a reduction of the relativistic BLM to a two-fluid model was carried out, and transport coefficients associated with fluid dynamical variables was carried out. Then this model was applied to investigate equilabration and fluctuation properties in a counter-streaming nuclear fluid.

Commonwealth Edison has submitted a request to NRC to replace the snubbers in the Reactor Coolant Bypass Line of Byron Station -Unit 2 with gapped pipe supports. The specific supports intended for use are commercial units designated ''Seismic Stops'' manufactured by Robert L. Cloud Associates, Inc. (RLCA). These devices have the physical appearance of snubbers and are essentially spring supports incorporating clearance gaps sized for the Byron Station application. Although the devices have a nonlinear stiffness characteristic, their design adequacy is demonstrated through the use of a proprietary linear elastic piping analysis code ''GAPPIPE'' developed by RLCA. The code essentially has all the capabilities of a conventional piping analysis code while including an equivalent linearization technique to process the nonlinear spring elements. Brookhaven National Laboratory (BNL) has assisted the NRC staff in its evaluation of the RLCA implementation of the equivalent linearization technique and the GAPPIPE code. Towards this end, BNL performed a detailed review of the theoretical basis for the method, an independent evaluation of the Byron piping using the nonlinear time history capability of the ANSYS computer code and by result comparisons to the RLCA developed results, an assessment of the adequacy of the response estimates developed with …