Forty-four sediment samples were collected from 28 locations in the Hanford Reach of the Columbia River to assess the presence of metals and man-made radionuclides in the near shore and shoreline settings of the Hanford Site. Three locations were sampled upriver of the Hanford Site plutonium production reactors. Twenty-two locations were sampled near the reactors. Three locations were sampled downstream of the reactors near the Hanford Townsite. Sediment was collected from depths of 0 to 6 in. and between 12 to 24 in. below the surface. Samples containing concentrations of metals exceeding the 95 % upper threshold limit values (DOE-RL 1993b) are considered contaminated. Contamination by arsenic, chromium, copper, lead, and zinc was found. Man-made radionuclides occur in all samples except four collected opposite the Hanford Townsite. Man-made radionuclide concentrations were generally less than 1 pCi/g.

Soil washing laboratory tests performed at Hanford in support of 100 Area Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) feasibility studies included characterization of soils, physical separation, chemical extraction, and water treatment. Results to date show that < 20 % of the soil is finer than 0.25 mm ({minus}40 mesh). The highest concentration of {sup 60}Co, {sup 152}Eu, and {sup 137}Cs contaminants is generally associated with fine soil particles. However, measurable concentrations of contaminants were found in all sizes of soil particles. In initial testing, attrition scrubbing was generally sufficient to treat soils to meet selected performance levels for {sup 60}Co and {sup 152}Eu. However, more intense attrition scrubbing, autogenous grinding, or chemical extraction was required to enhance removal of {sup 137}Cs. Additional tests and assessment of the feasibility of using soil washing techniques are in progress.

This document reports the results of the field terrestrial ecological investigations conducted by Westinghouse Hanford Company during fiscal years 1991 and 1992 at operable units 100-FR-3, 100-HR-3, 100-NR-2, 100-KR-4, and 100-BC-5. The tasks reported here are part of the Remedial Investigations conducted in support of the Comprehensive Environmental Response, compensation, and Liability Act of 1980 studies for the 100 Areas. These ecological investigations provide (1) a description of the flora and fauna associated with the 100 Areas operable units, emphasizing potential pathways for contaminants and species that have been given special status under existing state and/or federal laws, and (2) an evaluation of existing concentrations of heavy metals and radionuclides in biota associated with the 100 Areas operable units.

This report contains short papers on research being conducted throughout the world on magnetically levitated systems, mainly consisting of trains, and magnetic linear drives. These papers have been index separately elsewhere on the data base.

This 1992 report contains monitoring data from routine radiological and nonradiological environmental surveillance activities. summaries of significant environmental compliance programs in progress, such as National Environmental Policy Act documentation, environmental permits, envirorunental restoration, and various waste management programs for Sandia National Laboratories in Albuquerque, New Mexico, are included. The maximum offsite dose impact was calculated to be 0.0034 millirem. The total population within a 50-mile radius of Sandia National Laboratories/New Mexico received an estimated collective dose of 0.019 person-rem during 1992 from the laboratories` operations. As in the previous year, the 1992 operations at Sandia National Laboratories/New Mexico had no discernible impact on the general public or on the environment.

Each year the National Low-Level Waste Management Program publishes a state-by-state assessment report. This report provides both national and state-specific disposal data on low-level radioactive waste commercially disposed in the United States. Data in this report are categorized according to disposal site, generator category, waste class, volumes, and radionuclide activity. Included in this report are tables showing the distribution of waste by state for 1992 and a comparison of waste volumes and radioactivity by state for 1988 through 1992; also included is a list of all commercial nuclear power reactors in the United States as of December 31, 1992. This report distinguishes between low-level radioactive waste shipped directly for disposal by generators and waste that was handled by an intermediary, a reporting change introduced in the 1988 state-by-state report.

This report describes the 1993 yearly calibration of a gross gamma-ray geophysical pulse logging system owned by the US Department of Energy (DOE) and operated by Pacific Northwest Laboratory. The calibration was conducted to permit the continued use of this system for geologic and hydrologic studies associated with remedial investigation at the Hanford Site. The calibration is limited to the probe identified as CG27A-97 and applies to a new probe detector crystal that replaced the former detector in January 1993, after a crack was discovered. Primary calibrations to equivalent-uranium units were conducted in DOE borehole model standards that reside on the Hanford Site. The calibrations were performed in borehole models SBL/SBH and SBA/SBB, which both contain sections with relatively low equivalent-uranium concentrations. Model SBH/SBL has now been countersunk at the site so that data were taken by suspending the probe downhole. Model SBA/SBB is still lying horizontally above ground at the site, so data were logged as in previous calibrations at the Hanford site by pushing the probe into the hole and drawing it out with the logging equipment. A previous correlation for relating observed count rate in before- and after-logging field calibrations to equivalent-uranium concentrations was confirmed for field …

This report provides a status of the expedited response action (ERA) projects currently being implemented at the Hanford Site. A detailed review of the accomplishments to date, the technologies employed, the problems encountered, and an analysis of the lessons learned are included. A total of nine ERAs have been initiated at the Hanford Site and are presented in a case study format with emphasis on the progress being made and the challenges ahead.

Researchers at Los Alamos have been developing transmutation concepts involving accelerator-driven nuclear systems. A medium energy, high current proton beam strikes a heavy metal target, producing a high flux of spallation neutrons. These neutrons are moderated to near-thermal energies in a blanket surrounding the target. Materials to be transmuted flow through the blanket region where they are fissioned or transmuted to stable nuclides. Stable or short-lived nuclides are separated while the long-lived radioactive species are returned to the blanket. For most applications the fission energy produced is much greater than that required to power the accelerator and can be directed to the commercial power grid. A number of possible applications are envisioned for accelerator-driven nuclear systems. These include destruction of surplus weapons-grade plutonium, production of tritium, transmutation of commercial spent fuel, and even commercial power generation in next-generation nuclear power plants. Some of these applications will be discussed with particular emphasis on the required chemical separations for such systems.

Versions of the CINDER code have been used over three decades for determination of reactor fuel inventories and aggregate neutron absorption and radioactive decay properties. The CINDER`90 code, an evolving version which requires no predetermined nuclide chain structure, is suitable for a wider range of transmutation problems including those treated with older versions. In recent accelerator transmutation studies, the CINDER`90 code has been linked with the LAHET Code System (LCS) and, for high-energy calculations, with SUPERHET. A description of the nature of these linked calculational tools is given; data requirements for the transmutation studies are described; and, examples of linked calculations are described for some interesting accelerator applications.

The foundations of many of the subdisciplines of radiological protection laid in accelerator laboratories began with the invention of accelerators. This paper suggests that the discipline of accelerator radiological protection has played and will continue play a more significant part in our lives than is generally recognized. A brief review of some existing uses of accelerators by society is given, and a few probable future uses are described. These future applications will result in the exposure of accelerator (or {open_quotes}mixed{close_quotes}) radiation fields to an increased population. Consequently, what are perceived to be the rather specialized concerns of today`s accelerator health physicists will -- by necessity -- become of general interest to all health physicists.

This report provides an overview of the containers that are currently stored at Pantex and available for use in response to an accident or for use in any other application where a sealed containment vessel and accident resistant overpack may be needed.

In addition to the accuracy-through-order requirement that the defining polynomials not all be divisible by z, as required for Pade and integral approximants, there is the further problem of deficiency as pointed out by McInnes. I prove a finite bound on the deficiency and also prove the accuracy-through-order property for algebraic approximants. In addition I prove the equivalence property for algebraic approximants.

The Army acquisition community currently uses a dedicated, point-to-point secure computer network for the Army Material Plan Modernization (AMPMOD). It must transition to the DOD supplied Defense Secure Network 1 (DSNET1). This is one of the first networks of this size to begin the transition. The type and amount of computing resources available at individual sites may or may not meet the new network requirements. This task surveys these existing telecommunications resources available in the Army acquisition community. It documents existing communication equipment, computer hardware, associated software, and recommends appropriate changes.

Pi{tilde n}on pine germinating seeds, emergent seedlings, and one-year-old seedlings were exposed to sulfur dioxide under both acute and chronic exposure conditions. These fumigations were conducted in order to determine the potential for damage to pi{tilde n}on pine in southwestern national parks and monuments where there is potential for exposure to elevated sulfur dioxide concentrations from smelters and power plants. Injury was apparent only in acute fumigations of one-year-old seedlings at ambient sulfur dioxide concentrations of greater than 3 ppm. Chronic fumigations were conducted only a ambient concentrations of 0.2 ppm. Pi{tilde n}on pine resistance was evidenced by lack of effect of fumigation on biomass and growth parameters. Growth rate data for both experimental and control seedlings were fit to a linear growth model with a correlation (r{sup 2} = 0.95). The results of this study agree with other data in the literature and indicate that damage from elevated sulfur dioxide concentrations in southwestern national parks and monuments is much more likely for other, more sensitive, species than for pi{tilde n}on pine.

As requested in the subject reference, adiabatic calorimetry (RSST and VSP) tests have been performed with sodium acetate covering TOC concentrations from 3 to 7% with the following results: Exothermic activity noted around 200{degrees}C. Propagating reaction initiated at about 300{degrees}C. Required TOC concentration for propagation estimated at about 6 w% (dry mixture) or about 20 w% sodium acetate. Heat of reaction estimated to be 3.7 MJ per kg of sodium acetate (based on VSP test with 3 w% TOC and using a dry mixture specific heat of 1000 J kg{sup {minus}1} K{sup {minus}1}). Based upon the above results we estimate that a moisture content in excess of 14 w% would prevent a propagating reaction of a stoichiometric mixture of fuel and oxidizer ({approximately} 38 w% sodium acetate and {approximately}62 w% sodium nitrate). Assuming that the fuel can be treated as sodium acetate equivalent, and considering that the moisture content in the organic containing waste generally is believed to be in excess of 14 w%, it follows that the possibility of propagating reactions in the Hanford waste tanks can be ruled out.

The objective of the Clean Option Strategy is to reduce the volume of waste from Hanford Storage tanks that must be vitrified and subsequently buried in a deep geologic repository to less than 1000 canisters (1) Advanced chemical separations in support of the Clean Option Strategy comprise a series of novel processes that are designed to extract and recover U, TRUs (Np, Pu, Am, Cm), {sup 90}Sr, {sup 99}Tc and {sup 137}Cs from dissolved sludge waste obtained from Hanford storage tanks. All inert constituents and the balance of the fission products, including barium and the lanthanides (Ln), will remain in the raffinates and effluent streams generated in these processes. The aim of the advanced chemical processes is to reduce the complexity and cost of the chemical pretreatment of the dissolved sludge from the single- and double-shelled tanks. To achieve this goal, Hanford must minimize the number of processes to extract U, TRUs, {sup 90}Sr, {sup 99}Tc and {sup 137}Cs, minimize the number of times that the initial volume of dissolved sludge must be handled, and concentrate product streams to reduce the scale of operation. To meet the requirements of advanced chemical separation processes, all systems must: Readily achieve the desired …

AEP has been supporting research on novel materials for energy technology, renewable and biodegradable materials, new uses for scientific discoveries, alternate pathways to energy efficiency, alternative energy sources, innovative approaches to waste treatment and reduction, etc. The summaries are grouped according to projects active in FY 1993, Phase I SBIR projects, and Phase II SBIR projects. Investigator and institutional indexes are included.

The overall objective of this project is to develop a new approach for the direct liquefaction of coal to produce an all-distillate product slate at a sizable cost reduction over current technology. The approach integrates coal selection, pretreatment, coal swelling with catalyst impregnation, liquefaction, product recovery with characterization, alternate bottoms processing, and carrying out a technical assessment including an economic evaluation. The primary coal of this program, Black Thunder subbituminous coal, can be effectively beneficiated to about 4 wt% ash using aqueous sulfurous acid pretreatment. This treated coal can be further beneficiated to about 2 wt% ash using commercially available procedures. All three coals used in this study (Black Thunder, Burning Star bituminous, and Martin Lake lignite) are effectively swelled by a number of solvents. The most effective solvents are those having hetero-functionality. In addition, a synergistic effect has been demonstrated, in which solvent blends are more effective for coal swelling than the pure solvents alone. Therefore, it will be necessary to use only low levels of swelling agents and yet promote the impregnation of catalyst precursors. The rate of the impregnation of catalyst precursors into swollen coal increases greatly as the effectiveness of the solvent to swell the coal …

This report discusses the following on the Advanced Neutron Source: A global view; neutron research improves our lives; the challenge; the solution; neutron research; some major applications; environmental, safety, and health considerations; education; what the ANS means for local communities; and what will the ANS cost.

This project addressed two main goals and one much smaller one. The main goals were (1) to improve the significance, reliability and information content in high-resolution NMR (nuclear magnetic resonance) characterization of coal samples and (2) to develop chemically informative NMR imaging techniques for coal. The minor goal was to explore advanced features of dynamic nuclear polarization (DNP) as a technique for coal characterization; this included the development of two DNP probes and the examination of DNP characteristics of various carbonaceous samples, including coals. {sup 13}C NMR advances for coal depended on large-sample MAS devices, employing either cross-polarization (CP) or direct polarization (DP) approaches. CP and DP spin dynamics and their relationships to quantitation and spin counting were elucidated. {sup 1}H NMR studies, based on CRAMPS, dipolar dephasing and saturation with perdeuteropyridine, led to a {sup 1}H NMR-based elucidation of chemical functionality in coal. {sup 1}H and {sup 13}C NMR imaging techniques, based on magic-angle spinning and rotating magnetic field gradients, were developed for introducing chemical shift information (hence, chemical detail) into the spatial imaging of coal. The TREV multiple-pulse sequence was found to be useful in the {sup 1}H CRAMPS imaging of samples like coal.

One of the main problems in coal utilization is the inability to properly characterize its complex pore structure. Coals typically have micro/ultramicro pores but they also exhibit meso and macroporosity. Conventional pore size techniques (adsorption/condensation, mercury porosimetry) are limited because of this broad pore size range, microporosity, reactive nature of coal, samples must be completely dried, and network/percolation effects. Small angle scattering is limited because it probes both open and closed pores. Although one would not expect any single technique to provide a satisfactory description of a coal`s structure, it is apparent that better techniques are necessary. Small angle scattering could be improved by combining scattering and adsorption measurements. Also, the measurement of NMR parameters of various gas phase and adsorbed phase NMR active probes can provide pore structure information. We will investigate the dependence of the common NMR parameters such as chemical shifts and relaxation times of several different nuclei and compounds on the pore structure of model microporous solids, carbons, and coals. In particular, we will study the interaction between several small molecules ({sup 129}Xe, {sup 3}He, {sup 2}H{sub 2},{sup 14}N{sub 2}, {sup 14}NH{sub 3}, {sup 15}N{sub 2},{sup 13}CH{sub 4}, {sup 13}CO{sub 2}) and the pore surfaces in …

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This report documents an improved preparation of low density microcellular carbon as well as characterization of spatial homogeneity. The report also documents the process for preparing the nficrocellular carbon from poly(acrylonitrile) raw material. A microcellular polymer precursor (0.025 g/cc) is first prepared via a solution-based process and then pyrolyzed to produce the microcellular carbon in a monolithic form (0.05 g/cc). The process improvement developed in this study permits the pore structure of the n-ficrocellular polymer precursor and the microcellular carbon to be reproduced consistently in different laboratories. Pore structure is affected by the completeness of dissolution of the polymer raw material, which variable can be adjusted via dissolution temperature or particle size of the raw material. The second topic in this report involves determining the spatial fluctuation in mass density caused by periodic, millimeter-scale bands, known as `tree rings` visible on machined surfaces of the carbon monoliths. To measure the fluctuations, we developed a high precision, spatially resolved X-ray transmission technique. The periodic bands caused less than {plus_minus}2% variation of mass density in a microcellular carbon having average density 0.041 g/cc.