The Battelle Northwest Liquid Level Probe was evaluated for possible use in the LOFT Blowdown Suppression Tank. The results from the test indicate that the probe will measure the liquid level to +-/sup 1///sub 4/ inch, over a range of 50 inches. The next step is to test the functionability of the probe under simulated LOFT-Blowdown Suppression Tank operating conditions.

This review contains 175 references to commonly encountered dissolution problems.

The Safety Analysis Report for Packaging (SARP) satisfies the request of the U.S. Energy Research and Development Administration for a formal safety analysis of the insulated drum shipping container identified as USA/9506/BLF(DOE-A1). Included are discussions of structural integrity, thermal resistance, radiation shielding and radiological safety, nuclear criticality safety, and quality control. Complete physical and technical descriptions of the packages are presented.

Recent studies have shown straightforward systematic behavior as a function of constant proton and neutron number for neutron-induced fission cross sections of the actinide elements in the incident-neutron energy range 3 to 5 MeV. In this report, the second in a series, fission cross-section values are studied over the MeV incident-neutron energy range, and at 0.0253 eV. Fission-barrier heights and neutron-binding energies are correlated by constant proton and neutron number; however, these systematic behaviors alone do not explain the trends observed in the fission cross-section values.

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The Laser Cyclotron Auto-Resonant Accelerator LACARA has successfully operated this year. Results are summarized, an interpretation of operating data is provided in the body of the report, and recommendations are made how the experiment should be carried forward. The Appendix A contains a description of the LACARA apparatus, currently installed at the Accelerator Test Facility, Brookhaven National Laboratory. This report summarizes the project, extending over three grant-years.

A team comprised of governmental, academic and industrial partners led by the Savannah River National Laboratory developed and demonstrated a regenerative fuel cell system for backup power applications. Recent market assessments have identified emergency response and telecommunication applications as promising near-term markets for fuel cell backup power systems. The Regenerative Fuel Cell System (RFC) consisted of a 2 kg-per-day electrolyzer, metal-hydride based hydrogen storage units and a 5 kW fuel cell. Coupling these components together created a system that can produce and store its own energy from the power grid much like a rechargeable battery. A series of test were conducted to evaluate the performance of the RFC system under both steady-state and transit conditions that might be encountered in typical backup power applications. In almost all cases the RFC functioned effectively. Test results from the demonstration project will be used to support recommendations for future fuel cell and hydrogen component and system designs and support potential commercialization activities. In addition to the work presented in this report, further testing of the RFC system at the Center for Hydrogen Research in Aiken County, SC is planned including evaluating the system as a renewable system coupled with a 20kW-peak solar photovoltaic …

High-energy (MeV) ion implantation is now being rapidly introduced into integrated circuit manufacturing because it promises process simplification and improved device performance. However, high-energy implantation introduces an imbalance of excess vacancies and vacancy-cluster defects in the near-surface region of a silicon crystal. These defects interact with dopants affecting diffusion and electrical activation during subsequent processing. The objective of this project was to develop sufficient understanding of the physical mechanisms underlying the evolution of these defects and interactions with dopant atoms to enable accurate prediction and control of dopant diffusion and defect configurations during processing. This project supported the DOE mission in science and technology by extending ongoing Basic Energy Sciences programs in ion-solid physics and x-ray scattering at ORNL into new areas. It also strengthened the national capability for advanced processing of electronic materials, an enabling technology for DOE programs in energy conversion, use, and defense.

A group of documents pertaining to the Dallas County Department of Human Services funding and budget listed for the year 1993.

Two principal deposition processes are compared for the case of depositing 1 to 2 ..mu..m beryllium on fused-silica substrates. While the evaporation-deposition process offers advantages such as higher deposition rate, purification of the evaporant and efficient use of masks, the sputter-deposition is more versatile, and therefore more effective, in varying and controlling the microstructure of the deposits. The versatility comes about because the latter process has five major operational parameters to be selected or adjusted. Consequently, sputter-deposited beryllium films are expected to display more desirable microstructures and better surface finish than evaporation-deposited films.

Energy-dependent evaluated photon interaction cross sections and related parameters are presented for elements H through Cf(Z = 1 to 98). Data are given over the energy range from 0.1 keV to 100 MeV. The related parameters include form factors and average energy deposits per collision (with and without fluorescence). Fluorescence information is given for all atomic shells that can emit a photon with a kinetic energy of 0.1 keV or more. In addition, the following macroscopic properties are given: total mean free path and energy deposit per centimeter. This information is derived from the Livermore Evaluated-Nuclear-Data Library (ENDL) as of October 1978.

Abstract: "A theoretical and experimental investigation is made of the diffraction pattern produced by a slit, whose aperture varies uniformly from a constant value A to zero. The results of this investigation are applied to a proposed high speed camera. It is shown that diffraction effects are very serious and cannot be neglected. It seems, unless the suggested design of this high speed camera is changed, the camera will be of little use for accurate measurements, and photographs will show too much blue to give details."

220 MeV is the energy that has to be obtained in routine operation. A standard 12m girder with SLED II can give 220 MeV minus a few percent due to not riding at the crest of the wave. In order to have the 200 MeV with only one girder, a klystron at full power all the time would be required - kept brand new. Then, for safety it is necessary to use two klystrons as designated in the SLC design. Having two klystrons gives freedom for the choice of the best arrangement. Since there will be excess rf power, it can be traded against higher gradient, shorter waveguides, larger apertures (lower shunt impedence).

This program calls for the development and delivery of eight prototype solar heating and cooling systems for installation and operational test. Two heating and six heating and cooling units will be delivered for single-family residences, multiple-family residences and commercial applications. This document describes the progress of the program during the fifth program quarter, 1 July 1977 to 30 September 1977.

The General Electric Company operates eight large filter plants for the Atomic Energy Commission at the Hanford works in the state of Washington. Because of the importance of water to the process, research and development on water treatment has been an important part of the overall Hanford research and development program. The research and development on water treatment has resulted in important capital and operating savings and in the production of better quality water. It is the purpose of this paper to present some of the information developed by the programs. 3 tabs.

Geologic systems generally are complex with physical properties and trends that can be difficult to predict. Subsurface geology exerts a fundamental control on groundwater flow and contaminant transport. The primary source for direct observation of subsurface geologic information is a borehole. However, direct observations from a borehole essentially are limited to the diameter and spacing of boreholes and the quality of the information derived from the drilling. Because it is impractical to drill a borehole every few feet to obtain data, it is necessary to maximize the data gathered during limited drilling operations. A technically defensible balance between the customer`s data quality objectives and control of drilling costs through limited drilling can be achieved with proper conduct of operations. This report presents the minimum criteria for geologic and hydrologic characterization and sampling that must be met during drilling. It outlines the sampling goals that need to be addressed when drilling boreholes, and the types of drilling techniques that work best to achieve these goals under the geologic conditions found at Hanford. This report provides general guidelines for: (1) how sampling methods are controlled by data needs, (2) how minimum sampling requirements change as knowledge and needs change, and (3) when …

This report compares the activity and disintegration energy of fission products from metal under two conditions of exposure: 200 Megawatt-days integrated exposure over a period of 180 days, and 400 Megawatt-days integrated exposure over a period of 360 days. (JL)

Depolymerization of coals at low temperatures may offer advantages over thermal bond cleavage. Because bond cleavage energies of radical cations are lower than the corresponding homolytic bond cleavage energies of the same bond, generation of radical cations in coal may make possible depolymerization at lower temperatures. We seek to investigate the above possibility using single molecules containing functional groups common in coals. Since the generation of a radical cation requires the removal of an electron from a neutral molecule, a primary focus of the study will be finding oxidants that will remove an electron from compounds with structural similarity to those typically found in coals. The study will also be concerned with the decomposition of radical cations and the products formed as a result of the decomposition. In our last report we described that treatment of bibenzyl and neo-pentylbenzene with Fe(III) (1,10-phenanthroline){sub 3}(ClO{sub 4}){sub 3} (Fe(III)(PHEN)) in refluxing CH{sub 3}CN (82{degrees}C) failed to produce substantial bond cleavage {beta} to the aromatic ring. Because bond cleavage was not observed, we have continued our study by moving to compounds which have lower ionization potentials as well as study other oxidants.

This report provides a complete description of the analytic and discretized equations for 2D deterministic radiation transport. This computational model has been checked against a wide variety of analytic test problems and found to give excellent results. We make extensive use of the discontinuous finite element method.

This document considers the costs of rhenium formation as produced by irradiating tungsten. Two isotopic compositions of tungsten are considered for the study. The cost for reactor-formed rhenium appears to be prohibitively high -- over $20 per gram. This cost would exist for tungsten containing 90% 186, 9, 184, and 1% tungsten 182 and 183. The cost of alloy made fro natural isotopic compositions of tungsten would be higher by a factor of 3, and would take prohibitively long to produce significant quantities of rhenium. Thus, detailed numbers are not shown or considered for the natural isotopic composition of tungsten.

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This report contains the feasibility and cost data for the production of tungsten-rhenium alloys from tungsten targets in the N-Reactor. The two types of target elements assumed were: (a) tungsten containing 90 a/o tungsten-186, 9 a/o tungsten-184 and 1 a/o tungsten-183 and 182, and (b) tungsten of natural isotopic composition.

The use of organic cooling media for nuclear reactors operating at high power levels predicates the use of a coolant which will not react violently with metallic uranium in the event of a fuel element failure. This report describes the testing, and subsequent examination, of two pieces of irradiated uranium which were immersed in monoisopropylbiphenyl (MIPB) at high temperatures and pressures for periods of time up to twenty-five days. The uranium samples had different irradiation histories and cooling times. Similar experiments had been performed with unirradiated uranium by the Corrosion and Coatings Operation, and it was wished to determine whether irradiated uranium would react with MIPB in a different manner.

The purpose of this work has been to determine the production rate of tritium in fringe Li-Al alloy columns with the degree of precision necessary for economic analyses of such reactor loadings. These results are provided for use in such an analysis. This experiment indicates the production rate of tritium in the outermost fringe tubes to be T = 0.0216 M{sub E} = 0.175 M{sub t} where T = grams of tritium per full length (67 pieces) charge of Li-Al alloy material; M{sub E} = MWD/adjacent ton of E metal; M{sub t} = MWD/adjacent tube of E metal. The above values should apply for fringe loads utilizing greater or smaller quantities of E metal; that is, for isotope production loadings which are over or under-compensated from a reactivity standpoint. In the actual test load it was calculated that one gram of tritium and 13.5 grams of Pu were made for each 21.3 grams of U-235 burned up. During the same time interval the displaced uranium loading would have generated 24.3 grams of Pu and burned up 29.9 grams of U-235. The factor which seems to limit the accuracy with which these data can be interpreted is the ratio of the …