A Perkin-Elmer 3920 gas chromatograph and associated software has been ordered. The materials necessary to interface it to the CEC 21-110B mass spectrometer and the other auxiliary components of the total GC/MS system are being acquired. Elemental composition data were obtained from 35 coal-liquid samples from the mass spectra of each sample recorded at high resolution on photographic plates. (auth)

A major challenge in the development of optical glasses for high-power lasers is reducing or eliminating laser-induced damage to the interior (bulk) and the polished surface of the glass. Bulk laser damage in glass generally originates from inclusions. With the development of novel glass melting and forming processes it is now possible to make both fused silica and a suit of meta-phosphate laser glasses in large sizes ({approx}>0.5-lm diameter), free of inclusions and with high optical homogeneity ({approx} 10{sup -6}). Considerable attention also has been focused on improving the laser damage resistance to polished optical glass surfaces. Studies have shown that laser-induced damage to surfaces grows exponentially with the number of shots when illuminated with nano-second pulses at 351-nm above a given fluence threshold. A new approach for reducing and eliminating laser-induced surface damage relies on a series of post-polishing treatment steps. This damage improvement method is briefly reviewed.

Due to increasing environmental concerns, in 1994, the California Air Resources Board (CARB) and the U.S. Environmental Protection Agency (EPA) began implementing regulations that require automakers to incorporate comprehensive on-board diagnostics into new vehicles. The purpose is to monitor emissions, which will allow early detection of any malfunctioning of the engine and/or exhaust treatment system. Currently, monitorings of hydrocarbon and NOx emissions are regarded as being the most critical for evaluating car emissions.

The study of the electrochemical behavior of wrought and welded Alloy 22 was carried out in 5 M CaCl{sub 2} between 45 and 120 C with Multiple Crevice Assembly (MCA) specimens. The susceptibility to corrosion was found to increase with increase in temperature in both the wrought and the welded forms of the alloy. The weld metal was found to be less susceptible to localized corrosion under the conditions tested.

The aims of the proposed project are to enrich our understanding of the roles of various aqueous soluble catalyst precursor anions on the surface electrical properties of coal and to ascertain the influence of the surface charge on the adsorption, dispersion, and activities of calcium and potassium. These goals will be achieved by impregnating a North Dakota lignite (PSOC 1482) and its demineralized derivative with calcium or potassium catalyst precursors containing acetate (CH{sub 3}COO{sup {minus}}), chloride (Cl{sup {minus}}), nitrate (NO{sub 3}{sup {minus}}), sulfate (SO{sub 4}{sup 2{minus}}), and carbonate (CO{sub 3}{sup 2{minus}}) anions. Catalyst loading will be conducted under well-controlled conditions of solution pH and ionic strength. In the last quarter, the surface charge properties of the coal was determined as a function of acetate (CH{sub 3}COO{sup {minus}}), chloride (Cl{sup {minus}}), nitrate (NO{sup 3}{sup {minus}}), carbonate (CO{sub 3}{sup 2{minus}}) or sulfate (SO{sub 4}{sup 2{minus}})concentration using the respective potassium salts of these anions. In general, low anion concentrations (10{sup {minus}3} or 10{sup {minus}2} mol/L) had little effect on the zeta potentials of the coals. However, the surface charge densities of the coal become less negative at 10-1 mol/L of the nitrate, carbonate or sulfate anions. These trends suggest that the surface charge …

Radiative strength functions and level densities have been extracted from primary {gamma}-ray spectra for {sup 27,28}Si, {sup 56,57}Fe, {sup 96,97}Mo, and several rare earth nuclei. An unexpectedly strong ({approx} 1 mb MeV) resonance at 3 MeV in the radiative strength function has been observed for well-deformed rare earth nuclei. The physical origin of this resonance and its connection to the scissors mode is discussed.

Lawrence Livermore National Laboratory (LLNL) integrates and collects data for use in calibration of seismic detection, location, and identification. Calibration data is collected by (1) numerous seismic field efforts, many conducted under NNSA (ROA) and DTRA (PRDA) contracts, and (2) permanent seismic stations that are operated by national and international organizations. Local-network operators and international organizations (e.g. International Seismic Center) provide location and other source characterization (collectively referred to as source parameters) to LLNL, or LLNL determines these parameters from raw data. For each seismic event, LLNL rigorously characterizes the uncertainty of source parameters. This validation process is used to identify events whose source parameters are accurate enough for use in calibration. LLNL has developed criteria for determining the accuracy of seismic locations and methods to characterize the covariance of calibration datasets. Although the most desirable calibration events are chemical and nuclear explosions with highly accurate locations and origin times, catalogues of naturally occurring earthquakes offer needed geographic coverage that is not provided by man made sources. The issue in using seismically determined locations for calibration is validating the location accuracy. Sweeney (1998) presented a 50/90 teleseismic, network-coverage criterion (50 defining phases and 90{sup o} maximum azimuthal gap) that generally …

The power deposition of an incident electron beam in a tungsten-rhenium target and the resultant thermal shock stresses in the material have been modeled with a transient, dynamic, structural response finite element code. The Next Linear Collider electron beam is assumed split into three parts, with each part impinging on a 4 radiation lengths thick target. Three targets are required to avoid excessive thermal stresses in the targets. Energy deposition from each beam pulse occurs over 265 nanoseconds and results in heating of the target and pressure pulses straining the material. The rapid power deposition of the electron beam and the resultant temperature profile in the target generates stress and pressure waves in the material that are considerably larger than those calculated by a static analysis. The 6.22 GeV electron beam has a spot radius size of 3 mm and results in a maximum temperature jump of 147 C. Stress pressure pulses are induced in the material from the rapid thermal expansion of the hotter material with peak effective stresses reaching 83 ksi (5.77 x 10{sup 8} Pa) on the back side of the target, which is less than one half of the yield strength of the tungsten/rhenium alloy and …

AMAX Research & Development Center (AMAX R&D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.

This report was prepared for the Ohio Coal Development Office (OCDO) under Grant Agreement No. CDO/R-88-LRl and comprises two volumes. Volume I presents data on the chemical, physical, and leaching characteristics of by-products from a wide variety of clean coal combustion processes. Volume II consists of a discussion of (a) process modification waste minimization opportunities and stabilization considerations; (b) research and development needs and issues relating to clean coal combustion technologies and by-products; (c) the market potential for reusing or recycling by-product materials; and (d) regulatory considerations relating to by-product disposal or reuse.

This is a condensed version of an extended hazards safety review of a proposal to modify the six 8 3/8-inch lattice reactors on the Hanford site. The review was intended to satisfy the specifications for a Preliminary Hazards Review as adopted at the third meeting of the General Electric Technological Hazards Council at New York City on June 15-16, 1961. This supplement is a tabular condensation of the information in the general document. One departure is made from the specifications for such a review: since the overbore proposal is a modification to existent production reactors, those items which will not be changed by the modification are not as a rule included.

None

This report was prepared for the Ohio Coal Development Office (OCDO) under Grant Agreement No. CDO/R-88-LR1 and comprises two volumes. Volume 1 presents data on the chemical, physical, and leaching characteristics of by-products from a wide variety of clean coal combustion processes. Volume 2 consists of a discussion of (a) process modification waste minimization opportunities and stabilization considerations; (b) research and development needs and issues relating to clean coal combustion technologies and by-products; (c) the market potential for reusing or recycling by-product materials; and (d) regulatory considerations relating to by-product disposal or reuse.

Higher, i.e. C{sub 2{sup +}}, alcohols are desired as gasoline additives, feedstocks for producing ethers and as alternative fuels for automobiles. In all cases, the backbone branching of an alcohol improves octane rating, which is essential for good engine performance. These types of branched, higher alcohols are the desired products for a process converting synthesis gas, a CO and H{sub 2} mixture, often generated from coal gasification. Based on this premise, promoted ZnCr oxide catalysts appear to be as one of the best avenues for further investigation. Once this investigation is complete, a natural extension is to replace the Cr in the ZnCr oxide catalyst with Mo and W, both in the same elemental triad with Cr. Mo has already been shown as an active HAS catalyst, both on a SiO{sub 2} support and in the MoS{sub 2} form. The three catalyst combinations, ZnMo, ZnW, and MnCr oxides will be tested in the stirred autoclave system. However, if none of the three indicate any comparable activity and/or selectivity toward higher alcohols as compared with other HAS catalysts, then an investigation of the effects of Cs promotion on the ZnCr oxide methanol catalysts will be executed.

Procurement and installation are proposed of a 50-kW, high-frequency induction heating unit for can-sleeve preheating prior to dip brazing to the uranium core.

The Environmental Compliance Program is developing and implementing a PHMC-wide chemical management system with the goal being to: (1) manage and control chemicals from procurement through use and final disposition; (2) develop and maintain procedures for identifying and evaluating hazards and environmental impacts present in facilities, and the hazard classification of the facilities. The US Department of Energy (DOE) may promulgate the final rule, 1 0 CFR 834, Radiation Protection of the Public and the Environment in FY 1999. This rule establishes controls for the release of radioactive material and limits for the amount of radiation exposure to the public and the environment. It will be applicable to activities of DOE contractors at the Hanford site. This rule is expected to replace the bulk of DOE Orders 5400.5, Radiation Protection of the Public and the Environment and 5400. 1, General Environmental Protection Program. In doing so, these Orders will be backed by the Price-Anderson enforcement procedures and carry penalties for non-compliance.

The purpose of this engineering study is to investigate the available technology related to dissolution of the K Basin sludge in nitric acid. The conclusion of this study along with laboratory and hot cell tests with actual sludge samples will provide the basis for beginning conceptual design of the sludge dissolver. The K Basin sludge contains uranium oxides, fragments of metallic U, and some U hydride as well as ferric oxyhydroxide, aluminum oxides and hydroxides, windblown sand that infiltrated the basin enclosure, ion exchange resin, and miscellaneous materials. The decision has been made to dispose of this sludge separate from the fuel elements stored in the basins. The sludge will be conditioned so that it meets Tank Waste Remediation System waste acceptance criteria and can be sent to one of the underground storage tanks. Sludge conditioning will be done by dissolving the fuel constituents in nitric acid, separating the insoluble material, adding neutron absorbers for criticality safety, and then reacting the solution with caustic to co-precipitate the uranium and plutonium. There will be five distinct feed streams to the sludge conditioning process two from the K East (KE) Basin and three from the K West (KW) Basin. The composition of …

Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 tons/ month may proceed for six months and, assuming continued favorable performance, up to 150 tons/month may be accepted to complete large scale evaluation of dingot uranium, and on a continuing basis thereafter.

An O III N, I and E dingot element exhibited several transverse cracks when it failed in tube 2986 DR. Detailed examination in the Radiometallurgy Laboratory was requested to determine the cause of failure and obtain the ingot number. The element was so badly damaged that it was impossible to determine the exact cause of failure. Reaction between the coolant and fuel occurred at the internal surface around the spire over the total length of the element. Reaction was the greatest near the midpoint where the transverse cracks occurred and was least in the male end. Metallography of both longitudinal and transverse sections revealed that the metal quality of the fuel vas good. Cracks which originated from the oxide extended in both the longitudinal and transverse directions. The fuel near the core, which was insulated by oxide, was annealed but had not been heated into the uranium beta phase. One transverse crack which appeared to have water entry was observed approximately two inches from the male end. The ingot number was UZ 5751 B. After removal of the cladding at the ends, the uranium was bright dip etched and no defects were observed in the surface metal.

The K East (KE) and K West (KW) fuel storage basins at the 100 K Area of the Hanford Site contain sludge on the floor, in pits, and inside fuel storage canisters. The major sources of the sludge are corrosion of the fuel elements and steel structures in the basin, sand intrusion from outside the buildings, and degradation of the structural concrete that forms the basins. The decision has been made to dispose of this sludge separate from the fuel elements stored in the basins. The sludge will be treated so that it meets Tank Waste Remediation System (TWRS) acceptance criteria and can be sent to one of the double-shell waste tanks. The US Department of Energy, Richland Operations Office accepted a recommendation by Fluor Daniel Hanford, Inc., to chemically treat the sludge. Sludge treatment will be done by dissolving the fuel constituents in nitric acid, separating the insoluble material, adding neutron absorbers for criticality safety, and reacting the solution with caustic to co-precipitate the uranium and plutonium. A truck will transport the resulting slurry to an underground storage tank (most likely tank 241-AW-105). The undissolved solids will be treated to reduce the transuranic (TRU) and content, stabilized in grout, …

Three self support, natural uranium, I & E production fuel elements, which exhibited serious in-reactor cladding corrosion were selected from several tubes of discharged pieces from PT-IP-272-A-FP. The elements were transferred to the Radiometallurgy Laboratory for detailed examination to determine thickness of the remaining cladding and measure any irradiation induced dimensional changes in the fuel cores. Each element had four support tabs attached to each end and was from Parent Lot KT.009. The fuel geometry of all three was C IV NS.

None

The effective starting date of this grant was May 15. In the first three months of this project we focused primarily on organizational and technical aspects of our research which included: organization of the database of repeats in primates; preparation of software for rapid and sensitive search of novel repetitive elements in GenBank; purchase and installation of the Sun workstation; and research on the mammal-specific MAR1 family of repetitive elements (to be communicated in October).

The development and verification of advanced computer models which describe the boiling water reactor (BWR) pressure suppression process for a hypothetical loss-of-coolant accident (LOCA) require a clear description of basic steam condensation phenomena. The GKSS Research Center, in coordination with interested institutions of West Germany and the United States, is currently conducting a test program for such basic research on a multivent BWR-related pressure suppression system. The Lawrence Livermore National Laboratory (LLNL) acts as the principal US NRC liaison for this test program, with particular emphasis on development of GKSS data for confirmatory use regarding US Mark II nuclear power plants as well as to advanced code development. The multivent test facility, placed in operation in February 1979, is a three-pipe full-scale vent system modelling main features of both the West German KWU and United States G.E. Mk II BWR pressure suppression systems. The test facility and testing programs are described.