We report the measurement of the lifetime of the tau lepton. This measurement was made using the HRS spectrometer at PEP, operating at 29 GeV. The 3 prong decay vertices were measured using a four layer tubular cell vertex chamber. The lifetime of the tau was determined to be tau/sub tau/ = .28 +- .02 +- .02 ps. 7 refs., 3 figs.

The objective of this program is to develop a synthesis gas conversion catalyst with higher selectivity to liquid fuels, while maintaining catalytic activity and stability at least equivalent relative to state-of-the-art precipitated iron catalysts. Hydrocarbon cutoff hypothesis and developmental needs for a ruthenium catalyst with low light ends selectivity were investigated during this quarter. Hydrocarbon product distribution was Anderson-Schulz-Flory up to a carbon number of 250 and cutoff did not occur with a titania-supported catalyst containing ruthenium particles smaller than 20[Angstrom]. It was found that an alumina-supported catalyst with 1% (by weight) ruthenium in the form of 50[Angstrom] to 100[Angstrom] metal particles was initially about half as active (by catalyst volume) and made one quarter of the amount of C[sub 1][minus]C[sub 4] light end products relative to the Sasol precipitated iron catalyst.

The objective of this program is to develop a synthesis gas conversion catalyst with higher selectivity to liquid fuels, while maintaining catalytic activity and stability at least equivalent relative to state-of-the-art precipitated iron catalysts. During this quarter, the emphasis in the program has been the investigation of the hydrocarbon cutoff hypothesis with supported ruthenium catalysts. An alumina-supported catalyst with smaller than 20[Angstrom] ruthenium particles was tested under conditions of maximal water gas shift activity. During this test more than 90% of the water made in the Fischer-Tropsch synthesis reaction was converted to H[sub 2]. However, the extent of ruthenium metal agglomeration was not reduced. Accordingly, it was not possible to conclude whether hydrocarbon cutoff occurs with smaller than 20[Angstrom] ruthenium particles on [gamma]-alumina. A ruthenium catalyst prepared on Y-type zeolite had 20[Angstrom] or smaller ruthenium particles according to STEM examination and a 15[Angstrom] average ruthenium metal particle size according to EXAFS examination. The ruthenium metal particle size was stable during the test with this catalyst. The hydrocarbon product distribution was Anderson-Schulz-Flory with no cutoff up to a carbon number of 160. A well-dispersed titania-supported ruthenium catalyst is going to be evaluated during the next quarter in order to determine whether …

The objective of this program is to develop a synthesis gas conversion catalyst selective to gasoline or diesel range fuel via application of a micelle technique for preparing specific site supported ruthenium particles. The current emphasis is to investigate hydrocarbon cutoff principle and to apply it for developing selective catalysts. During this quarter, micelle technique was further improved and 1 ruthenium particle:l reverse micelle limit was approached by careful control of catalyst synthesis conditions. Accordingly, it became possible to synthesize supported particles that closely meet the size and composition targets originally set. This improved technique was applied to synthesis of chemically modified ruthenium catalysts. Some of the chemically modified ruthenium catalysts will be evaluated later in the program. We previously reported that 40--60 [Angstrom] ruthenium particles prepared on [gamma]-alumina do not result in hydrocarbon cutoff. We could not determine then whether smaller ruthenium particles result in hydrocarbon cutoff because these particles agglomerated via ruthenium carbonyl formation during the course of a 6--10 day test. We have recently evaluated a catalyst with 20--40 [Angstrom] ruthenium particles prepared on [gamma]-alumina by carefully analyzing products initially made during the test prior to substantial ruthenium agglomeration. We concluded that cutoff is not effected by …

The objective of this program is to develop a synthesis gas conversion catalyst with improved selectivity to gasoline or diesel range fuel via application of a micelle technique for preparing novel supported catalysts with specific size ruthenium particles. The major emphasis is to investigate hydrocarbon cutoff principle and to apply it for developing selective catalysts. We previously reported that cutoff is not effected with 40--60 [Angstrom] and 20--40 [Angstrom] ruthenium particles on [gamma]-Al[sub 2]O[sub 3]. We recently tested a catalyst with <20 [Angstrom] ruthenium particles. Well dispersed ruthenium in that catalyst extensively agglomerated to larger particles even during the course of a short test despite the high H[sub 2]:CO ratio used. Therefore, we could not conclude whether cutoff is effected with <20 [Angstrom] ruthenium particles. We are going to continue to evaluate the effect of operational conditions and also evaluate the effect of modifiers on ruthenium agglomeration. A catalyst with <20 [Angstrom] ruthenium particles will be evaluated to investigate occurrence of cutoff, after no agglomeration conditions are identified. We are now proposing to conduct, parallel to the main approach, a second research approach which will aim at developing a ruthenium catalyst with substantially lower light ends selectivity while maintaining at …

March 1, 1984, was the 30th anniversary of the Bravo thermonuclear test that resulted in the accidental exposure of the populations of Rongelap and Utirik atolls to radioactive fallout. The chronicling of the medical events resulting from that exposure is continued in this report, which covers the period from January 1983 through December 1984. An updated listing of all relevant publications from the Medical Department Brookhaven National Laboratory, is presented in the Reference Section. Thirty years of observation continue to show no detectable increase in mortality in the exposed population as a result of that exposure. The survival curves of the high-exposure Rongelap group, the low-exposure Utirik population, and an unexposed group of Rongelap people matched by age and sex to the exposed Rongelap group in 1957 continue to be similar. 89 refs., 2 figs., 6 tabs.

This technical note (TN) reports on the development of a zero-order ASPEN (Advanced System for Process Engineering) model for the fluidized-bed retort/combustion of an eastern oil shale. The objective of the work described was to identify data needs and to create a structure for future, more definitive models. New Albany shale was the initial reference eastern shale at the Department of Energy (DOE)/Morgantown Energy Technology Center (METC). A literature search on this shale was conducted to find the physical property data required for the ASPEN model. This TN discusses the types of missing or incomplete data, the process being modeled, and how process variables are affected by varying input parameters. The TN also presents recommendations for increasing the reliability of the simulation. 12 refs., 3 figs., 5 tabs.

Pacific Northwest Laboratory conducted a study to evaluate alternatives to the design and operation of nuclear power plants, emphasizing a reduction of their vulnerability to sabotage. Estimates of core melt accident frequency during normal operations and from sabotage/tampering events were used to rank the alternatives. Core melt frequency for normal operations was estimated using sensitivity analysis of results of probabilistic risk assessments. Core melt frequency for sabotage/tampering was estimated by developing a model based on probabilistic risk analyses, historic data, engineering judgment, and safeguards analyses of plant locations where core melt events could be initiated. Results indicate the most effective alternatives focus on large areas of the plant, increase safety system redundancy, and reduce reliance on single locations for mitigation of transients. Less effective options focus on specific areas of the plant, reduce reliance on some plant areas for safe shutdown, and focus on less vulnerable targets.

An experimental approach for the nondestructive characterization of plutonium and uranium solutions is presented. The technique relies on the transmission of photons of three different properly chosen energies, and allows an independent and simultaneous determination of plutonium and uranium by the different absorption of the two elements in the range of K-edge energies. The performances achievable have been evaluated through measurement of a set of solutions using the hardware of the compact K-edge densitometer. The plutonium and uranium concentrations ranged from 50 to 150 g/l. In this concentration range, the relative precision is below 3.0% for uranium assay and below 6% for plutonium assay. Further improvements of the performances of the technique are discussed. 3 refs., 9 figs., 1 tab.

A numerical technique designed to solve a wide class of convectively dominated flow problems is presented. An attractive feature of the technique is its ability to resolve the behavior of field quantities possessing large gradients and/or shocks. The method is a finite-difference technique known as flux-corrected transport (FCT) that maintains four important numerical considerations - stability, accuracy, monotonicity, and conservation. The theory and methodology of two-dimensional FCT is presented. The method is applied in demonstrative example calculations of a 2-D Riemann problem with known exact solutions and to the Euler equations in a study of classical Rayleigh-Taylor and Kelvin-Helmholtz instability problems. The FCT solver has been vectorized for execution on the Cray 1S - a typical call with a 50 by 50 mesh requires about 0.00428 cpu seconds of execution time per call to the routine. Additionally, we have maintained a modular structure for the solver that eases its implementation. Fortran listings of two versions of the 2-D FCT solvers are appended with a driver main program illustrating the call sequence for the modules. 59 refs., 49 figs.

The descriptions and results of two separate heat transfer tests designed to investigate the dry storage of commercial PWR spent fuel assemblies are presented. Presented first are descriptions and selected results from the Fuel Temperature Test performed at the Engine Maintenance and Disassembly facility on the Nevada Test Site. An actual spent fuel assembly from the Turkey Point Unit Number 3 Reactor with a decay heat level of 1.17 KW, was installed vertically in a test stand mounted canister/liner assembly. The boundary temperatures were controlled and the canister backfill gases were alternated between air, helium and vacuum to investigate the primary heat transfer mechanisms of convection, conduction and radiation. The assembly temperature profiles were experimentally measured using installed thermocouple instrumentation. Also presented are the results from the Single Assembly Heat Transfer Test designed and fabricated by Allied General Nuclear Services, under contract to the Department of Energy, and ultimately conducted by the Pacific Northwest Laboratory. For this test, an electrically heated 15 x 15 rod assembly was used to model a single PWR spent fuel assembly. The electrically heated model fuel assembly permitted various ''decay heat'', levels to be tested; 1.0 KW and 0.5 KW were used for these tests. …

This project deals with the seasonal snow on Alaska's Arctic Slope. It is concentrated on snow of the R{sub 4}D project area. However, an important aspect of this study is to relate the snow cover of this area with the rest of the Arctic Slope. The goals include determination of the amount of precipitation which comes as snow, the wind transport of this snow and its depositional pattern as influenced by drifting, the physical properties of the snow, the physical processes which operate in it, the proportions of it which go into evaporation, infiltration and runoff, and the biological role of the snow cover.

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SRP glass containing actual radioactive waste was leached in static tests at 90{sup 0}C in a tuffaceous groundwater (J-13 water at pH {similar_to}7.4) at a SA/V ratio of 100m{sup -1} in 316 stainless steel vessels. Tests were performed for time periods up to 134 days. Normalized mass losses were calculated for {sup 137}Cs, {sup 90}Sr, and {sup 238}Pu. The {sup 137}Cs in the leachate appeared to reach a steady value of {similar_to}3 g/m{sup 2}, corresponding to a steady-state concentration of only 1.0 ppB for total cesium. The mass losses based on {sup 90}Sr and {sup 238}Pu appearing in solution were low (<0.3 and <0.01, respectively) because of their low solubilities. However, significant amounts of these radionuclides had deposited on the steel vessel while the amount of deposited {sup 137}Cs was negligible. During the leach tests, the pH changed <0.4 unit and the only significant effect of radiolysis was reduction of NO{sub 3}{sup -} ions in solution to NO{sub 2}{sup -}. When compared to earlier tests, the results confirm that leach rates in the earlier tests with radioactive glass in Teflon vessels were high due to radiolysis of the Teflon. The results also indicate that radioactive and nonradioactive glasses of comparable …

The influence of resistivity on energetic trapped particle-induced internal kink modes, dubbed ''fishbones'' in the literature, explored. A general dispersion relation, which recovers the ideal theory in its appropriate limit, is derived and analyzed. Implications of the theory for present generation fusion devices such as the Joint European Torus are discussed. 8 refs., 2 figs.

This report provides temperature and temperature gradient data for boreholes in Oregon. (ACR)

The First Workshop on Antimatter Physics at Low Energy was held at FNAL last spring, April 10-12, 1986, with the stated purpose of gauging the interest in the physics that would be made possible by adding a variable energy pbar storage and cooling ring to the existing Accumulator at FNAL. The Workshop Proceedings are now published and include a concise collection of papers addressing the physics with pbars below 10 GeV/c that could be made available from the present antiproton source at FNAL. It is worth emphasizing that this is a possible without major impact on the primary mission of the laboratory. Such a facility would include provisions for extracted cooled pbar beams as well as future internal targer and colliding beam experiments. Specific experimental proposals would be facilitated by the existence of a reference design for such a facility. A central effort to produce such a reference design would be the logical next step. they are requesting the opportunity to present to this committee an overview of the physics arguments for such a facility; what we would require from the committee is 'strong encouragement' to proceed with such a reference design leading to a formal proposal. The aid of …

The goals of the project were to: establish fishery rehabilitation objectives for naturally and hatchery produced salmonids in the Umatilla Basin; estimate potential benefits of each of the rehabilitation and flow enhancement projects to naturally and hatchery produced salmonids; and develop a plan to set priorities, implement, and evaluate projects that will achieve rehabilitation objectives. This document identifies fishery needs, quantifies the contribution of proposed fishery projects under present and enhanced flows, provides cost estimates for projects, and provides a plan for prioritization, implementation, and evaluation of projects.

Abstract: On June 24-25, 1985, NBS and IEEE cosponsored a seminar at NBS to examine the need fox improved access to Japanese technical information and to explore possible app. aches to satisfy those needs. To limit the discussion to practical dimensions, the technical subject matter was restricted to electrical and electronics engineering. The program was designed to provide an opportunity for individuals representing Congress, the practicing engineering community, industry, and the educational community to voice their concerns and their needs. This proceedings volume contains selected presentations made at the seminar plus the visual aids used by each speaker.

The IBM 3090 with Vector Facility is an extremely interesting machine because it combines very good scaler performance with enhanced vector and multitasking performance. For many IBM installations with a large scientific workload, the 3090/vector/MTF combination may be an ideal means of increasing throughput at minimum cost. However, neither the vector nor multitasking capabilities are sufficiently developed to make the 3090 competitive with our current worker machines for our large-scale scientific codes.

The basic purpose of the transition program in the operations area was to obtain a detailed understanding of the FMPC operations with emphasis on equipment and organization, Also considered in this evaluation were several extant conditions at FMPC which may have significant impact on initiatives adopted in the operations area. These conditions are as follows: capital expenditures over the last several years averaged less than 20% of what might be considered minimum to sustain such a facility in a good operating condition; the production load is ramping up placing greater demands on an old facility; the workforce is relatively inexperienced (68% with less than five (5) years) at FMPC; plans are in place to institute major upgrading of FMPC facilities; the RFP described the need for a major effort in the Environment, Safety and Health Area. Considering the above concerns, the transition program was focused in the following areas: Procedures - An inexperienced workforce operating in an atmosphere requiring rigid compliance with more rigorous environmental criteria necessitates clear, concise up-to-date procedures to enhance performance; Training - New equipment, new people and rigorous environmental constraints demand an aggressive, focused training program. Equipment - Site conditions are not conducive to reliable equipment …

The bibliography includes all the Utah geothermal references through 1984. Some 1985 citations are listed. Geological, geophysical, and tectonic maps and reports are included if they cover a high-temperature thermal area. The references are indexed geographically either under (1) United States (national studies), (2) regional - western United States or physiographic province, (3) Utah - statewide and regional, or (4) county. Reports concerning a particular hot spring or thermal area are listed under both the thermal area and the county names.

Exploration techniques included the following: (1) a temperature survey of springs, (2) chemical analyses and calculated geothermometer temperatures of water samples collected from selected springs and wells, (3) chemical analyses and calculated geothermometer temperatures of spring and well water samples in the literature, (4) thermal gradients measured in accessible wells, and (5) geology. The highest water temperature recorded in the St. George basin is 42/sup 0/C at Pah Tempe Hot Springs. Additional spring temperatures higher than 20/sup 0/C are at Veyo Hot Spring, Washington hot pot, and Green Spring. The warmest well water in the study area is 40/sup 0/C in Middleton Wash. Additional warm well water (higher than 24.5/sup 0/C) is present north of St. George, north of Washington, southeast of St. George, and in Dameron Valley. The majority of the Na-K-Ca calculated reservoir temperatures range between 30/sup 0/ and 50/sup 0/C. Anomalous geothermometer temperatures were calculated for water from Pah Tempe and a number of locations in St. George and vicinity. In addition to the known thermal areas of Pah Tempe and Veyo Hot Spring, an area north of Washington and St. George is delineated in this study to have possible low-temperature geothermal potential.

An emerging thermal treatment process known as in situ vitrification is being developed to immobilize selected portions of radioactively contaminated soils. The process is a permanent remedial action that destroys solid and liquid organic contaminants and incorporates radionuclides and heavy metals into a glass and crystalline form. The process's flexibility in design and broad capabilities make it potentially adaptable to mixed and chemical wastes, as well. The process consists of an electrical power system for vitrifying contaminated soil, a hood to contain gaseous effluents, an off-gas treatment system, an off-gas cooling system, and a process control station. The process is mounted in three transportable trailers that can be easily moved from site to site. The process is capable of treating contaminated soils at least 13 m deep. The system components are designed to accommodate waste inclusions in the soil such as metals, combustibles, and large voids. Selectively applied to the more troublesome radioactively contaminated soils, in situ vitrification provides a potentially useful and permanent tool for remedial action.