An addition is presented for the IBM-7090 program MURGATROYD to produce a rough graph of reactor power versus time. A sample of output is included for the case given as an example. (J.R.D.)

Reports and articles on decommissioning have been reviewed to determine the current technology status and also attempt to identify potential decommissioning problem areas. It is concluded that technological road blocks, which limited decommissioning facilities in the past have been removed. In general, techniques developed by maintenance in maintaining the facility have been used to decommission facilities. Some of the more promising development underway which will further simplify decommissioning activities are: electrolytic decontamination which simplifies some decontaminating operations; arc saw and vacuum furnace which reduce the volume of metallic contaminated material by a factor of 10; remotely operated plasma torch which reduces personnel exposure; and shaped charges, water cannon and rock splitters which simplify concrete removal. Areas in which published data are limited are detailed costs identifying various components included in the total cost and also the quantity of waste generated during the decommissioning activities. With the increased awareness of decommissioning requirements as specified by licensing requirements, design criteria for new facilities are taking into consideration final decommissioning of buildings. Specific building design features will evolve as designs are evaluated and implemented.

Calculations are presented which show that the reactivity effect of flooding and unflooding the fast superheating section of the Mixed Spectrum Superheater can be made small by the addition of epithermal poisons to the superheater. The reactivity effects of flooding superheater sections ranging in size from 1.25 to 3.5 ft cubes and containing U/sup 23/5/sup >/oxide or Pu/sup 239/ oxide fuel and various amounts o f the epithermal poison europium were calculated. Reactivity changes during several postulated flooding processes are given. Methods for deterthination of fissile and fertile material and poison cross sections in the resonance- region are discussed. (auth)

This report provides a top level functional description and design for the development and implementation of the central network to support the next generation of SNL, Albuquerque supercomputer in a UNIX{reg sign} environment. It describes the network functions and provides an architecture and topology.

The first phase of the Hualapai Tribal Utility Development Project (Project) studied the feasibility of establishing a tribally operated utility to provide electric service to tribal customers at Grand Canyon West (see objective 1 below). The project was successful in completing the analysis of the energy production from the solar power systems at Grand Canyon West and developing a financial model, based on rates to be charged to Grand Canyon West customers connected to the solar systems, that would provide sufficient revenue for a Tribal Utility Authority to operate and maintain those systems. The objective to establish a central power grid over which the TUA would have authority and responsibility had to be modified because the construction schedule of GCW facilities, specifically the new air terminal, did not match up with the construction schedule for the solar power system. Therefore, two distributed systems were constructed instead of one central system with a high voltage distribution network. The Hualapai Tribal Council has not taken the action necessary to establish the Tribal Utility Authority that could be responsible for the electric service at GCW. The creation of a Tribal Utility Authority (TUA) was the subject of the second objective of the project. …

Oak Ridge Institute for Science and Education (ORISE) conducted independent verification radiological survey activities at Argonne National Laboratory’s Building 315, Zero Power Reactor-6 facility in Argonne, Illinois. Independent verification survey activities included document and data reviews, alpha plus beta and gamma surface scans, alpha and beta surface activity measurements, and instrumentation comparisons. An interim letter report and a draft report, documenting the verification survey findings, were submitted to the DOE on November 8, 2006 and February 22, 2007, respectively (ORISE 2006b and 2007).

Despite their great importance in low-temperaturegeochemistry, self-diffusion coefficients of noble gas isotopes in liquidwater (D) have been measured only for the major isotopes of helium, neon,krypton and xenon. Data on the self-diffusion coefficients of minor noblegas isotopes are essentially non-existent and so typically are estimatedby a kinetic theory model in which D varies as the inverse square root ofthe isotopic mass (m): D proportional to m-0.5. To examine the validityof the kinetic theory model, we performed molecular dynamics (MD)simulations of the diffusion of noble gases in ambient liquid water withan accurate set of noble gas-water interaction potentials. Our simulationresults agree with available experimental data on the solvation structureand self-diffusion coefficients of the major noble gas isotopes in liquidwater and reveal for the first time that the isotopic mass-dependence ofall noble gas self-diffusion coefficients has the power-law form Dproportional to m-beta with 0<beta<0.2. Thus our results callinto serious question the widespread assumption that the square rootmodel can be applied to estimate the kinetic fractionation of noble gasisotopes caused by diffusion in ambient liquid water.

The program scope was to affect the heat input and the resultant weld bead geometry by synchronizing robotic weave cycles with desired pulsed waveform shapes to develop process parameters relationships and optimized pulsed gas metal arc welding processes for welding fatique-critical structures of steel, high strength steel, and aluminum. Quality would be addressed by developing intelligent methods of weld measurement that accurately predict weld bead geometry from process information. This program was severely underfunded, and eventually terminated. The scope was redirected to investigate tandem narrow groove welding of steel butt joints during the one year of partial funding. A torch was designed and configured to perform a design of experiments of steel butt weld joints that validated the feasability of the process. An initial cost model estimated a 60% cost savings over conventional groove welding by eliminating the joint preparation and reducing the weld volume needed.

The radioactive amino acid's synthesized from C{sup 14}O{sub 2} by green algae both in the light and in the dark after CO{sub 2}-free preillumination have been separated and identified using paper chromatography and radioautography. The radioactive amino acids identified were aspartic acid, alanine and smaller amounts of 3- and 4-carbon amino acids. This finding as well as the total absence of radioactive glutamic acid substantiates the mechanism for reduction of CO{sub 2} previously postulated by members of this laboratory.

In this CRADA, Oak Ridge National Laboratory (ORNL) assisted RIS Corporation of Knoxville, TN, in the development of graphical environment tools for the development and programming of high speed real-time algorithms to be implemented in a Field-Programmable Gate Array (FPGA). The primary application was intended to be digital signal processing for gamma-ray spectroscopy, in particular for Gamma-Ray Energy Tracking Arrays such as the GRETINA project. Key components of this work included assembling an evaluation platform to verify designs on actual hardware, and creating various types of Simulink functional blocks for peak-shaping and constant-fraction discrimination.

This report, sponsored the Army's Energy Engineering Analysis Program, provides the Operations and Maintenance (O&M) Energy manager and practitioner with useful information about the top O&M opportunities consistently found across the DoD/Army sector. The target is to help the DoD/Army sector develop a well-structured and organized O&M program.

CBP-Tech Note-345 (July 2005), devoted to a study of microbunching instability in FERMI@ELETTRA linac quotes '...the above analysis shows that the most of the gain in microbunching instability occurs after BC2, i.e. after transformation of the energy modulation to the spatial modulation that takes place in BC2. It is possible to avoid that if we use only BC1 for all our needs for bunch compression. There are also additional advantages for a mitigation of the microbunching instability related to that. First, we would need to increase R56 in BC1 (for given energy chirp in the electron beam). Second, a relative energy spread is significantly larger at BC1 than at BC2. Both these factors would contribute to instability suppression due to increased Landau damping effect.' One additional argument was however missed in that report. Instability smearing due to finite emittance is stronger in BC1 simply because the geometrical emittance is larger than in BC2. In spite of the considerations in favor of a lattice with one-stage compressor, it was thought at the time that the two bunch compressors configuration was still preferable as it appeared difficult to obtain a flat-flat distribution at the end of the linac with only one bunch …

Recent studies have shown geothermal power plants to have a significant environmental impact on the ground water of the area. The heavy metals arsenic and mercury are special problems, as both are concentrated by flora and fauna exposed to the effluent waters. Because the toxicity of these and other metallic pollutants present in geothermal effluent depends on the chemical form, or speciation, of the particular metal, any serious study of the environmental impact of a geothermal development should include studies of trace metal speciation, in addition to trace metal concentration. This proposal details a method for determining metal speciation in dilute waters. The method is based on ion-exchange and backed by atomic absorption spectrometry and multiple scanning anodic stripping voltammetry. Special laboratory studies will be performed on mercury, arsenic and selenium speciation in synthetic geothermal water. The method will be applied to three known geothermal areas in Washington and Oregon, with emphasis on the speciation of mercury, arsenic and selenium in these waters. The computer controlled electrochemical instrumentation was built and tested. Using this instrumentation, a new experimental procedure was developed to determine the chemical form (speciation) of metal ions in very dilute solutions (ng/ml). This method was tested on …

The traditional approach used to study high energy beam propagation relies on the frozen field approximation. A minor modification of the frozen field approximation yields the set of equations applied to the analysis of the hose instability. These models are constrasted with the Darwin field approximation. A statement is made of the Darwin model equations relevant to the analysis of the hose instability.

The concept of a Super Fixed Target Beauty Facility (SFT) which uses a relatively low intensity 20 TeV proton beam as a generator of very high momenta B's is an exciting prospect which is very competitive with other B factory ideas. The yields of B's in such a facility are quite high (3 {times} 10{sup 10} {yields} 10{sup 11} B's per year). At this level of statistics, CP violation measurements will be possible in many modes. In addition, the fixed target configuration, because of the high momenta of the produced B's and the resulting long decay lengths, facilitates the detection and reconstruction of B's and offers unique opportunities for observation of the B decays. The limited solid angle coverage required for the fixed target spectrometer makes the cost of the facility much cheaper than other e{sup +}e{sup {minus}} or hadron collider options under consideration. The relatively low intensity 20 TeV beam (1 {yields} 2 {times} 10{sup 8} protons/second) needed for the SFT makes it possible to consider an extraction system which operates concurrently and in a non-interfering manner with the other collider experiments. One possible method for generating such a beam, crystal channeling, is discussed.

A calculation of the cross section for e/sup +/e/sup -/ ..-->.. ..mu../sup +/..mu../sup -/ interactions is performed assuming colliding beam conditions and propagation of a neutral intermediate vector boson. From this a derivation of the expression for the longitudinal polarization of the final state ..mu../sup -/ is made. The calculation, using relativistic, weak interaction, and field theory, demonstrates the connection between the polarization and the weak force parameters explicity. (JFP)

The radial-outflow reaction turbine, a pure-reaction turbine designed to improve the conversion efficiency of geothermal energy into electrical power is described. It also has potential as a total-flow turbine for low-temperature water. The principle of incomplete expansion can be used to obtain a reduction in turbine size when the turbine exhausts into a low-pressure condenser. And, by adding this turbine to single- and two-stage flashed-steam systems, the conversion efficiency of systems utilizing low- and high-energy wellhead sources, respectively can be improved. The Appendix outlines the analysis of the radial-outflow reaction turbine and leads to an expression for engine efficiency.

Nineteen-day-old dwarf sunflower plants (Helianthus annuus, variety NK894) received a variable dose (0-40 Gy) from a cobalt-60 gamma source. A very sensitive stem monitoring device, developed at Battelle's Pacific Northwest Laboratories, Richland, Washington was used to measure real-time changes in stem diameter. Exposure of plants caused a significant reduction in stem growth and root biomass. Doses as low as 5 Gy resulted in a significant increase in leaf density, suggesting that nonreversible morphological growth changes could be induced by very low doses of radiation. Carbohydrate analysis of 40-Gy irradiated plants demonstrated significantly more starch content in leaves and significantly less starch content in stems 18 days after exposure than did control plants. In contrast, the carbohydrate content in roots of 40-Gy irradiated plants were not significantly different from unirradiated plants 18 days after exposure. These results indicate that radiation either decreased phloem transport or reduced the availability of sugar reducing enzymes in irradiated plants. 44 refs., 12 figs.

The EMPACT experiment utilizes a broad approach to maximize its discovery potential for new phenomena accessible at the SSC. The high resolution detector has a balances emphasis on, and large acceptance for, electrons, muons, jets, and noninteracting particles, and is capable of utilizing the ultimate luminosity of the SSC. The detector emphasizes excellent calorimetry augmented by TRD tracking, and employs an innovative system of superconducting air core toroids for muon measurements. Significant engineering effort has established the feasibility of a baseline detector concept and has addressed the related issues of support facilities, assembly, and detector integration. The design has been tested against the challenges of predicted phenomena, with the expectation that this will optimize the capacity for observing the unexpected. EMPACT's international collaboration has unprecedented support from major aerospace industries who are providing tools and expertise for project design and integration, which will assure that a detector optimized for performance and cost will be available for the first collisions at the new laboratory.

As part of the overall Solvent Refined Coal (SRC-1) project baseline being prepared by International Coal Refining Company (ICRC), the RUST Engineering Company is providing necessary input for the Outside Battery Limits (OSBL) Facilities. The project baseline is comprised of: design baseline - technical definition of work; schedule baseline - detailed and management level 1 schedules; and cost baseline - estimates and cost/manpower plan. The design baseline (technical definition) for the OSBL Facilities has been completed and is presented in Volumes I, II, III, IV, V and VI. The OSBL technical definition is based on, and compatible with, the ICRC defined statement of work, design basis memorandum, master project procedures, process and mechanical design criteria, and baseline guidance documents. The design basis memorandum is included in Paragraph 1.3 of Volume I. The baseline design data is presented in 6 volumes. Volume I contains the introduction section and utility systems data through steam and feedwater. Volume II continues with utility systems data through fuel system, and contains the interconnecting systems and utility system integration information. Volume III contains the offsites data through water and waste treatment. Volume IV continues with offsites data, including site development and buildings, and contains raw materials …

Volume III contains information on: water treatment (potable, process and waste water) and waste solids handling. (LTN)

It was demonstrated that the modified version of the Martin flowsheet can produce SrF/sub 2/ of acceptable quality using a simulated feed of the same composition as the anticipated packaging plant feed. By careful control of operating conditions, strontium losses in the process can be reduced to an acceptable level. Using a nonrepresentative radioactive feed (which contained impurities not present in the simulated feed) high strontium losses were encountered in the feed purification step, although the purification obtained was excellent. The other steps in the process presented no difficulties. Additional tests of the feed purification step will be necessary when a representative feed is available to ensure that strontium losses can be reduced to an acceptable level. The proposed flowsheet differs from the Martin flowsheet in that a feed purification step is used in the proposed process. All the remaining steps in the process are essentially identical and the data and recommendations reported in the Martin publications appear applicable to the proposed process. Based on the results of this study (and including data published by the Martin Company), a detailed flowsheet with recommended operating conditions is given.

Volume 2 contains flowsheets and equipment specifications for the following parts of the plant: cooling water systems, process water supply, potable water supply, nitrogen system, compressed air system, flares, incinerators, fuels and interconnecting systems (pipes). The instrumentation requirements are included. (LTN)

This report is a supplement to a tabulation of the thermodynamic and phase data for the 100 binary systems of Mo with the elements from H to Lr. The calculations of thermodynamic data and phase equilibria were carried out from 5000/sup 0/K to low temperatures. This report presents the methods of calculation used. The thermodynamics involved is rather straightforward and the reader is referred to any advanced thermodynamic text. The calculations were largely carried out using an HP-65 programmable calculator. In this report, those programs are reformulated for use with the HP-67 calculator; great reduction in the number of programs required to carry out the calculation results.