Several authorities govern the daily chamber work of the Senate: its standing rules, standing orders, unanimous consent agreements, precedent, and tradition. Because these authorities have different influence at certain times, no Senate session day is truly typical. This report discusses procedures and business that usually occur every session day, and refers to certain business items that may occur less frequently.

Data on the effects of nuclear fuel burnup on dissolution rates and U losses of a few fuel types are summarized. Burnup to the 40% level produced very little effect on the rate of solution of stainless steel-UO/sub 2/ fuel elements in solutions of the Darex type. Beyond passivation, burnup to the 250 Mwd/T level did not produce a large effect on the rate of decladding nor on the U losses in the Sulfex process. Bunnup to the 15% or 4300 Mwd/T level produced little or no effect on the rate of decladding, U losses, or Pu losses in the Zirflex process. Two other effects, air oxidation of irradiated UO/sub 2/ and prolonged contact of this oxide with Sulfex solutions in the absence of actively dissolving stainless steel appeared to be much more serious sources of loss of U. (auth)

The three-dimensional mechanical behavior of thick Spectra/epoxy sonar window materials containing various special materials is summarized in this report. Three different materials, which were fabricated by two companies known as `A` and `B` were received from the Naval Warfare Center. The three materials designated `A with microspheres (A micron),` `A without microspheres (A),` and `B` were measured for all properties. The total number of tests was reduced through the assumption that the two orthogonal, in-place directions were identical. Consequently, these materials should have only six independent elastic variables. The measured constants and strengths are given.

Engineering Work Requests ESE-48 & 49 established a program for performance of Qualification Approval Tests on RPC`s 0.2 and 40 meghom Carbon Composition Resistors. This report is an accounting of these tests wherein (50) samples of each component were subjected to QA tests per drawings 8O2C250 and 802C251. Tests are explained and results tabulated.

The purpose of this CRADA extension which effectively ended in 2003 was to quantify the effect of iron-sulfide formation on the fouling propensity of crude oil. The specific objectives are focused on fouling of the Crude Distillation Unit (CDU-1) at the Shell Refinery in Mobile, Alabama. The technical approach consists of analyzing the plant data, chemical analysis of crude oil to detect key precursors, performing refinery tests using the Argonne Field Fouling Unit, and verifying the effectiveness of a physical device of tube insert and enhanced tubes to change threshold conditions and thereby reducing fouling.

Nuclear-explosive prompt diagnostics techniques and equipment are surveyed. These techniques and equipment have been developed to answer nuclear-explosive performance questions. The techniques and equipment must be selective in radiation sensitivity, linear in calibration, fast, insensitive to strong signals, wide in dynamic range, and reliable. Diagnostic techniques and equipment measure neutron, gamma-ray, and x-ray emissions, as well as aid in the determination of the physical location of the production of radiation through imaging. The high cost of nuclear experiments will continue to encourage the development of sophisticated techniques to gain as much information as possible from each experiment.

The report discusses the issues regarding the Homeland Security Act of 2002 (P.L. 107-296, 116 Stat. 2135), which contains provisions to arm pilots of passenger aircraft and gives deputized pilots the authority to use force, including lethal force, to defend the flight deck against criminal and terrorist threats. The report includes the legislative Background, implementation issues, equipment, training, operational procedures and costs.

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The in-line monitoring instruments installed in the Redox plant in the late 1950s consisted of six gamma monitors, a single channel gamma spectrometer, an alpha monitor, and a neutron counter. A gamma monitor on the steam condensate outlet line and a uranium monitor on the 2DFS stream were to be added at a later date. The first section of this information manual describes the in-line gamma monitors and gives operating instructions for them. The second section covers the alpha monitor, and the third section the neutron counter. Sections on the uranium monitor and the steam header gamma monitor were to be added at a later date.

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In a previous study the trimer of rhenium tetracarbonyl was found to be diamagnetic, suggesting the presence of hydrogen in the compound. This was supported by chemical analysis, which indicated about one hydrogen per rhenium, and the compound was formulated as [Re(C0)4H] 3• Subsequently a proton resonance was observed on a broad line spectrometer. In the original work the infrared spectra were compared for the hydride and deuteride; cyclohexane solutions were used for the CO stretching region and KBr discs were used for the rest of the spectrum. Surprisingly, the spectra of the hydride and deuteride showed only minor differences, insufficient to confirm the presence of hydrogen. No evidence of a hydrogen stretching frequency was found. In the present work, the previously unobserved Raman spectra were measured for the hydride and deuteride . In the solid state ratber striking shifts were observed in the CO stretching region. Also there is some evidence for a metal-hydrogen stretching band at the rather low frequency of 1100 cm-1. In an attempt to support the interpretation of the Raman spectra more detailed infrared studies of the solid in KBr discs were made. The hope was to observe a metal-hydrogen stretching frequency and to explain …

This report presents difficult-to-find statistics regarding U.S. military casualties in Operation Iraqi Freedom (OIF) and Operation Enduring Freedom (OEF, Afghanistan), including those concerning medical evacuations, amputations, and the demographics of casualties.

To evaluate the crudding characteristics of ammonium hydroxide conditioned coolant it is necessary to use a thermocouple element. The present design has accentuated structural integrity, reliability and constant heat flux. A radical departure from past designs was made by selecting a stainless steel cladding and enriched ceramic fuel. Three thermocouples are inserted in the cladding to increase the reliability. By the use of two thermocouple elements it will be possible to obtain important preliminary information on preferential crud deposition while simultaneously evaluating the crudding characteristics of ammonium hydroxide conditioned coolant.

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This report provides an overview of key environmental issues that are receiving or may receive attention in the 109th Congress. The sections on specific issues contain references to more detailed and extensive CRS reports on the subjects covered.

This manual is a general resource tool to assist EMSL users and Laboratory staff within EMSL locate official policy, practice and subject matter experts. It is not intended to replace or amend any formal Battelle policy or practice. Users of this manual should rely only on Battelle’s Standard Based Management System (SBMS) for official policy. No contractual commitment or right of any kind is created by this manual. Battelle management reserves the right to alter, change, or delete any information contained within this manual without prior notice.

A performance assessment is required to demonstrate compliance with the post-closure performance objectives for the Yucca Mountain Project (YMP), as stated in 10 CFR Part 63.1 13 (66 FR 55732, p. 55807). A performance assessment is defined in 10 CFR 63.2 (66 FR 55732, p. 55794) as an analysis that: (1) identifies the features, events, and processes (FEPs) that might affect the potential geologic repository; (2) examines the effects of those FEPs upon the performance of the potential geologic repository; and (3) estimates the expected dose incurred by a specified reasonably maximally exposed individual as a result of releases caused by significant FEPs. The performance assessment must also provide the technical basis for inclusion or exclusion of specific FEPs in the performance assessment as stated in 10 CFR 63.114 (66 FR 55732, p. 55807). An initial approach for FEP development, in support of the Total System Performance Assessment for the Site Recommendation (TSPA-SR) (CRWMS M&O 2000e), was documented in Freeze et al. (2001). The development of a comprehensive list of FEPs potentially relevant to the post-closure performance of the potential Yucca Mountain repository is an ongoing, iterative process based on site-specific information, design, and regulations. Although comprehensiveness of the FEPs …

This report describes the use of noise analysis to investigate in-core instrument tube vibrations in BWR-4 reactors. Neutron noise signals from in-core fission chambers and acoustic noise signals from externally mounted accelerometers were used in these studies. The results show that neutron noise can be used to detect vibration and, more importantly, impacting of instrument tubes against adjacent fuel channel boxes. Externally mounted accelerometers detect impacting but not rubbing of instrument tubes against fuel channel boxes. Accelerometers can monitor impacting only on the particular instrument tube where the accelerometer is mounted. Surveillance for instrument tube impacts can be accomplished using standard BWR-4 in-core power range neutron flux detectors at all instrument tube locations containing these detectors. Ex-vessel accelerometers can then be used to monitor instrument tubes that lack power range neutron flux detectors. However, noise on axial flux profiles obtained with movable in-core detectors is not a reliable indicator of impacting, because the recorder used to plot the flux profiles does not respond adequately to the noise frequency generated by impacting.

This report discusses the federal law regarding marijuana that is classified as a Schedule I Controlled Substance. The federal Controlled Substances Act (CSA) outlaws the possession, cultivation, or distribution of marijuana except for authorized research.

This report discusses state medical marijuana laws that grants registered patients, their doctors, and providers immunity from the consequences of state law.

New computational physics methods for estimating constitutive property parameterizations in ground water aquifers were developed and demonstrated in this project. The dynamical and statistical axioms of physics, embodied in partial differential equations (PDES) of kinetic theory, are employed to constrain interpolations of hydraulic head (pressure) and transmissivity (permeability) between sparsely measured datum points. These methods can apparently be applied in numerous approaches to parameter estimation. To demonstrate the basic concepts and techniques developed in this work, examples are considered for steady-state, two-dimensional, heterogeneous, ground water flow models, given (i) discrete borehole observations of hydraulic head and transmissivity and (ii) governing kinetic equations for Darcy flow behavior. Estimations of spatially dependent parameters from sparsely measured data are treated as mathematically ill- posed problems because infinitely many parameter distributions (realizations) that are consistent with the data generally exist. Potential difficulties associated with ill-posedness in mean flow realizations are mitigated by requiring that acceptable realizations respect the observed data, are solutions of forward and inverse PDEs for physical continuity, respect information sampling principles, and are distributed by spatial interpolations that themselves are optimal solutions of the governing PDEs between measured datum points. To accomplish these requisites, adaptive numerical grid Galerkin techniques were applied …

The Graphite Isotope Ratio Method (GIRM) is a technique used to estimate the total plutonium production in a graphite-moderated reactor. The cumulative plutonium production in that reactor can be accurately determined by measuring neutron irradiation induced isotopic ratio changes in certain impurity elements within the graphite moderator. The method does not require detailed knowledge of a reactor's operating history, although that knowledge can decrease the uncertainty of the production estimate. The basic premise of the Graphite Isotope Ratio Method is that the fluence in non-fuel core components is directly related to the cumulative plutonium production in the nuclear fuel.

Methods and algorithms are developed to enable the accurate analysis of problems that exhibit interacting physical processes with uncertainties. These uncertainties can pertain either to each of the physical processes or to the manner in which they depend on each others. These problems are cast within a polynomial chaos framework and their solution then involves either solving a large system of algebraic equations or a high dimensional numerical quadrature. In both cases, the curse of dimensionality is manifested. Procedures are developed for the efficient evaluation of the resulting linear equations that advantage of the block sparse structure of these equations, resulting in a block recursive Schur complement construction. In addition, embedded quadratures are constructed that permit the evaluation of very high-dimensional integrals using low-dimensional quadratures adapted to particular quantities of interest. The low-dimensional integration is carried out in a transformed measure space in which the quantity of interest is low-dimensional. Finally, a procedure is also developed to discover a low-dimensional manifold, embedded in the initial high-dimensional one, in which scalar quantities of interest exist. This approach permits the functional expression of the reduced space in terms of the original space, thus permitting cross-scale sensitivity analysis.