This note is a compilation of comments on the limitations on the Main Ring cycle time, and multi-batch operation of the Main Ring. The first page is a summary of three talks given in january 1986 by the authors about limitations to Main Ring cycle rates and the possibilities for multi-batch targeting schemes. Following this is a writeup by Stan pruss on the Main Ring cycle time limitations. This is followed in turn by some comments by G. Dugan on the general topic, from the pbar Source perspective. The basic conclusions of the talks are: (1) The main ring should be able to ramp to 120 GeV with a cycle time of less than 2.15 sec, with existing hardware. The principal limits are due to voltage limitations on the MR power supplies, both on the upgramp and on invert, and RF bucket area limitations. The magnet cooling is adequate to run at 120 GeV DC. (2) Bunch narrowing techniques for multiple batch operation, with up to 4 batches on flat top, is possible with the existing hardware and results in a very small ({approx} 3%) longitudinal emittance dilution per batch. This conclusion does not include the effects of instabilities, if …

The materials and properties investigated for this blanket study are listed. The phenomenological equations and mathematical fits for all materials and properties considered are given. Efforts to develop a swelling equation based on the few experimental data points available for breeder materials are described. The sintering phenomena for ceramics is investigated.

In an exposure of the SLAC Hybrid Facility (SHF) to a backward scattered laser beam, 136 charm events produced in ..gamma..p interactions at 20 GeV have been observed. The SHF 1 m bubble chamber was equipped with a High Resolution Optics camera in order to detect directly the production and decay of charm particles. After imposing rigorous cuts, 48 charged, 50 neutral, and 2 topologically ambiguous decays remain. Using a novel method for estimating the momentum of unconstrained decays, the D meson lifetimes from this sample are measured to be tau/sub D sup +-/ = (8.6 +- 1.3/sub -0.3//sup +0.8/) x 10/sup -13/ sec and tau/sub D/sup 0// = (6.1 +- 0.9 +- 0.3) x 10/sup -13/ sec with a ratio of R = tau/sub D sup +-//tau/sub D/sup 0// = (1.4 +- 0.3/sub -0.1//sup +0.2/). This value of R indicates the Spectator Model charm particle decay mechanism is the dominate piece in the D/sub +-/ and D/sup 0/ decay rates. Limits are placed on additional contributions to the D decay rates from other processes including W-Exchange, Final State Interactions, and Pauli Principle Interference. 34 refs., 41 figs.

An experiment was carried out to observe microwave signals of the bunched beam in the Fermilab Main Ring. The purpose of this paper is to analyze the experiment and attempt a computation of the longitudinal impedance per unit harmonic Z/n of the Main Ring. The result of the analysis indicates Z/n = 8.6 ..cap omega.. if the driving impedance is a broad band at f/sub MW/ = 1.646 GHz. However, if the driving impedance is a high-Q resonance at 1.646 GHz with RMS width less than approx.0.13 GHz (or Q approx. 50), Z/sub sh//Q of the resonance is 5.2 k..cap omega... We demonstrate that the proton bunches are of Gaussian shape. The time at which the microwave amplitude starts to grow is determined. We find that this occurs when two adjacent bunches overlap each other. A stability criterion is derived for the overlapped bunches. Then Z/n and Z/sub sh//Q are computed. The source of the driving impedance is traced.

A microcanonical simulation is formulated of the disassembly of a finite nuclear system into individually excitable and mutually interacting nuclear fragments. Illustrative results are presented. 7 refs.

Hydrophobic or floatable materials released to the water column during dredge disposal operations may accumulate in high concentrations on the water surface. If such surface accumulations occur, they could impact the reproduction of fish and shellfish with neustonic (floating) eggs or larvae. Also, floatable surface contaminants could deposit on nearby beaches. In order to examine the potential impacts of such processes, an interactive computer (IBM PC) model was developed. The FORTRAN model allows input of contaminant concentrations on the dredge material, the surface area of the disposal site, the floatable fraction of the contaminated material, and the baseline concentrations of contaminants present in the sea-surface microlayer. The model then computes the resultant concentrations of each contaminant in the microlayer and the potential impact on floating fish eggs. The utility of the model would be greatly improved by empirical data, not yeat available, on the vertical upward and lateral movement of contaminants during dredge material disposal.

We present a simple model which may be used to evaluate the suitability of different ions for rapid plasma cooling by line radiation in recombination pumped x-ray laser schemes.

The use of solid breeders in blanket components of fusion reactors is necessitated by the need for tritium breeding, with avoidance of problems arising from liquid metal breeders; such as corrosion and MHD pressure drop. The material 9-C (low activation equivalent of HT-9) is used for the outside structure of the module, as well as for solid breeder pin cladding. The first wall is cooled with high velocity helium through coolant channels, while the pins are cooled by helium in a cross-flow configuration. The first zone is made up entirely of beryllium pins for neutron breeding, and then two solid breeder zones follow. In order to minimize maintenance time, a satisfactory configuration has to withstand transient phenomena associated with power-ramps and shutdowns while giving optimal thermomechanical performance in reasonable lifetime. These objectives can be reached by selecting suitable geometry and material specifications as well as prescribed temperature histories. Finding the minimal allowable ramp rate for startup is important from the economy of the operation, since overly conservative startup can amount to substantial percentage of the power cycle. In the stage of preliminary design the main concern is failure of the cladding due to high stresses or large total strains. The …

This study supplements a larger study of a solid breeder blanket design featuring lithium ceramic pins. This aspect of the study looks at tritium transport, release, and inventory within this blanket design. Li/sub 2/O and ..gamma..-LiAlO/sub 2/ are the two primary candidates for ceramic solid breeders. ..gamma..-LiAlO/sub 2/ was chosen for this blanket design due to its higher structural stability. Analysis of tritium behavior in solid breeder blankets is of great importance due to its impact on several critical issues: the generation of an adequate amount of fusion fuel, the safety-related issue of keeping radioactive blanket inventories as low as possible, and the release, purge, and economical processing of the bred tritium without undue contamination of the coolant and other reactor structures.

This volume contains reports on habitat improvement and fisheries enhancement projects conducted in the following subbasins: (1) Clackamas River; (2) Hood River; :(3) Deschutes River; (4) John Day River; (5) Umatilla River; and (6) Grande Ronde River. (ACR)

Cross sections have been measured from 100 eV to 1 MeV by the neutron-time-of-flight technique. The capture events were recorded by detecting the prompt gamma-ray cascade with two C/sub 6/D/sub 6/ scintillators, and were normalized to standard gold cross sections. The background was determined experimentally by utilizing the ''black resonance'' technique. A /sup 6/Li-glass scintillator was used to monitor the neutron flux. A Maxwellian-averaged capture cross section at kT = 30 keV of 74 +- 3 mb for /sup 86/Sr, and 102 +- 4 mb for /sup 87/Sr. (LEW)

In this report, a pressurized lobular blanket configuration is neutronically optimized. Among the features of this blanket configuration are the use of beryllium and LiAlO/sub 2/ solid breeder pins in a cross-flow configuration in a helium coolant. One-dimensional neutronic optimization calculations are performed to maximize the tritium breeding ratio (TER). The procedure involves spatial allocations of Be, LiAlO/sub 2/, 9-C (ferritic steel), and He; in such a way as to maximize the TBR subject to several material, engineering and geometrical constraints. A TBR of 1.17 is achieved for a relatively thin blanket (approx. = 43 cm depth), and consistency with all imposed constraints.

We have measured the temperature of the cosmic background radiation (CBR) at 3.3 mm wavelength in 1982, 1983, and 1984 as part of a larger project to determine the CBR temperature at five wavelengths from 12 cm to 3.3 mm (Smoot et al. 1985). The 3.3-mm measurements yield a brightness temperature of 2.57 K with a 1{sigma} uncertainty of 20.12 K. This paper describes the instrument, the measurement techniques, and the data-analysis procedures used. Our result is in good agreement with recent measurements at comparable wavelengths by Meyer and Jura (1985) and by Peterson, Richards, and Timusk (1985), but it disagrees with the temperatures reported by Woody and Richards (1981).

This work describes the development and application of selective excitation techniques in Nuclear Magnetic Resonance. Composite pulses and multiple-quantum methods are used to accomplish various goals, such as broadband and narrowband excitation in liquids, and collective excitation of groups of spins in solids. These methods are applied to a variety of problems, including non-invasive spatial localization, spin cluster size characterization in disordered solids and solid state NMR imaging.

Charge-dependent convective impurity transport is observed in the central core of PBX H-mode discharges by measuring radial profiles for both low- and high-Z intrinsic impurities in the presence of strong sawtooth activity. Transport coefficients are derived by simulating the data with a diffusive/convective transport model which includes an internal disruption model. The time evolving Z/sub eff/ profile and central metallic densities are fitted during the quiescent phase between internal disruptions to yield a diffusion coefficient of D = 1 x 10/sup 3/ cm/sup 2//s for all species and an inward convective speed of v = 2.2 x 10/sup 2/ (r/a) cm/s for oxygen and carbon and v = 1.1 x 10/sup 3/ (r/a) cm/s for metals. These transport coefficients are in quantitative agreement with simple cylindrical neoclassical estimates for the region within q less than or equal to 1. 17 refs., 4 figs.

Since 1957, evaluations of offsite impacts from each year of operation have been summarized in publicly available, annual environmental reports. These evaluations included estimates of potential radiation exposure to members of the public, either in terms of percentages of the then permissible limits or in terms of radiation dose. The estimated potential radiation doses to maximally exposed individuals from each year of Hanford operations are summarized in a series of tables and figures. The applicable standard for radiation dose to an individual for whom the maximum exposure was estimated is also shown. Although the estimates address potential radiation doses to the public from each year of operations at Hanford between 1957 and 1984, their sum will not produce an accurate estimate of doses accumulated over this time period. The estimates were the best evaluations available at the time to assess potential dose from the current year of operation as well as from any radionuclides still present in the environment from previous years of operation. There was a constant striving for improved evaluation of the potential radiation doses received by members of the public, and as a result the methods and assumptions used to estimate doses were periodically modified to add …

The method of ''multiple interacting continua'' is based on the assumption that changes in thermodynamic conditions of rock matrix blocks are primarily controlled by the distance from the nearest fracture. The accuracy of this assumption was evaluated for regularly shaped (cubic and rectangular) rock blocks with uniform initial conditions, which are subjected to a step change in boundary conditions on the surface. Our results show that pressures (or temperatures) predicted from the MINC approximation may deviate from the exact solutions by as much as 10 to 15% at certain points within the blocks. However, when fluid (or heat) flow rates are integrated over the entire block surface, MINC-approximation and exact solution agree to better than 1%. This indicates that the MINC approximation can accurately represent transient inter-porosity flow in fractured porous media, provided that matrix blocks are indeed subjected to nearly uniform boundary conditions at all times.

The progress of the project objectives are given in this report. The project objectives are: (1) enhancement of the natural spawning summer steelhead run in the Umatilla River Drainage; (2) establishment of a hatchery produced summer steelhead run in the Umatilla River; (3) protect the Confederated Tribes right to fish as reserved by the Treat of 1855 with the US Government; (4) enhance Indian and non-Indian fishing opportunities within the Umatilla River System; (5) demonstration of low-tech, low-cost acclimation facilities in conjunction with off-site hatchery production for rehabilitation of anadromous salmonid populations; and (6) partial mitigation for the impact of federal hydroelectric projects on the Umatilla River fisheries.

Various fundamental topics are considered which underlie the design and use of optical systems for synchrotron radiation. The point of view of linear system theory is chosen which acts as a unifying concept throughout the series. In this context the important optical quantities usually appear as either impulse response functions (Green's functions) or frequency transfer functions (Fourier Transforms of the Green's functions). Topics include the damped harmonic oscillator, free-space optical field propagation, optical properties of materials, dispersion, and the Kramers-Kronig relations.

The process of reflection of VUV and x-radiation is summarized. The functions of mirrors in synchrotron beamlines are described, which include deflection, filtration, power absorption, formation of a real image, focusing, and collimation. Fabrication of optical surfaces for synchrotron radiation beamlines are described, and include polishing of a near spherical surface as well as bending a cylindrical surface to toroidal shape. The imperfections present in mirrors, aberrations and surface figure inaccuracy, are discussed. Calculation of the thermal load of a mirror in a synchrotron radiation beam and the cooling of the mirror are covered briefly. 50 refs., 7 figs. (LEW)

General properties of monochromators are discussed, and some useful formulas for optical design are given. The discussion is limited to the Rowland reflection grating. Topics covered include focussing properties of a toroidal grating, aberrations, dispersion, resolution, and phase space acceptance. (LEW)

Double output cavities have been used experimentally to increase the efficiency of high-power klystrons. We have used particle-in-cell simulations with the 2 + 1/2 dimensional code MASK to optimize the design of double output cavities for the lasertron under development at SLAC. We discuss design considerations for double output cavities (e.g., optimum choice of voltages and phases, efficiency, wall interception, breakdown). We describe how one calculates the cavity impedance matrix from the gap voltages and phases. Some results of the effect of varying voltage, perveance, and pulse are reported.

This document describes the monitoring schedules and methods used to measure ambient radon concentrations around Uranium Mill Tailings Remedial Action (UMTRA) Project sites. Radon monitoring at both processing sites and disposal sites is performed primarily for two reasons. The first, and foremost, of these is to provide a means to keep the off-site radon concentrations during the construction activities As Low As Reasonably Achievable (ALARA). The second purpose is to provide a basis for comparison with the EPA standards developed for the UMTRA Project. Radon monitoring data are also used to demonstrate compliance with ambient concentration standards and for public information due to concern about potential radiation releases during construction. 1 fig., 1 tab.

This report summarizes progress on OHER biomedical and health-effects research conducted at PNL in FY 1985 to develop information for a comprehensive understanding of the interaction of energy-related radiation and chemicals with man. Our continuing emphasis on decreasing the uncertainty of health-effects risk estimates to man from existing and/or developing energy-related technologies supports the DOE goal of increasing and diversifying national energy resources and decreasing risks to human health. The report is arranged to reflect the PNL research relative to OHER programmatic needs. The first section concerns evaluation of possible health effects among nuclear workers. The next two sections, which contain reports of health-effects research in biological systems, include health effects of radiation and health effects of chemical mixtures. The last section is related to medical applications of nuclear technology.