A preliminary point design for an 11.4 GHz power source for a 1 TeV center-of-mass Next Linear Collider (NLC) based on the Relativistic-Klystron Two-Beam-Accelerator (RK-TBA) concept is presented. The present report is the result of a joint LBL-LLNL systems study. consisting of three major thrust areas: physics, engineering, and costing. The new RK-TBA point design, together with our findings in each of these areas, are reported.

Modify Hughes x-band radar for airborne implementation. Upgrade to polarimetry, high-power, and add SLAR mode. Deploy in UK/US field experiments as needed.

The ultimate goal of this project is to develop novel processes for making the conversion of coal into distillable liquids competitive to that of petroleum products in the range of $25/bbl. The objectives of Phase 1 were to determine the utility of new precursors to highly dispersed catalysts for use of syngas atmospheres in coal liquefaction, and to estimate the effect of such implementation on the cost of the final product. The project is divided into three technical tasks. Tasks 1 and 2 are the analyses and liquefaction experiments, respectively, and Task 3 deals with the economic effects of using these methods during coal liquefaction. Results are presented on the following: Analytical Support--screening tests and second-stage conversions; Laboratory-Scale Operations--catalysts, coal conversion in synthetic solvents, Black Thunder screening studies, and two-stage liquefaction experiments; and Technical and economic Assessment--commercial liquefaction plant description, liquefaction plant cost; and economic analysis.

The Standards/Requirements Identification Document(S/RID) is a list of the Environmental, Safety, and Health (ES&H) and Safeguards and Security (SAS) standards/requirements applicable to the K Basins facility

This first volume of the five volume set begins with a CPDR overview and then details the PF magnet system, manufacturing R&D, Westinghouse R&D, the central solenoid, the PF 5 ring coil, the PF 6/7 ring coil, quality assurance, and the system design description.

This System Design Description, prepared in accordance with the TPX Project Management Plan provides a summary or TF Magnet System design features at the conclusion of Phase I, Preliminary Design and Manufacturing Research. The document includes the analytical and experimental bases for the design, and plans for implementation in final design, manufacturing, test, and magnet integration into the tokamak. Requirements for operation and maintenance are outlined, and references to sources of additional information are provided.

This document presents sampling data resulting from the March 23, 1995, sampling of SST 241-SX-103 using the vapor sampling system.

This document describes the Quality Assurance Program Plan (QAPP) for the Spent Nuclear Fuels (SNF) Canister Storage Building (CSB) Project. The purpose of this QAPP is to control project activities ensuring achievement of the project mission in a safe, consistent and reliable manner.

Onsite and site boundary radiological consequences were estimated for a postulated accidental drop of an Interim Storage Cask (ISC) loaded 7 assemblies at the maximum available burnup. The postulated cask drop was assumed to occur from the maximum physically attainable height during crane movement of the cask. The resulting onsite and site boundary doses of 45 mSv and 0.04 mSv are far below the corresponding 1 Sv and 250 mSv risk guidelines for highly unlikely accidents

Earlier research was on finite confinement for the soliton, proton- transfer doping of polyacetylene, electron hopping, Peierls distortion in discrete polyenes (cyanines), conductive heteropolymers, and synthesis and covalent attachment of polymerizable trimers to insulating, conductive, and semiconductive surfaces. The past year`s research was on synthesis of binuclear complexes with soliton-like communication between the two metal centers, and soluble polyheterocycles with remarkable conjugation lengths. These materials show electroluminescence as well.

Radiological consequences at the site boundary were estimated for non-mechanistic disruption of an Interim Storage Cask (ISC) loaded with 7 assemblies at the maximum available burnup. The hypothetical disruption consisted of a crushing/shearing of the Core Component Container (CCC) along with all 7 assemblies and the creation of a large escape path out of the cask. The resulting site boundary dose of 1.6 mSv is far below the 250 mSv risk guidelines for highly unlikely events.

This study evaluates alternatives for high-level waste forms, containers, container processing systems, and onsite interim storage. Glass waste forms considered are cullet, marbles, gems, and monolithic glass. Small and large containers configured with several combinations of overpack confinement and shield casks are evaluated for these waste forms. Onsite interim storage concepts including canister storage building, bore holes, and storage pad were configured with various glass forms and canister alternatives. All favorable options include the monolithic glass production process as the waste form. Of the favorable options the unshielded 4- and 7-canister overpack options have the greatest technical assurance associated with their design concepts due to their process packaging and storage methods. These canisters are 0.68 m and 0.54 m in diameter respectively and 4.57 m tall. Life-cycle costs are not a discriminating factor in most cases, varying typically less than 15 percent.

The Electric Power Monthly (EPM) presents monthly electricity statistics for a wide audience including Congress, Federal and State agencies, the electric utility industry, and the general public. The purpose of this publication is to provide energy decisionmakers with accurate and timely information that may be used in forming various perspectives on electric issues that lie ahead. The EIA collected the information in this report to fulfill its data collection and dissemination responsibilities as specified in the Federal Energy Administration Act of 1974 (Public Law 93-275) as amended. 64 tabs.

A consortium (Los Alamos, Sandia, OR, Livermore) have been collaborating under the GONII project to generate a synthetic seismic data base. Two deliverables were a common code that would run on the various site machines, and the use of these codes to generate parts of the final data base. The data base consists of a large number of shots applied to two geographic models developed by another part of GONII, the salt model and the overthrust model,s which were supplied as large files containing propagation velocity on a 3-D grid. Los Alamos was supplied with the source code of a seismic propagation code written by the French Petroleum Institute. A decision was made to port a subset of the code to Fortran on a node. Part of this contract was spent verifying/debugging the Fortran on a node code; a port of the code was made to run on the Cray. A total of 846 shots were run on the CM5. It was found that files on the SDA are not safe from corruption and the model velocity file may change.

We report the status of a high-statistics Monte Carlo simulation of non-self-avoiding crystalline surfaces with extrinsic curvature on lattices of size up to 128{sup 2} nodes. We impose free boundary conditions. The free energy is a gaussian spring tethering potential together with a normal-normal bending energy. Particular emphasis is given to the behavior of the model in the cold phase where we measure the decay of the normal-normal correlation function.

Surface measurements of solar irradiance of the atmosphere were made by a multipurpose computer-controlled scanning photometer at the Rattlesnake Mountain Observatory. The observatory is located at 46.4{degrees}N, 119.6{degrees}W at an elevation of 1088 m above mean sea level. The photometer measures the attenuation of direct solar radiation for different wavelengths using 12 filters. Five of these filters (ie., at 428 nm, 486 nm, 535 nm, 785 nm, and 1010 nm, with respective half-power widths of 2, 2, 3, 18, and 28 nm) are suitable for monitoring variations in the total optical depth of the atmosphere. Total optical depths for the five wavelength bands were derived from solar irradiance measurements taken at the observatory from August 5, 1979, to September 2, 1994; these total optical depth data are distributed with this numeric data package (NDP). To determine the contribution of atmospheric aerosols to the total optical depths, the effects of Rayleigh scattering and ozone absorption were subtracted (other molecular scattering was minimal for the five filters) to obtain total column aerosol optical depths. The total aerosol optical depths were further decomposed into tropospheric and stratospheric components by calculating a robustly smoothed mean background optical depth (tropospheric component) for each wavelength using …

The purpose of this waste analysis plan is to document the necessary characterization, sampling, screening, analysis, and waste acceptance criteria for waste received at the WRAP Module 1. Waste expected to be received at WRAP Module 1 includes newly generated and retrieved waste. The newly generated waste will undergo verification prior to treatment, storage, or disposal. Retrieved waste from the burial grounds or above ground storage will undergo further characterization (as needed), treatment, supercompaction, and repackaging

One of the most significant factors impacting the performance of waste package container materials under repository relevant conditions is the thermal environment. This environment will be affected by the areal power density of the repository, which is dictated by facility design, and the dominant heat transfer mechanism at the site. The near-field environment will evolve as radioactive decay decreases the thermal output of each waste package. Recent calculations (Buscheck and Nitao, 1994) have addressed the importance of thermal loading conditions on waste package performance at the Yucca Mountain site. If a relatively low repository thermal loading design is employed, the temperature and relative humidity near the waste package may significantly affect the degradation of corrosion allowance barriers due to moist air oxidation and radiolytically enhanced corrosion. The purpose this report is to present a literature review of the potential degradation modes for moderately corrosion resistant nickel copper and nickel based candidate materials that may be applicable as alternate barriers for the ACD systems in the Yucca Mountain environment. This report presents a review of the corrosion of nickel-copper alloys, summaries of experimental evaluations of oxidation and atmospheric corrosion in nickel-copper alloys, views of experimental studies of aqueous corrosion in nickel …

A relatively new advanced composite matrix, polycyanate ester, was evaluated for cure shrinkage. The chemical cure shrinkage of composites is difficult to model but a number of clever experimental techniques are available to the investigator. In this work the method of curing a prepreg layup on top of a previously cured laminate of identical ply composition is utilized. The polymeric matrices used in advanced composites have been primarily epoxies and therefore a common system of this type, Fiberite 3501-6, was used as a base case material. Three polycyanate matrix systems were selected for the study. These are: Fiberite 954-2A, YLA RS-3, and Bryte Technology BTCy-1. The first three of these systems were unidirectional prepreg with carbon fiber reinforcement. The Bryte Technology material was reinforced with E-glass fabric. The technique used to evaluate cure shrinkage results in distortion of the flatness of an otherwise symmetric laminate. The first laminate is cured in a conventional fashion. An identical layup is cured on this first laminate. During the second cure all constituents are exposed to the same thermal cycles. However, only the new portion of the laminate will experience volumetric changes associate with matrix cure. The additional strain of cure shrinkage results in …

This test report summarizes testing activities and documents the results of the load tests performed on-site and off-site to structural qualify the 52-inch equipment containers designed and fabricated under Project W-320.

This Acceptance Test Procedure is to verify the correct reading of points connected to the Tank Monitor and Control System (TMACS).

The Ford/Andresen slip dissolution SCC model, originally developed for stainless steel components in BWR environments, has been applied to Alloy 600 and Alloy X-750 tested in deaerated pure water chemistry. A method is described whereby the crack growth rates measured in compact tension specimens can be used to estimate crack growth in a component. Good agreement was found between model prediction and measured SCC in X-750 threaded fasteners over a wide range of temperatures, stresses, and material condition. Most data support the basic assumption of this model that cracks initiate early in life. The evidence supporting a particular SCC mechanism is mixed. Electrochemical repassivation data and estimates of oxide fracture strain indicate that the slip dissolution model can account for the observed crack growth rates, provided primary rather than secondary creep rates are used. However, approximately 100 cross-sectional TEM foils of SCC cracks including crack tips reveal no evidence of enhanced plasticity or unique dislocation patterns at the crack tip or along the crack to support a classic slip dissolution mechanism. No voids, hydrides, or microcracks are found in the vicinity of the crack tips creating doubt about classic hydrogen related mechanisms. The bulk oxide films exhibit a surface oxide …

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, and WHC 222-S Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples for tank 241-TY-106.

The Hanford Site Spent Nuclear Fuel (SNF) Project was formed to manage the SNF at Hanford. Specifically, the mission of the SNF Project on the Hanford Site is to ``provide safe, economic, environmentally sound management of Hanford SNF in a manner which stages it for final disposition.`` The current mission of the Fuel Fabrication Facilities Transition Project (FFFTP) is to transition the 308 Building for turn over to the Environmental Restoration Contractor for decontamination and decommissioning.