American companies are facing increased competitive pressures from foreign firms. Many observers feel that U.S. firms lag behind their foreign competitors in the development, application, and marketing of new technologies and techniques. The Japanese industrial enterprise is characterized by a large proportion of private sector financing and many other factors, which this report analyzes at length. The question being debated by Congress is whether or not U.S. government programs and policies are an acceptable and effective means of supporting the efforts of American industries to operate in a manner consistent with success in world markets.

This report is one of a series of CRS reports that examines lobbying and pressure group influence by foreign interests on US public policy.

This preliminary assessment summarizes U.S. Army, Navy, Air Force, and Marine Corps performances during recent war, then relates it to past experience and potential threats in ways that might help decisionmakers determine the most suitable characteristics of U.S. armed forces for the rest of this decade.

This report the National Emergencies Act (50 U.S.C. 1601-1651) that eliminated or modified some statutory grants of emergency authority, required the President to declare formally the existence of a national emergency and to specify what statutory authority, activated by the declaration, would be used, and provided Congress a means to countermand the President's declaration and the activated authority being sought.

This OTA’s report responds to the request of numerous Members of Congress to review the physical, emotional, and behavioral health status of contemporary American adolescents, including adolescents in groups who might be more likely to be in special need of health-related interventions: adolescents living in poverty, adolescents from racial and ethnic minority groups, Native American adolescents, and adolescents in rural areas. In addition, OTA was asked to: 1 ) identify risk and protective factors for adolescent health problems and integrate national data in order to understand the clustering of specific adolescent problems, 2) evaluate options in the organization of health services and technologies available to adolescents (including accessibility and financing), 3) assess options in the conduct of national health surveys to improve collection of adolescent health statistics, and 4) identify gaps in research on the health and behavior of adolescents.

This report identifies several immediate steps the Federal Government could take. First, new environmental standards, population shifts, and industrial changes have transformed the nature of many public works problems, and Federal programs must be refocused to fit the new circumstances. Second, if we expect to maintain our economic health, the Nation must increase its investment in public works, despite budget dilemmas.

This background paper, which describes the state-of the- art of identifying substances that can harm the immune system, represents one response to the committee’s request. Chapter 2 provides basic information about the principal components of the immune system and the general consequences that stem from perturbations to it. Chapter 3 describes methods for evaluating chemical immunotoxicity and reports on some known or suspected immunotoxicants. Chapter 4 summarizes Federal research and regulatory activities related to immunotoxicity.

This study explores the role that communication technologies can play in securing rural America’s future. It develops several policy strategies and options to encourage such development. The study was requested by the Joint Economic Committee of Congress and Senators Charles E. Grassley and Orrin G. Hatch.

Performance-assessment calculations in support of the site- suitability effort for the Yucca Mountain Project will address radionuclide transport arising from various disruptive scenarios. Here we present release rates of radionuclides from individual waste packages for scenarios involving various postulated forms of water intrusion, including increased infiltration rate as well as rock immediately surrounding an individual waste package becoming saturated with ground water. We examine: (1) effect of increased water infiltration rate on release rates; increases in radionuclide release rates resulting from water filling the annulus between the waste container and the surrounding rock, as well as water saturating the pores and fractures in the rock surrounding the waste package; (3) the effect of flow in fractures in the saturated rock on release rate; and (4) release of radionuclides to the mountain surface resulting from an exploratory borehole shaft intersecting a waste package. The radionuclides considered are Tc-99; I-129; Cs-135; Np- 237; Pu-239,240,242; and Am-241,243. Release rates are calculated for both the wet-drip bathtub and the wet-continuous water-contact modes, as described in the Working Group 2 report, applying equations as published by Sadeghi, et al., [1990] and as extended in the present report.

A computer code is described which can simulate non-isothermal multiphase multicomponent flow in porous media. It is applicable to natural-state studies of geothermal systems and ground-water flow. The equations of heat and mass transfer for multiphase flow in porous and permeable media are solved using the finite element method. The permeability and porosity of the medium are allowed to depend on pressure and temperature. The code also has provisions for movable air and water phases and noncoupled tracers; that is, tracer solutions that do not affect the heat and mass transfer solutions. The tracers can be passive or reactive. The code can simulate two-dimensional, two-dimensional radial, or three-dimensional geometries. A summary of the equations in the model and the numerical solution procedure are provided in this report. A user`s guide and sample problems are also included. The main use of FEHMN will be to assist in the understanding of flow fields in the saturated zone below the proposed Yucca Mountain Repository. 33 refs., 27 figs., 12 tabs.

This report is intended to provide a summary of the cost and schedule performance for the Civilian Radioactive Waste Management Program. Historical and current cost profiles (extracted from the DOE Financial Information System) are presented for each of the major program elements. Also included in this report are the reference program schedule, the status of near-term program milestones and the status of the Nuclear Waste Fund revenues and disbursements. This report includes data through December 1990.

This is the final report of the Nuclear Physics Laboratory of the University of Washington on work supported in part by US Department of Energy contract DE-AC06-81ER40048. It contains chapters on giant dipole resonances in excited nuclei, nucleus-nucleus reactions, astrophysics, polarization in nuclear reactions, fundamental symmetries and interactions, accelerator mass spectrometry (AMS), ultra-relativistic heavy ions, medium energy reactions, work by external users, instrumentation, accelerators and ion sources, and computer systems. An appendix lists Laboratory personnel, a Ph. D. degree granted in the 1990-1991 academic year, and publications. Refs., 41 figs., 7 tabs.

Six hundred eighty-two (682) containers of soil were generated at Mound Plant between April 1 and October 31, 1990 as a result of the excavation of soils containing plutonium-238 at two ongoing Decontamination and Decommissioning (D&D) Program sites; these areas are known as Area 14, the waste transfer system (WTS) hillside, and Area 17, the Special Metallurgical (SM) Building Area. The soils from these areas are part of the Mound Plant waste stream number AMDM-000000010, Contaminated Soil, and are proposed for shipment to the Nevada Test Site (NTS) for disposal as low-level radioactive waste. These containers of soil are currently in storage at Mound Plant. The purpose of this sampling and analysis was to demonstrate that the D&D soils comply with the waste acceptance requirements of the NTS, as presented In Nevada Test Site Defense Waste Acceptance Criteria, Certification, and Transfer Requirements (DOE 1988). The sealed waste packages, constructed of wood or metal, are currently being stored In Building 31 and at other locations throughout the Mound Plant. For additional historical information concerning the D&D soils, Including waste stream evaluations and past sampling data see the Sampling and Analysis Plan for Mound Plant D&D Soils Packages (EG&G 1991).

This analysis indicates that the potential impacts associated with the current/projected Mound tritium operations are adequately bounded by the existing environmental impacts analyzed in the FEIS. It also indicates that the incremental impacts of the NFM project will make a positive contribution to the overall impact of current/projected tritium operations. Except for minor and normal temporary conditions during the construction and demolition phases, the NFM project would measurably reduce the likelihood of adverse consequences to the environment. Relocation of the PE/PD laboratory operations from the SW/R Tritium Complex to the T Building will place these operations in a safer, state-of-the-art glovebox systems. Through the utilization of modern laboratory equipment and enhanced containment, the project will reduce the quantity of routine airborne tritium releases and volume of solid tritiated wastes resulting from routine PE/PD laboratory operations. The increased reliance placed on engineered safety aspects and stronger mitigative measures by the project will also reduce the risk associated with these operations by reducing both the probability and consequences of unusual occurrences involving uncontrolled tritium releases.

This specification documents the gas tungsten arc (GTA) welding process and production weld acceptance criteria requirements for the MC4163. This document is written specifically to apply to the welds on the MC4163 and is not to be used as a general gas tungsten arc welding specification. All sections of this specification must be complied with unless specifically exempted in writing. There are a total of five welds with three different joint designs required to fabricate the MC4163. In the order of fabrication they are (1) initiator closure disc, (2) nozzle to case girth welds, two and, (3) nozzle closure disc welds, two. This specification will only address the nozzle to case girth welds and the nozzle closure disc welds.

This Site Hydrogeologic/Geotechnical Characterization Report (SHCR) presents the results of a comprehensive study conducted on a proposed solid waste landfill site, identified herein as Site B, at the Savannah River Site (SRS). This report is intended to satisfy all requirements of the South Carolina Department of Health and Environmental Control (SCDHEC) with regard to landfill siting requirements and ground water and environmental protection. In addition, this report provides substantial geotechnical data pertinent to the landfill design process.

On 18 February 1991 the Project Manager formed a working group to address the safety guidelines and requirements for the underground facilities during the period of accelerator construction, installation, and commissioning. The following report summarizes the research and discussions conducted by the group and the recommended guidelines for safety during this phase of the project.

Solutions are given for the decay of the local current in both a finite and an infinite superconducting circuit consisting of a linear array of loops each containing in series an inductance L and in parallel a resistance R. Numerical results obtained from these solutions are given, and the results for local current decay for both cases are compared The properties of polynomials associated with the finite chain solution and two generating functions along with the method of solution of the diffusion type equation associated with the infinite chain model are discussed in the appendices. These solutions are used to obtain insight into the nature of the time decay of the currents in the loops resulting from crossings of the strands forming the superconducting cable of the SSC dipole magnets.

Compilation of monthly reports from departments in the city of San Antonio, Texas providing statistics, project updates, and other information about services and activities.

A report on alternative sources of revenue for Texas and current tax revenues.

A number of correction magnets are required for the advanced photon source (APS) machine to correct the beam. There are five kinds of correction magnets for the storage ring, two for the injector synchrotron, and two for the positron accumulator ring (PAR). Table I shoes a summary of the correction magnet power supplies for the APS machine. For the storage ring, the displacement of the quadrupole magnets due to the low frequency vibration below 25 Hz has the most significant effect on the stability of the positron closed orbit. The primary external source of the low frequency vibration is the ground motion of approximately 20 {mu}m amplitude, with frequency components concentrated below 10 Hz. These low frequency vibrations can be corrected by using the correction magnets, whose field strengths are controlled individually through the feedback loop comprising the beam position monitoring system. The correction field require could be either positive or negative. Thus for all the correction magnets, bipolar power supplies (BPSs) are required to produce both polarities of correction fields. Three different types of BPS are used for all the correction magnets. Type I BPSs cover all the correction magnets for the storage ring, except for the trim dipoles. …

This report consists of two parts. Part 1 describes the development of novel analytical methods needed to predict the BOM performance and the subsequent performance degradation of the mutually obstructed RTGs for the CRAF and Cassini missions. Part II applies those methods to the two missions, presents the resultant predictions, and discusses their programmatic implications. The results indicate that JPL's original power demand goals could have been met with two standard GPHS RTGs for each mission. However, JPL subsequently raised both the power demand profile and the duration for both missions, to the point where two standard RTGs could no longer provide the desired power margin. Each mission can be satisfied by adding a third RTG, and in the case of the Cassini mission the use of three RTGs appears to be unavoidable. In the case of the CRAF mission, there appears to be a possibility that modest modifications of the RTGs' design and/or operating scheme and meet the missions' power demand without the addition of a third RTG. The potential saving in cost and schedule pressure prompted Fairchild to undertake a study of various obvious and not-so-obvious stratagems, either singly or in combination, to determine whether they would make …

The vacuum pumping of the CC Cryostat was anticipated to be dominated by a water vapor load. The Engineering Note 270, extrapolating from earlier experience, predicts the removal of water vapor will be the dominant pumping load and take ca. 45 days to remove at the pumping speed planned. Part of the planned pumping capability was a homemade, liquid nitrogen temperature, water vapor cryopump. This note describes the design, fabrication and performance experiences of the Cryopump described in the D0 assembly drawing 3740.514-ME-294693.

This engineering note documents the testing of the set pressure of the EC hydraulic drive cylinder relief valve. The purpose of the relief valve is to provide a safety measure in the event that oil becomes trapped in the rod side of the cylinder and pressure is applied to the cap side. The note includes an explanation of the procedure used and a summary of the result of the testing done on February 14, 1991 by Gary Trotter. The result was that the cylinder relief valve relieved at the correct set pressure of 10,500 psig. The basic concern is for the protection of the cylinder. The pump is capable of providing up to 10,500 psi of pressure to either side of the cylinder. The cylinder is rated for 10,500 psi. Under normal operating conditions, the valves would be open, and the pumping pressure would automatically flow oil into one side, and remove oil from the other side. If, however, the valve for the other side was closed, so that oil could not be removed, then the pressure would build in that side. If the rod side is pressurized to the maximum pump pressure of 10,500 psi, the cross sectional area …