The Electric Power Annual presents a summary of electric utility statistics at national, regional and State levels. The objective of the publication is to provide industry decisionmakers, government policymakers, analysts and the general public with historical data that may be used in understanding US electricity markets. The Electric Power Annual is prepared by the Survey Management Division; Office of Coal, Nuclear, Electric and Alternate Fuels; Energy Information Administration (EIA); US Department of Energy. ``The US Electric Power Industry at a Glance`` section presents a profile of the electric power industry ownership and performance, and a review of key statistics for the year. Subsequent sections present data on generating capability, including proposed capability additions; net generation; fossil-fuel statistics; retail sales; revenue; financial statistics; environmental statistics; electric power transactions; demand-side management; and nonutility power producers. In addition, the appendices provide supplemental data on major disturbances and unusual occurrences in US electricity power systems. Each section contains related text and tables and refers the reader to the appropriate publication that contains more detailed data on the subject matter. Monetary values in this publication are expressed in nominal terms.

The United States has a superb capability for forefront research in elementary particle physics for the next decade-but it can be realized only if there is sufficient funding to make efficient use of our existing world-class facilities. Throughout most of the past half century, the US has led the world in making contributions to our growing understanding of elementary particle physics. We are no longer the dominant force in the field, but we are still one of the leaders. The termination of the SSC is an enormous blow, but it need not end our participation in the field. We must first take advantage of what we have -- and that is considerable -- and then use it as the basis for a successful strategy for the first few decades in the next century. The US can make many important contributions to our field for the rest of this decade and for part of the next. But, after that, we will not long remain among the world`s leaders unless we have the foresight to preserve and strengthen our capability to construct and operate world-class facilities.

In our light ion inertial confinement fusion (ICF) program, fusion capsules are driven with an intense x-ray radiation field produced when an intense beam of ions penetrates a radiation case and deposits energy in a foam x-ray conversion region. A first step in the program is to generate and measure these intense fields on the Particle Beam Fusion Accelerator II (PBFA II). Our goal is to generate a 100-eV radiation temperature in lithium ion beam driven hohlraums, the radiation environment which will provide the initial drive temperature for ion beam driven implosion systems designed to achieve high gain. In this paper, we describe the design of such hohlraum targets and their predicted performance on PBFA II as we provide increasing ion beam intensities.

During 1993, the activity at the University was split into two primary groups. One group provided direct support for the development and testing of the RVIR vehicle. This effort culminated in a demonstration of the vehicle at ORNL during December. The second group of researchers focused attention on pushing the technology forward in the areas of radiation imaging, navigation, and sensing modalities. A major effort in technology transfer took place during this year. All of these efforts reflected in the periodic progress reports which are attached. During 1994, our attention will change from the Nuclear Energy program to the Environmental Restoration and Waste Management office. The immediate needs of the Robotics Technology Development Program within the Office of Technology Development of EM drove this change in target applications. The University will be working closely with the national laboratories to further develop and transfer existing technologies to mobile platforms which are currently being designed and employed in seriously hazardous environments.

The Savannah River Technical Center visually examined several axial piston pump wear plates from Delta-Q Corporation in an effort to determine the cause of the scratches. The investigation found the material and hardness to be approximately consistent with vendor specifications. The visual examination revealed gouges and tears on plates 1 - 4, silicon and aluminum contamination on plates 2 & 3 and a heavy inclusion content in the base metal. The scratches were most likely attributable to either metal debris created by the protruding metal around the gouges and tears or the silicon and aluminum contamination. The heavy inclusion content may have contributed by providing sites for the gouges and tears to develop during fabrication. It is recommended that tighter controls be introduced during procurement to ensure cleaner, inclusion controlled, steel and controlling the silicon and aluminum contamination during process assembly of the pumps. Specific surface texture requirements may also be considered for final machining.

Work continued as planned and scheduled. Total expenditures are below budget. Task 2 is complete. Task 3 is complete except for R, D & T Plan -- Phase II. Task 4 is currently slightly behind schedule but is projected to finish on or ahead of schedule. Task 5 was started early. The following major deliverables were issued: (1) Technical Paper for `93 International Joint Power Generation Conference. (2) Technical Paper for IEA Second International Conference, and (3) Topical Report by EAR on Air Toxics. Subtask 4.1 -- Engineering Analysis in support of the CGU design is nearly complete and partial design specifications are being employed in Task 5. Subtask 4.2 -- Experimental Research efforts consisted of the first series of Drop Tube Furnace tests. Data is being analyzed. Subtask 4.3 -- Modeling work to data resulted in input files for Boiler Simulation Facility and flow pattern convergence was attained. Particle combustion is the next step. This work will be reported on at the next Quarterly Project Review meeting. Task 5 was started early to facilitate Task 6 schedule and quality. Integration of the SNO{sub x} Hot Scheme into the boiler and turbine/feedwater train was optimized and design work on the …

This project is a major step in the Department of Energy`s program to show that ultra-clean coal-water slurry fuel (CWF) can be produced from selected coals and that this premium fuel will be a cost-effectve replacement for oil and natural gas now fueling some of the industrial and utility boilers in the United States as well as for advanced combustars currently under development. The replacement of oil and gas with CWF can only be realized if retrofit costs are kept to a minimum and retrofit boiler emissions meet national goals fbr clean air. These concerns establish the specifications for maximum ash and sulfur levels and combustion properties of the CWF. This cost-share contract is a 51-month program which started on September 30, 1992. This report discusses the technical progress, made during the 6th quarter of the project from January 1 to March 31, 1994. The project has three major objectives: (1) The primary objective is to develop the design base for prototype commercial advanced fine coal cleaning facilities capable of producing ultra-clean coals suitable for conversion to coal-water slurry fuel for premium fuel applications. The fine coal cleaning technologies are advanced column flotation and selective agglomeration. (2) A secondary objective …

The acceptance test procedure (ATP) for the compressed air system at building 241-AW-273 was completed on March 11, 1993. The system was upgraded to provide a reliable source of compressed air to the tank farm. The upgrade included the demolition of the existing air compressor and associated piping, as well as the installation of a new air compressor with a closed loop cooling system. A compressed air cross-tie was added to allow the process air compressor to function as a back-up to the existing instrument air compressor. The purpose of the ATP was to achieve three primary objectives: verify system upgrade in accordance with the design media; provide functional test of system components and controls; and prepare the system for the Operational Test. The ATP was successfully completed with thirteen exceptions, which were resolved prior to completing the acceptance test. The repaired exceptions had no impact to safety or the environment and are briefly summarized. Testing ensured that the system was installed per design, that its components function as required and that it is ready for operational testing and subsequent turnover to operations.

The purpose of this tank characterization report is to describe and characterize the waste in Double-Shell Tank 241-AP-107 based on information gathered from various sources. This report summarizes the available information regarding the waste in Tank 241-AP-107, and arranges it in a useful format for making management and technical decisions concerning this particular waste tank. In addition, conclusion and recommendations based on safety and further characterization needs are given. Specific objectives reached by the sampling and characterization of the waste in Tank 241-AP-107 are: Contribute toward the fulfillment of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-44-05 concerning the characterization of Hanford Site high-level radioactive waste tanks; Complete safety screening of the contents of Tank 241-AP-107 to meet the characterization requirements of the Defense Nuclear Facilities Safety board (DNFSB) Recommendation 93-5; and Provide tank waste characterization to the Tank Waste Remediation System (TWRS) Program Elements in accordance with the TWRS Tank Waste Analysis Plan.

The Oak Ridge Y-12 Plant operates its Criticality Accident Alarm System (CAAS) according to the guidance of Standard ANSI/ANS-8.3-1986. This standard requires that the detector shall not fail to initiate an alarm when subjected to a radiation field of at least 0.1 Gy/s (10 rad/s). It also requires that the system shall be designed to immediately detect the minimum accident of concern and shall produce an alarm within one half second of activation. Sixty-three new detectors that use plastic scintillators have been obtained to upgrade the current Y-12 Plant CAAS. To ensure that these detectors can support the above criteria, testing was done using the SPR III reactor at the Sandia Pulsed Reactor Facility.

The audit disclosed that Sandia`s pension plans had $588.9 million in excess assets as of December 31, 1990, on a current value basis. If plan terminations and spin-offs occurred, at least $408.8 million of this amount could be returned to the Government without affecting the pension benefits that Sandia employees and retirees have earned. We recommended that Albuquerque take the necessary action to reduce the excess assets in the pension plans and recover the Government`s share. However, Albuquerque disagreed with the recommendation. Albuquerque justified leaving the excess assets in the pension plans to fund future plan amendments; to avoid future funding contributions; to avoid the costs and time-consuming administrative steps associated with taking action; and to prevent damaging effects on employee morale. We analyzed these points, and concluded that they should not prevent the Department from initiating action to return excess assets to the Government. Actuarial analysis of the pension plans showed that, even if certain plan adjustments were made, the plans were overfunded by $256 million as of December 31, 1991 (on an actuarial value basis).

This report is the seventh in a series of publications developed by the Energy Information Administration (EIA) to quantify the biomass-derived primary energy used by the US economy. It presents estimates of 1991 and 1992 consumption. The objective of this report is to provide updated estimates of biomass energy consumption for use by Congress, Federal and State agencies, biomass producers and end-use sectors, and the public at large.

A theme which emerges from our simple considerations is that some well-planned early parametric and sensitivity studies, using current-generation coupled Earth system model components, along with simplistic proxy models of terrestrial biospheric and biogeochemical processes, could furnish valuable information to help guide the development of a longer-term plan for research supporting ESM development. This theme is rooted in the premise that the importance of various ESM component processes can be fully assessed only from the perspective of a complete coupling of that process into the ESM context. That is, the question, ``How well must a given process be modelled``? Cannot be answered in isolation, but rather requires a careful blend of process research and coupled model studies.

With the closure of many experimental facilities, the nuclear criticality safety analyst increasingly is required to rely on computer calculations to identify safe limits for the handling and storage of fissile materials. However, in many cases, the analyst has little experience with the specific codes available at his/her facility. This primer will help you, the analyst, understand and use the MCNP Monte Carlo code for nuclear criticality safety analyses. It assumes that you have a college education in a technical field. There is no assumption of familiarity with Monte Carlo codes in general or with MCNP in particular. Appendix A gives an introduction to Monte Carlo techniques. The primer is designed to teach by example, with each example illustrating two or three features of MCNP that are useful in criticality analyses. Beginning with a Quickstart chapter, the primer gives an overview of the basic requirements for MCNP input and allows you to run a simple criticality problem with MCNP. This chapter is not designed to explain either the input or the MCNP options in detail; but rather it introduces basic concepts that are further explained in following chapters. Each chapter begins with a list of basic objectives that identify the …

Accurate placement of hundreds of focused laser beams on target is necessary to achieve success in the National Ignition Facility (NIF). The current system requirement is {le}7 {mu}rad error in output pointing and {le}1 mm error in focusing. To accommodate several system shots per day, a target alignment system must be able to align the target to chamber center, inject an alignment beam to represent each shot beam, and point and focus the alignment beams onto the target in about one hour. At Lawrence Livermore National Laboratory, we have developed a target alignment concept and built a prototype to validate the approach. The concept comprises three systems: the chamber center reference, target alignment sensor, and target alignment beams.

We are pursuing several novel x-ray imaging schemes to measure plasma parameters in inertial-confinement fusion experiments. This paper will review two quite successful approaches, the soft x-ray moire deflectometer, and the annular (ring) coded-aperture microscope. The deflectometer is the newer diagnostic, and this paper will concentrate on this topic. We will describe the operating principles of moire deflectometry, give the motivations for soft x-ray probing, describe the physical apparatus in detail, and present some sample images and results. The ring coded-aperture microscope has been described previously, so here we will only briefly review the principle of the instrument. We will concentrate on the signal-to-noise ratio calculations that motivate the use of annular coded apertures, and describe recent work to predict and measure the resolution of the instrument.

Thermal methods, and particularly steam injection, are currently recognized as the most promising for the efficient recovery of heavy oil. Despite significant progress, however, important technical issues remain open. Specifically, still inadequate is our knowledge of the complex interaction between porous media and the various fluids of thermal recovery (steam, water, heavy oil, gases, and chemicals). While, the interplay of heat transfer and fluid flow with pore- and macro-scale heterogeneity is largely unexplored. The objectives of this contract are to continue previous work and to carry out new fundamental studies in the following areas of interest to thermal recovery: displacement and flow properties of fluids involving phase change (condensation-evaporation) in porous media; flow properties of mobility control fluids (such as foam); and the effect of reservoir heterogeneity on thermal recovery. The specific projects are motivated by and address the need to improve heavy oil recovery from typical reservoirs as well as less conventional fractured reservoirs producing from vertical or horizontal wells. This quarterly report covers work accomplished for studies in: vapor-liquid flow; recovery processes in heterogeneous reservoirs; and chemical additives.

The application of laser ablation technology to the decontamination of radioactive metals, particularly the surfaces of equipment, is discussed. Included is information related to the design, capital and operating costs, and effectiveness of laser ablation technology, based on commercial excimer and Nd:YAG lasers, for the decontamination of production scale equipment.

A new experimental technique has been devised to measure residual stresses in ductile materials with a combination of laser speckle pattern interferometry and spot heating. The speckle pattern interferometer measures in-plane deformations while the heating provides for very localized stress relief. The residual stresses are determined by the amount of strain that is measured subsequent to the heating and cool-down of the region being interrogated. A simple lumped parameter model is presented to provide a description of the method. This description is followed by presentations of the results of finite element analyses and experimental results with uniaxial test specimens. Excellent agreement between the experiments and the computer analyses were obtained.

This document provides an Acceptance Test Procedure (ATP) for the project W-337 upgrades to the 340-NT-EX stack, and its associated sampling and monitoring systems.

We report the first experimental verification of the MHD dynamo in the RFP. A burst of magnetohydrodynamic (MHD) dynamo electric field is observed during the sawtooth crash, followed by an increase in the local parallel current in the MST RFP edge. By measuring each term, the parallel MHD mean-field Ohm`s law is observed to hold within experimental error bars both between and during sawtooth crashes.

This report provides information on the seismic hazard for design of the proposed Environmental Restoration Disposal Facility (ERDF), a facility designed for the disposal of wastes generated during the cleanup of Hanford Site aggregate areas. The preferred ERDF site is located south and east of 200 East and 200 West Areas. The Washington State Groundwater Protection Program (WAC 173-303-806 (4)(a)(xxi)) requires that the characteristics of local and regional hydrogeology be defined. A plan for that work has been developed (Weekes and Borghese 1993). In addition, WAC 173-303-282 provides regulatory guidance on siting a dangerous waste facility, and US Department of Energy (DOE) Order 5480.28 requires consideration of natural phenomena hazards mitigation for DOE sites and facilities. This report provides information to evaluate the ERDF site with respect to seismic hazard. The ERDF will be a Corrective Action Management Unit (CAMU) as defined by 40 CFR 260.10.

This document is a plan which serves as the contractual agreement between the Characterization Program, Sampling Operations, WHC 222-S Laboratory, and PNL 325 Analytical Chemistry Laboratory. The scope of this plan is to provide guidance for the sampling and analysis of samples from tank 241-C-101.

A micro-processor based datalogger is used to monitor, display, and log seventeen RTD temperature channels. Five bearings are monitored for each of the three electric motor-fan assemblies and two bearings are monitored on the steam turbine unit. Several alarms per data channel (a High alarm at 236 degrees and a High High alarm at 246 degrees F) will alert the operation`s staff to increasing abnormal bearing temperatures. This procedure is cross-referenced to the manufacturers manual. All programming steps will have the following footnote: Mpg x-xx. The Mpg refers to the Manual page, with x as the section number and xx as the page number in that section. When more information is needed, such as pictures or details, then the manual section and page number is provided.