At the request of the Office of Fusion Energy, a group of experts was convened on February 6--8, 1990. This group met to assess the world data base on Reversed Field Pinch (RFP) physics, and, further, to assess the role of the ZTH experiment in providing reactor relevant physics understanding for that confinement geometry. This group met, analyzed some of the relevant literature, and heard extensive presentations on the physics of the RFP and the plans for the ZTH and RFX devices. The conclusions of this group of experts are contained in this report.

The overall goal of this research in the area of ash transport was to advance the capability of making reliable engineering predictions of the dynamics and consequences of net deposit growth for surfaces exposed to the products of coal combustion. To accomplish this for a wide variety of combustor types, coal types, and operating conditions, this capability must be based on a quantitative understanding of each of the important mechanisms of mineral matter transport, as well as the nature of the interactions between these substances and the prevailing fireside'' surface of the deposit. This level of understanding and predictive capability could ultimately be translated into very significant cost reductions for coal-fired equipment design, development and operation.

In order to evaluate the effectiveness of Section 11, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components,'' of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code examinations, 26 inservice inspection (ISI) summary reports from 24 facilities were reviewed. It was found that these ASME Code examinations and tests are instrumental in revealing indications and defects in welds and plant components. In addition, this study uncovered that fact that some of the Section 11 requirements are apparently not clear and are misunderstood by some of the facilities. Also, the need for more stringent requirements was evaluated and some Code changes are recommended.

This report describes a new concept for integrated pollutant control: a cross-flow filter comprised of layered, gas permeable membranes that act a particulate filter, an SO{sub 2} sorbent, and a NO{sub x} reduction catalyst.

The reaction between tuffaceous groundwater and actinide-doped SRL 165 and PNL 76-68 type glasses in a gamma radiation field has been studied at 90 degrees C for periods up to 278 days. The primary effect of the radiation field was the acidification of the leachate through the production of nitrogen acids. Acidification of the leachate was limited by bicarbonate in the groundwater, for all exposures tested. Nonirradiated experiments were performed to represent the lowest limit of radiation exposure. Both irradiated and nonirradiated experiments were performed with and without a tuff monolith present in the reaction vessel. Neither irradiation nor the presence of tuff had a major effect on the extent of glass reaction as measured by the leachate concentrations of various glass species or analysis of the reacted glass surfaces. This report discusses the results of leaching experiments performed in a gamma radiation field and in the absence of a radiation field.

Two-phase flow patterns and frictional pressure gradients in flow in small, rectangular channels are being studies as part of a larger research program addressing phase-change heat transfer of pure refrigerants and refrigerant mixtures in plate-fin heat exchangers. Small rectangular flow channels were selected as representative of plain fin geometries. The particular channel reported herein has dimensions of 19.05 {times} 3.18 mm. Adiabatic flows of air/water mixtures, with the flow channel horizontal and the channel exit at near-atmospheric conditions, were utilized in the experiments. Analysis and interpretation of the pressure data relative to observed flow pattern transitions led to an objective method for determining the plug/bubble-to-slug flow transition. This method, together with visual observations, supplemented with photographic data, was used to develop a flow pattern man. A comparison of existing flow pattern maps for circular pipes, capillary tubes, and larger rectangular channels led to the conclusion that, while qualitative agreement exists, these maps are not generally applicable on a quantitative basis to the subject small rectangular channel. Two state-of-the-art correlations for frictional pressure gradient were evaluated, with particular emphasis on the practically important ranges of total mass quality and mass flux, from the standpoint of plate-fin heat exchangers designed as evaporators. …

This Special Report is the frost product of OTA assessment of international collaboration in defense technology. It provides an overview of the subject and analyzes the impact that changes in the environment of defense technology and reduced East-West tensions will exert on defense industrial cooperation and associated alliance relations.

Free-electron lasers as scientific instruments are reviewed. The present status and future prospects are delineated with attention drawn to the size, complexity, availability, and performance capability of this new tool. The Free-Electron Laser (FEL) was proposed by John Madey in 1970 (1), although earlier work, relevant to the concept, had been performed by Motz (2) and by Phillips (3). Experimental demonstration was achieved by Madey, et. al. in 1975 and 1976 (4). Since that time, FELs of diverse configurations have been operated at several laboratories around the world. At present, FEL development is focused in two directions: in constructing reliable FELs for scientific research and in extending FEL capability to vacuum ultra-violet (VUV) and even shorter wavelengths. In this article we shall only very briefly review the principles of an FEL, putting emphasis on those aspects that limit performance, after which we shall discuss the applications, present status and future prospects of FELs. Much material that we wish to present is in the form of Tables, and they are an essential part of this article.

If the 500 MW geothermal project on the Big Island of Hawaii is developed as planned, the Wao Kele O Puna rain forest will be severely damaged or destroyed. If this happens the State will lose one of its most precious resources. It would be tragic for this to happen, since on a least-cost basis, the geothermal project does not make economic sense. Improving energy efficiency in the commercial and residential sectors of Hawaii can save about 500 MW of power at a cost of $700 million.

This is a progress report for the past one year of research (year 3 of 5-year project) under the project titled CSDP: Seismology of Continental Thermal Regime'', in which we proposed to develop seismological interpretation theory and methods applicable to complex structures encountered in continental geothermal areas and apply them to several candidate sites for the Continental Scientific Drilling Project. The past year has been extremely productive especially in the area of interpretation theory, including the following two major break-throughs. One is the derivation of an integral equation for time-dependent power spectra, which unified all the existing theories on seismic scattering (including the radiative transfer theory for total energy and single and multiple scattering theories based on the ray approach) and offers more complete and economical solutions to the problems of seismic scattering and attenuation. The other is the new formula for synthetic seismograms for layered media with irregular interfaces, combining the T-matrix method for an arbitrary shaped inclusion and the method of global generalized reflection/transmission coefficients for layered media. Both breakthroughs will enable us to deal with seismic observations in complex earth structures more efficiently and accurately. In the area of experimental studies, we discovered seismic guided waves trapped …

This project plan for Phase II summarizes the design of a project to complete analysis of offsite Emergency Planning Zones (EPZ) for the Rocky Flats Plant. Federal, state, and local governments develop emergency plans for facilities that may affect the public in the event of an accidental release of nuclear or hazardous materials. One of the purposes of these plans is to identify EPZs where actions might be necessary to protect public health. Public protective actions include sheltering, evacuation, and relocation. Agencies use EPZs to develop response plans and to determine needed resources. The State of Colorado, with support from the US Department of Energy (DOE) and Rocky Flats contractors, has developed emergency plans and EPZs for the Rocky Flats Plant periodically beginning in 1980. In Phase II, Interim Emergency Planning Zones Analysis, Maximum Credible Accident'' we will utilize the current Rocky Flats maximum credible accident (MCA), existing dispersion methodologies, and upgraded dosimetry methodologies to update the radiological EPZs. Additionally, we will develop recommendations for EPZs for nonradiological hazardous materials releases and evaluate potential surface water releases from the facility. This project will allow EG G Rocky Flats to meet current commitments to the state of Colorado and make steady, …

This 1989 report contains monitoring data from routine radiological and nonradiological environmental surveillance activities. Summaries of significant environmental compliance programs in progress such as National Environmental Policy Act documentation, environmental permits, environmental restoration, and various waste management programs for Sandia National Laboratories in Albuquerque (SNL, Albuquerque) are included. The maximum offsite dose impact was calculated to be 8.8 {times} 10{sup {minus}4} mrem. The total Albuquerque population received a collective dose of 0.097 person-rem during 1989 from SNL, Albuquerque, operations. As in the previous year, SNL, Albuquerque, operations in 1989 had no adverse impact on the general public or on the environment. 46 refs., 20 figs., 31 tabs.

We have calibrated and studied the performance of the MARK II drift chamber vertex detector with cosmic ray tracks collected with the chamber inside the MARK II detector at the SLC. The chamber achieves 30 {mu}m impact parameter resolution and 500 {mu}m track-pair resolution using CO{sub 2}/C{sub 2}H{sub 6}H{sub 6}(92/8) at 2 atmospheres pressure. The chamber has successfully recorded Z{sup 0} decays at the SLC, and resolved tracks in dense hadronic jets with good efficiency and high accuracy. 5 refs., 13 figs.

This report is a summary of the environmental status of the Hanford Site in 1989. It includes descriptions of the Site and its mission, the status of compliance with environmental regulations, planning and activities to accomplish compliance, environmental protection and restoration activities, and environmental monitoring. 97 refs., 67 figs., 14 tabs.

The Nevada Operations Office (NV) is responsible for supporting the nuclear test programs of the Los Alamos and Lawrence Livermore National Laboratories. This support includes the drilling of test holes for nuclear device testing a the Nevada Test Site (NTS). The purpose of this audit was to assess the effectiveness of the Department of Energy's management of test hole inventories at the NTS. Our audit disclosed that NV accumulated a large inventory of unused test holes and approved drilling additional holes for which neither laboratory (Los Alamos nor Livermore) had identified a need. The overdrilling of test holes occurred because NV did not comply with good inventory practices that would have had NV's approving official question the need for, and the timing of, the laboratories' drilling requests. Instead, NV gave perfunctory approval to the laboratories' work orders for drilling test holes, and emphasized keeping two drill rig crews busy and satisfying the laboratories' demands for dedicated drilling personnel. Although NV did not agree that overdrilling had occurred, it has cut back its drilling activities and estimated that this will save abut $7.6 million annually. NV agreed with the recommendations in the report and has taken corrective actions.

An instrument capable of measuring the bulk temperature of a workpiece while it is being heated could have a variety of applications. If such an instrument were reasonably priced, it would have a tremendous impact upon national energy usage. The Department of Energy has realized the importance of this type of instrument and has sponsored three concurrent programs to evaluate three different technologies for this type of instrument. In one of these programs, Surface Combustion is the prime contractor to develop a pulsed laser, polarizing interferometer based sensor to be used as a workpiece temperature analyzer (WPTA). The overall goal of the program is to develop a workpiece temperature analyzer for industrial furnaces to significantly improve product quality, productivity and energy efficiency. The workpiece temperature analyzer concept in this program uses a pulsed laser polarizing interferometer (PLPI) for measuring sound velocity through a workpiece. This type of instrument has a high resolution and could detect surface motion of as small as 10 picometer. The sound velocity measurement can be converted to an average workpiece temperature through a mathematical equation programmed into the microprocessor used for control. 76 refs., 12 figs., 14 tabs.

An analysis of the proton rapidity distribution in central {sup 16}O+Au collisions at 60 GeV/n measured in the NA35 streamer chamber detector at the CERN SPS is presented. The charge excess of positive particles over negative particles was measured. The rapidity distribution of the charge excess which can be associated with the primordial protons in the collision is studied in terms of the nuclear stopping power and is compared to the predictions of various models. 7 refs., 2 figs.

During the development of the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), public comments were received regarding reduction of the discharge of liquid effluents into the soil column. As a result, the US Department of Energy (DOE), with concurrence of the Washington State Department of Ecology (WSDE)and the US Environmental Protection Agency (EPA), committed to a special project designed to document the discharge history and the charter of Hanford Site liquid discharges. The results of this project will be used in determining the need for additional waste stream analysis, and/or to negotiate additional milestones pertaining to such discharges in the Tri-Party Agreement. Wastestream sampling data collected prior to October 1989 were reported in the Waste Stream Characterization Report. Preliminary Stream-specific Reports were prepared which evaluated that data and proposed dangerous waste designations for each stream. This document contains the wastestream sampling and analysis data collected as part of the liquid effluent study. Data contained in this report were obtained from samples collected from October 1989 through March 1990. Information is presented on the wastestreams that have been sampled, the parameters analyzed, and the dates and times at which the samples were collected. This information will be evaluated in …

This paper summarizes the data generated by the NOXSO Life Cycle Test Unit (LCTU). The NOXSO process is a dry flue gas treatment system that employs a reusable sorbent. The sorbent consists of sodium carbonate impregnated on a high-surface-area gamma alumina. A fluidized bed of sorbent simultaneously removes SO{sub 2} and NO{sub x} from flue gas at a temperature of 250{degrees}F. The spent sorbent is regenerated for reuse by treatment at high temperature with a reducing gas. This regeneration reduces sorbed sulfur compounds to SO{sub 2}, H{sub 2}S, and elemental sulfur. The SO{sub 2} and H{sub 2}S are then converted to elemental sulfur in a Claus-type reactor. The sulfur produced is a marketable by-product of the process. Absorbed nitrogen oxides are decomposed and evolved on heating the sorbent to regeneration temperature.

The integrity of the SRS reactor tanks is a key factor affecting their suitability for continued service since, unlike the external piping system and components, the tanks are virtually irreplaceable. Cracking in various areas of the process water piping systems has occurred beginning in about 1960 as a result of several degradation mechanisms, chiefly intergranular stress corrosion cracking (IGSCC) and chloride-induced transgranular cracking. The purpose of this inspection was to determine if selected welds in the K Reactor tank wall contained any indications of IGSCC. These portions included areas in and beyond the weld HAZ, extending out as far as two to three inches from the centerline of the welds, plus selected areas of base metal at the intersection of the main tank vertical and mid-girth welds. No evidence of such degradation was found in any of the areas examined. This inspection comprised approximately 60% of the accessible weld length in the K Reactor tank. Initial setup of the tank, which prior to inspection contained Mark 60B target assemblies but no Mark 22 fuel assemblies, began on January 14, 1990. The inspection was completed on March 9, 1990.

This report summarizes the environmental monitoring program at Pantex Plant for 1989. It has been prepared in accordance with the United States Department of Energy Order 5400.1. This report presents monitoring data for both radioactive and nonradioactive species in the local environment. Plant activities involve the handling of significant quantities of uranium, plutonium, and tritium in the form of completed parts received from other DOE facilities, resulting in a very low potential for release of these radionuclides to the atmosphere. In May 1989, there was an accidental release of 40,000 curies (Ci) of tritium (conservatively estimated). The normal releases during the year were 0.12 Ci of tritium and 21 {mu}Ci of uranium-238. The USEPA issued a draft Administrative Order of Consent under section 3008(h) in 1988. Negotiations between DOE and EPA are still continuing. Chromium at a level above drinking water standards was found in a perched groundwater well in zone 12. Also, trace amounts of solvents and high explosives were found in the perched groundwater in zone 12. 12 refs., 10 figs., 53 tabs.

In the context of Heavy Higgs searches in the decay mode H {yields} ZZ {yields} 4e, electron identification issues and their implications on detector design are discussed (though many of the issues are valid for muon modes as well). The backgrounds considered seem manageable (a net rejection of 100 for combined electron ID and isolation cut is needed and seems fairly straightforward). A detector must have wide electron rapidity coverage {eta} < 2.5 to 3 and the ability to identify and measure an electron with P{sub T} > GeV; be hermetic (in the sense of minimizing regions where electrons can disappear through cracks, dead spaces, or poorly placed walls); and have high efficiency electron ID ({approximately} 0.90) since we are trying to be sensitive to a feeble signal and we need 4 electrons. The product of a number of fairly high acceptances based on optimistic estimates still yields in the end a net Higgs acceptance about 0.15 to 0.25 depending on how hermetic a detector is assumed. For M{sub Higgs} < 500 GeV, this may be tolerable; whereas, for higher Higgs masses, the situation is much less clear.

Gamma-ray damage to tank walls is typically more severe in D{sub 2}O than in H{sub 2}O moderated lattices because of the much higher ratios of slow-to-fast neutron flux. To estimate this effect it was first necessary to develop energy dependent gamma-ray displacement cross sections for iron. These, along with coupled neutron-gamma-ray transport computations, provided a measure of displacement damage from this source in SRS reactor tank walls. Gamma-ray displacements originating from high energy gammas from neutron capture in and near the tank wall exceeded those from gamma rays created in the reactor core. The displacements from the combined gamma sources ranged from 13% to 16% of that due to iron atom recoil following neutron capture. 8 refs., 2 figs., 2 tabs.

The program objective is to demonstrate efficient removal of fine particulates to sufficiently low levels to meet proposed small scale coal combustor emission standards. This is to be accomplished using a novel particulate removal device, the Confined Vortex Scrubber (CVS). The CVS consists of a cylindrical vortex chamber with tangential flue gas inlets. The clean gas exit is via tangent slots in a central tube. Liquid is introduced into the chamber and is confined with the vortex chamber by the centrifugal force generated by the gas flow itself. This confined liquid forms a layer through which the flue gas is then forced to bubble, producing a strong gas/liquid interaction, high inertial separation forces and efficient particulate cleanup. In effect, each of the sub-millimeter diameter gas bubbles in the liquid layer acts as a micro-cyclone, inertially separating particles into the surrounding liquid. The CVS thus obtains efficient particle removal by forcing intimate and vigorous interaction between the particle laden flue gas and the liquid scrubbing medium.