This thesis describes the results of a search for new leptons with associated heavy neutrinos. The search uses 68.1 pb/sup /minus/1/ of data taken with the TPC2..gamma.. detector at the PEP storage ring. New lepton pairs with charged lepton masses m/sub L/ < 12 GeV and mass differences in the approximate range 0.4 GeV < m/sub L/ /minus/ m/sub/nu/L/ < 2.5 GeV are excluded at the 99% confidence level. Results are also given of a study of search techniques for the region m/sub L/ < 12 GeV, m/sub L/ /minus/ m/sub ..nu..L/ < 0.4 GeV.

The design of the Target Fabrication Tritium Laboratory for deuterium-tritium fuel processing for laser fusion targets has been accomplished with the intent of providing redundant safeguard systems. The design of the tritium laboratory is based on a combination of tritium handling techniques that are currently used by experienced laboratories. A description of the laboratory in terms of its interrelated processing systems is presented to provide an understanding of the design features for safe operation.

The 300 Area was selected as a location for an IFC because it offers excellent opportunities for field research on the influence of mass-transfer processes on uranium in the vadose zone and groundwater. The 300 Area was the location of nuclear fuel fabrication facilities and has more than 100 waste sites. Two of these waste sites, the North and South Process Ponds received large volumes of process waste from 1943 to 1975 and are thought to represent a significant source of the groundwater uranium plume in the 300 Area. Geophysical surveys and other characterization efforts have led to selection of the South Process Pond for the IFC.

Borehole seismology is the highest resolution geophysical imaging technique available today to the oil and gas industry for characterization and monitoring of oil and gas reservoirs. However, the industry's ability to economically do high resolution 3D imaging of deep and complex gas reservoirs using borehole seismology is currently hampered by the lack of the acquisition technology necessary to record the large volumes of the high frequency, high signal-to-noise-ratio borehole seismic data needed to do 3D imaging. This project takes direct aim at this shortcoming by developing a 400 level 3C clamped downhole seismic receiver array, and accompanying software, for borehole seismic 3D imaging. This large borehole seismic array will remove the technical acquisition barrier for recording the necessary volumes of data to do high resolution 3D VSP or 3D cross well seismic imaging. Massive 3D VSP{reg_sign} and long range Cross-Well Seismology (CWS) are two of the borehole seismic techniques that will allow the Gas industry to take the next step in their quest for higher resolution images of the gas reservoirs for the purpose of improving the recovery of the natural gas resources. Today only a fraction of the original Oil or Gas in place is produced when reservoirs are …

The Supernova Science Center (SNSC) was founded in 2001 to carry out theoretical and computational research leading to a better understanding of supernovae and related transients. The SNSC, a four-institutional collaboration, included scientists from LANL, LLNL, the University of Arizona (UA), and the University of California at Santa Cruz (UCSC). Intitially, the SNSC was funded for three years of operation, but in 2004 an opportunity was provided to submit a renewal proposal for two years. That proposal was funded and subsequently, at UCSC, a one year no-cost extension was granted. The total operational time of the SNSC was thus July 15, 2001 - July 15, 2007. This document summarizes the research and findings of the SNSC and provides a cummulative publication list.

In light water reactors, components made of nickel-base alloys are susceptible to environmentally assisted cracking. This report summarizes the crack growth rate results and related metallography for field and laboratory-procured Alloy 600 and its weld alloys tested in pressurized water reactor (PWR) environments. The report also presents crack growth rate (CGR) results for a shielded-metal-arc weld of Alloy 182 in a simulated PWR environment as a function of temperature between 290 C and 350 C. These data were used to determine the activation energy for crack growth in Alloy 182 welds. The tests were performed by measuring the changes in the stress corrosion CGR as the temperatures were varied during the test. The difference in electrochemical potential between the specimen and the Ni/NiO line was maintained constant at each temperature by adjusting the hydrogen overpressure on the water supply tank. The CGR data as a function of temperature yielded activation energies of 252 kJ/mol for a double-J weld and 189 kJ/mol for a deep-groove weld. These values are in good agreement with the data reported in the literature. The data reported here and those in the literature suggest that the average activation energy for Alloy 182 welds is on the …

U.S. industry consumes approximately 37 percent of thenation's energy to produce 24 percent of the nation's GDP. Increasingly,society is confronted with the challenge of moving toward a cleaner, moresustainable path of production and consumption, while increasing globalcompetitiveness. Technology is essential in achieving these challenges.We report on a recent analysis of emerging energy-efficient technologiesfor industry, focusing on over 50 selected technologies. The technologiesare characterized with respect to energy efficiency, economics andenvironmental performance. This paper provides an overview of theresults, demonstrating that we are not running out of technologies toimprove energy efficiency, economic and environmental performance, andneither will we in the future. The study shows that many of thetechnologies have important non-energy benefits, ranging from reducedenvironmental impact to improved productivity, and reduced capital costscompared to current technologies.

The Phase I objectives were fully achieved the execution of a program that included the: • Development of a comprehensive model of the sonic drill technology and interaction of the dynamic drilling parameters with the impedance of the earth. • Operation and measurement of the sonic drilling process in the field at full scale. • Comparison of the analytical and experimental results to form an objective and quantified approach to describe the fundamental phenomena and to develop a methodology for automated control of the sonic drilling process. • Conceptual design of a modular sonic drilling system that can be transported to remote sites by helicopter. As a result, the feasibility of a commercially viable sonic drilling technology that can produce microholes up to 1,500 feet in depth, and that is field deployable to remote, environmentally sensitive sites via a helicopter, has been demonstrated.

This report disucsses the development of on-line state and parameter estimators used to analyze the structural response of buildings. The estimator/identifier is an extended Kalman filter (EKF), which has been applied with great success in other technological areas. It is shown that the EKF can perform quite well on simulated noisy structural response data.

A detailed study of the low beta insertion for the B0 experimental area has been carried out and is described below. This insertion is similar to the Type C low beta previously report, anti p Note 169, although some changes have been made to the quadrupole lengths and positions. This insertion is designated Type E. The purpose of the study was to see if it is possible to turn the insertion on in a smooth and continuous manner and tune the insertion to a value of ..beta..* of less than one meter while maintaining the overall tune of the j Tevatron to a constant value. This was found to be possible. An examination of chromaticity corrections for the Tevatron with the low beta insertion on in various configurations was also undertaken.

The cyclone incinerator was operated throughout the past quarter, generating additional data on system characteristics, equipment life expectancies, and by-product generation. Several changes in the incinerator system are in various stages of completion. The lid assembly, secondary chamber, and expansion unit for the new exhaust equipment are nearly ready for installation. A new heat exchanger has been installed in the scrubber system. An ash handling system has been designed for possible future addition to the system. Continuing studies will determine the best delivery mechanism for continuously feeding the cyclone incinerator. Preliminary investigations are being conducted to select an independent system to treat incinerator scrubber solution for recycling and to remove salts and sludge for disposal. Metal samples of two possible materials for incinerator construction were examined for corrosion degradation suffered at the incinerator exhaust outlet. Controlled experiments were conducted on the pressed ash-cement pellet matrix to define compressive strength, mechanical stability, density, and effect of curing environment (wet cure and dry cure). Leachability studies were initiated on pressed sludge/cement matrix in distilled water at ambient temperature. Compressive strengths of sludge/cement pressed matrix samples were investigated. Physical and chemical attributes of incinerated ash were evaluated in relationship to the ash/cement matrix.

Progress is reported on the following: well conditions; perforating and cementing; temperature-depth plot; slotted liner, well head and auxiliary equipment; well testing and analysis program; well monitoring during standby; environmental assessment; time schedule; and budgets. (MHR)

The FRS is a pool structure and enclosing building constructed in 1966 for storing spent nuclear fuel. The enclosing building was not analyzed. The pool structure's responses to operating loads, seismic excitation, and an accidentally dropped cask were determined. Locations in the FRS pool were identified where structural strength would be exceeded in the event of an earthquake of 0.2 g maximum ground acceleration or an accident in which a cask dropped from the maximum height of the crane hook used to maneuver it. 25 figures, 4 tables.

TMX experimental data on ambipolar potential control and on the accompanying electrostatic confinement are reported. New results on the radial dependence of the central-cell confining potential are given. Radial and axial particle losses as well as scaling of the central-cell axial confinement are discussed.

The laboratory cyclone incinerator, which started operation in January, 1978, has been developed to study the effects of burning feed containing radionuclides other than /sup 238/Pu. These isotopes must be removed from the off-gas during incineration. Preliminary data from early runs show that the combustion efficiency of the incinerator can still be improved. Controlled experiments were conducted on the pressed ash-cement pellet matrix to define compressive strength, mechanical stability, density, and effect of curing environment (wet cure and dry cure). Leachability studies were initiated on pressed sludge/cement matrix in distilled water at ambient temperature. Compressive strengths of sludge/cement pressed matrix samples were investigated. Physical and chemical attributes of incinerated ash were evaluated in relationship to the ash/cement matrix. 7 figs., 6 tables.

Well 199-N-81 was drilled in 1993 as a RCRA groundwater monitoring for the 1324-N network. The well is completed at the top of the uppermost aquifer, in the Ringold Formation. This data package includes information on drilling, construction, development, and aquifer testing. Copies of forms, notes, and diagrams completed in the field comprise the bulk of this document. Few interpretations are included. Lithologic contacts were picked by the site geologist. An attempt was made to interpret aquifer test data.

Metallic thorium uranium fuel elements continue to show excellent irradiation performance in high temperature pressurized water coolant. Volume expansion measurements made after 2.1{times}10{sup 20} fissions/cm{sup 3} (6200 MWD/T) at fuel temperatures above 500 C shows no indication of fission gas-in-duced swelling. Analysis of fuel swelling data from tubular elements shows apparent effect of geometry (restraint) on both low temperature volume expansion and the temperature at which accelerated volume expansion initiates. Evidence of grain boundary tearing has been observed in tubular metallic uranium fuels irradiated in 1600 pos water coolant. Volume expansion due to two types of structural damage have ben observed uranium - 2 w/o zirconium alloy irradiated to 0.25 a/o burnup at temperatures up to 550 C.

Under simplifying assumptions, an expression is obtained relating the integrated kinetic energy transferred to moderator atoms to the thermal neutron exposure in adjacent fuel. Reactor-dependent factors are explicit in the expression which make it possible to compare graphite contraction data from different reactors or to estimate graphite damage in a new reactor based oil observed damage in existent reactors. Graphite temperature, which may be an important factor in graphite contraction, is not considered as one of the variables in this report. Also, the damage dependency on neutron energy is not dealt with in great detail because of the relatively unknown facts in this regard. A particular application of concern at the present is to determine the pertinent factors relating to fast neutron exposure in the NPR to assist in determining the integrated damage over the life of the pile.

Following is a modification of the IFEFUEL systems code, called IFEFUEL2, to treat specifically the HYLIFE-II target chamber concept. The same improved Recirculating Induction Accelerator (RIA) energy scaling model developed recently by Bieri is used in this survey of the economics of multi-unit IFE plants producing both electricity and hydrogen fuel. Reference cases will assume conventional HI-indirect target gains for a 2 mm spot, and improved HYLIFE-II BoP models as per Hoffman. Credits for improved plant availability and lower operating costs due to HYLIFE-II`s 30-yr target chamber lifetime are included, as well as unit cost reductions suggested by Delene to credit greater {open_quotes}learning curve{close_quotes} benefits for the duplicated portions of a multi-unit plant. To illustrate the potential impact of more advanced assumptions, additional {open_quotes}advanced{close_quotes} cases will consider the possible benefits of an MHD + Steam BoP, where direct MHD conversion of plasma from baseball-size LiH target blanket shells is assumed to be possible in a new (as yet undesigned) liquid Flibe-walled target chamber, together and separately, with advanced, higher-gain heavy-ion targets with Fast Ignitors. These runs may help decide the course of a possible future {open_quotes}HYLIFE-III{close_quotes} IFE study. Beam switchyard and final focusing system costs per target chamber are assumed …

This document contains information about the sampling program at Columbia River during May 5, 1944. Topics discussed include: securing representative samples; analysis of the samples looking at temperature, bacteriological content, dissolved oxygen, and physical tests; and the method and equipment used in the sampling procedure.

None

Reactor fuels, reactor engineering, radiological engineering, process technology, and operational physics progress is reported for irradiation and testing at the Hanford production reactors.

During the week of March 1, 1965, KW Reactor shut down with indications of a tube leak. Leak testing during the shutdown indicated a front Van Stone flange leak on tube 3065 and a suspect internal leak on tube 3075. During the tube removal process, there was indication of Zircaloy embrittlement on both tubes. Subsequent metallographic examination of samples taken from these tubes indicated the presence of case hydriding on the internal tube surface extending from approximately the end of the active fuel corn to the rear Van Stone flange. Vacuum analysis of selected samples revealed the total hydrogen concentration, including the hydrogen present in the hydrided layer, ranged from approximately 50 ppm at the end of the active charge location to approximately 1300 ppm at the rear Van Stone flange, Since examination of these first two Zircaloy tubes removed from KW Reactor, two additional tubes have been removed from KW Reactor, two tubes have been removed from KE Reactor, and one C-size Zircaloy tube has been removed from C Reactor. The presence of hydriding has been observed on the seven Zircaloy-2 tubes removed to date. It is the purpose of this document to review in some detail the data …

Using a {sup 137}Cs source we have determined the position of two of the source tubes embedded in the Pb absorber in the cast EMC module used in the Fermilab test beam. Two scintillator tiles placed in the gaps on both sides of an absorber containing a source tube were readout into independent phototubes. The difference in scintillator response was measured in two towers at two different source tube layers. We find the source tube to be displaced towards the (radial) front of the EMC by about 1.6 mm in both measurements. Work is proceeding now to check other source tubes in other locations.