Recent research has been directed towards finding means to produce neutron emissions at will, to demonstrate reproducibility, and to permit in-depth studies of the origin of neutron emissions. this goal has been pursued in the Kamiokande detector in Japan and has led to the development of a deep underground laboratory in a tunnel in the Wasatch mountains near Brigham Young University. New counters for low-level neutron emissions are being utilized. Calorimetric tools have also been developed.

It has recently been brought to our attention that the LiYf{sub 4} (YLF) laser rods utilized in the alignment lasers of Nova tend to thin after several years of being exposed to the cooling water solution. As a consequence of this situation the YLF laser rods must occasionally be replaced. Since they found that they were able to minimize the dissolution rate for another fluoride crystal, Cr:LiSrAlF{sub 6} or Cr:LiSAF, by controlling the pH of the solution, they sought to determine if a similar fix could be applied to YLF laser crystals as well. For the case of Cr:LiSAF, the dissolution rate was observed to vary over 3 orders of magnitude depending on the pH, and a pH = 7 solution was determined to be optimal for improving the durability.

Synchrotron-based reflectometry is an important technique for the precise determination of optical properties of reflective multilayer coatings for Extreme Ultraviolet Lithography (EUVL). Multilayer coatings enable normal incidence reflectances of more than 65% in the wavelength range between 11 and 15 nm. In order to achieve high resolution and throughput of EUVL systems, stringent requirements not only apply to their mechanical and optical layout, but also apply to the optical properties of the multilayer coatings. Therefore, multilayer deposition on near-normal incidence optical surfaces of projection optics, condenser optics and reflective masks requires suitable high-precision metrology. Most important, due to their small bandpass on the order of only 0.5 nm, all reflective multilayer coatings in EUVL systems must be wavelength-matched to within {+-}0.05 nm. In some cases, a gradient of the coating thickness is necessary for wavelength matching at variable average angle of incidence in different locations on the optical surfaces. Furthermore, in order to preserve the geometrical figure of the optical substrates, reflective multilayer coatings need to be uniform to within 0.01 nm in their center wavelength. This requirement can only be fulfilled with suitable metrology, which provides a precision of a fraction of this value. In addition, for the detailed …

Thin-walled, compliant plastic structures for meso-scale fluidic systems were fabricated, tested and used to demonstrate valving, pumping, metering and mixing. These structures permit the isolation of actuators and sensors from the working fluid, thereby reducing chemical compatibility issues. The thin-walled, compliant plastic structures can be used in either a permanent, reusable system or as an inexpensive disposable for single-use assay systems. The implementation of valving, pumping, mixing and metering operations involve only an elastic change in the mechanical shape of various portions of the structure. Advantages provided by the thin-walled plastic structures include reduced dead volume and rapid mixing. Five different methods for fabricating the thin-walled plastic structures discussed including laser welding, molding, vacuum forming, thermal heat staking and photolithographic patterning techniques.

We calculate nuclear pairing gaps for ground-state configurations for 8979 nuclei from {sup 16}O to A = 339 in the Lipkin-Nogami pairing model. The energy levels required for the calculation are obtained from the folded-Yukawa single-particular model for ground-state shapes obtained in the macroscopic-microscopic approach by minimizing the total potential energy with respect to {epsilon}{sub 2},{epsilon}{sub 4}, {epsilon}{sub 3} and {epsilon}{sub 6} shape degrees of freedom. We study the behavior of the calculated pairing gap {Delta} and the number-fluctuation constant {lambda}2 on neutron number N and proton number Z. We discuss alternative methods for comparing calculated pairing gaps to odd-even experimental mass differences and study the trends of the deviations between calculated and measured quantities versus N and Z. In particular we discuss the many non-smooth contributions to the so-called experimental pairing gap that is extracted from odd-even measured mass differences and the resulting difficulties that are present when these axe compared to calculated results. In recent years several studies have investigated whether nuclear pairing depends on neutron excess. Furthermore, any dependence on neutron excess is small compared to both the random and the correlated errors in the pairing gaps that are extracted from experimental odd-even mass differences. Therefore appropriate …

This volume documents model parameters chosen as of July 1992 that were used by the Performance Assessment Department of Sandia National Laboratories in its 1992 preliminary performance assessment of the Waste Isolation Pilot Plant (WIPP). Ranges and distributions for about 300 modeling parameters in the current secondary data base are presented in tables for the geologic and engineered barriers, global materials (e.g., fluid properties), and agents that act upon the WIPP disposal system such as climate variability and human-intrusion boreholes. The 49 parameters sampled in the 1992 Preliminary Performance Assessment are given special emphasis with tables and graphics that provide insight and sources of data for each parameter.

Using box-shaped profiles created by laser melt annealing, the authors investigate the kinetics of arsenic activation and deactivation. They find deactivation shows no history effects, which can be consistent either with clustering or precipitation for the cases considered. For activation, they notice it occurs on very short time scales, followed by a slower deactivation process. This is suggestive evidence that at least some precipitation occurs.

The overall objective of the Project is the expedited commercialization of advanced coal-fired low-emission boiler systems. The specified primary objectives are: NOx emissions not greater than one-third NSPS; SOx emissions not greater than one-third NSPS; and particulate emissions not greater than one-half NSPS. The specific secondary objectives are: improved ash disposability and reduced waste generation; reduced air toxics emissions; and increased generating efficiency. The final deliverables are a design data base that will allow future coal-fired power plants to meet the stated objectives and a preliminary design of a commercial generation unit.

The purpose of this memo is to highlight an alternative to the approach for cw laser paint removal. The point to be made is that a direct diode design is feasible and can be far more competitive than a solid-state laser based system. Through by-passing the use of a solid-state laser media, we immediately gain a factor of about five in system efficiency based on measured optical-to-optical efficiencies of our average power diode pumped lasers. This permits a massive reduction in system cooling requirements. It should be noted that cooling system size was the greatest concern voiced by Gordon McFadden at Hobart Lasers with regards to his Nd:YAG laser systems operated in field applications. Furthermore, with direct diode use far fewer diode packages will be needed to deliver a given amount of wattage on the target. This will largely eliminate the intimidating sticker shock and shorten (proportionally by the diode count) the required run-to-fail times demanded of the system.

The objectives of the surveys were to locate subsurface obstructions that may affect the drilling of two holes to be fit with flow meters in the 100-H Area of the Hanford Site (Figure 1). Possible drill sites with the least likelihood of encountering identified obstructions were identified based upon the results of the survey. Ground-penetrating radar (GPR) was the method selected for the investigations. The electromagnetic induction method was also used to verify that the general site is relatively void of metallic debris at depth.

This document explains the tank waste sampling strategy needed to obtain the information required to identify and develop pretreatment and waste immobilization processes. The key tenet of the strategy is that process testing with real waste material from the Hanford Site underground tanks is necessary to design processes and measure their effectiveness. This document provides the criteria for selection of the limited number of tanks to be sampled. A phased, iterative approach is used for the single-shell tank (SST) waste sampling. In the first sampling phase, samples are taken from 25 tanks which provide a good representation of the waste types of interest. Results from process testing of these samples will be considered in final selection of a limited number of additional SSTs to sample (currently expected to be an additional 14 tanks).

Recent research has been directed towards finding means to produce neutron emissions at will, to demonstrate reproducibility, and to permit in-depth studies of the origin of neutron emissions. this goal has been pursued in the Kamiokande detector in Japan and has led to the development of a deep underground laboratory in a tunnel in the Wasatch mountains near Brigham Young University. New counters for low-level neutron emissions are being utilized. Calorimetric tools have also been developed.

Vacuum extraction is an environmental restoration technique that is currently being applied to the remediation of soils and shallow segments that are contaminated with volatile constituents. In 1987, a h study was performed to evaluate the performance and potential applicability of this technology at the Savannah River Site (SRS). Vacuum extraction is useful when volatile constituents are present in the vadose zone. The technology has been used to remediate a number of sites across the country, including leading underground storage tanks, spill sites, landfill, and production facilities. The primary objective of the pilot study was to test the performance of the technology under the conditions specific to many of the potential areas of application at SRS. There is only a limited body of literature documenting field studiesin similar environments with in sands and clayey zones and a relatively thick vadose zone. Careful studies of this type are needed to develop full scale designs at SRS. The vacuum extraction pilot study at SRS was performed by a mm consisting of technical representatives of the Environmental Sciences Section in the Savannah River Laboratory (SRL), the Raw Materials Engineering and Technology Section of SRS, and TerraVac Inc., a subcontractor with experience in this …

This report is intended to establish a baseline for the sample analyses to be completed by the 222-S, WSCF, 325, and LITCO laboratories during FY 1995. These analyses are intended to support the Hanford Environmental Restoration. The work covered by this report focuses on 5 Sample Categories (Environmental Remediation, Liquid Effluents, Solid Waste, TWRS, and Process Support).

This Project-Specific Project Management Plan describes the project management methods and controls used by the WHC Projects Department to manage Project 03-F-031. The Sodium Storage Facility provides for storage of the 260,000 gallons of sodium presently in the FFTF Plant. The facility will accept the molten sodium transferred from the FFTF sodium systems, and store the sodium in a solid state under an inert cover gas until such time as a Sodium Reaction Facility is available for final disposal of the sodium.

The 324 Building in the Hanford 300 Area contains Radiochemical Engineering Cells and High Level Vault tanks (the {open_quotes}REC/HLV{close_quotes}) for research and development activities involving radioactive materials. Radioactive mixed waste within this research installation, found primarily in B-Cell and three of the high level vault tanks, is subject to RCRA/DWR ({open_quotes}RCRA{close_quotes}) regulations for storage. This white paper provides a baseline RCRA compliance summary of MW management in the REC/HLV, based on best available knowledge. The REC/HLV compliance project, of which this paper is a part, is intended to achieve the highest degree of compliance practicable given the special technical difficulties of managing high activity radioactive materials, and to assure protection of human health and safety and the environment. The REC/HLV was constructed in 1965 to strict standards for the safe management of highly radioactive materials. Mixed waste in the REC/HLV consists of discarded tools and equipment, dried feed stock from nuclear waste melting experiments, contaminated particulate matter, and liquid feed stock from various experimental programs in the vault tanks. B-Cell contains most of these materials. Total radiological inventory in B-Cell is estimated at 3 MCi, about half of which is potentially {open_quotes}dispersible{close_quotes}, that is, it is in small pieces or …

This Acceptance Test Report (ATR) is for the Link Belt LS-518 Crane Hook Position/Rate Indication System.

Vacuum extraction is an environmental restoration technique that is currently being applied to the remediation of soils and shallow segments that are contaminated with volatile constituents. In 1987, a h study was performed to evaluate the performance and potential applicability of this technology at the Savannah River Site (SRS). Vacuum extraction is useful when volatile constituents are present in the vadose zone. The technology has been used to remediate a number of sites across the country, including leading underground storage tanks, spill sites, landfill, and production facilities. The primary objective of the pilot study was to test the performance of the technology under the conditions specific to many of the potential areas of application at SRS. There is only a limited body of literature documenting field studiesin similar environments with in sands and clayey zones and a relatively thick vadose zone. Careful studies of this type are needed to develop full scale designs at SRS. The vacuum extraction pilot study at SRS was performed by a mm consisting of technical representatives of the Environmental Sciences Section in the Savannah River Laboratory (SRL), the Raw Materials Engineering and Technology Section of SRS, and TerraVac Inc., a subcontractor with experience in this …

This report addresses the coupling and alignment of the PHENIX experiment solenoid in RHIC.

According to one of Maldacena's dualities, type IIB string theory on AdS{sub 3} x S{sup 3} x K3 is equivalent to a certain N = (4, 4) superconformal field theory. In this note we compute the elliptic genus of the boundary theory in the supergravity approximation. A finite quantity is obtained once we introduce a particular exclusion principle. In the regime where the supergravity approximation is reliable, we find exact agreement with the elliptic genus of a sigma model with target space K3{sup N}/S{sub N}.

Exposure scenarios are defined to identify potential pathways and combinations of pathways that could lead to radiation exposure from immobilized tank waste. Appropriate data and models are selected to permit calculation of dose factors for each exposure

Spherical harmonic solutions of order 5, 9 and 21 on spatial grids containing up to 3.3 million cells are presented for the Kobayashi benchmark suite. This suite of three problems with simple geometry of pure absorber with large void region was proposed by Professor Kobayashi at an OECD/NEA meeting in 1996. Each of the three problems contains a source, a void and a shield region. Problem 1 can best be described as a box in a box problem, where a source region is surrounded by a square void region which itself is embedded in a square shield region. Problems 2 and 3 represent a shield with a void duct. Problem 2 having a straight and problem 3 a dog leg shaped duct. A pure absorber and a 50% scattering case are considered for each of the three problems. The solutions have been obtained with Ardra, a scalable, parallel neutron transport code developed at Lawrence Livermore National Laboratory (LLNL). The Ardra code takes advantage of a two-level parallelization strategy, which combines message passing between processing nodes and thread based parallelism amongst processors on each node. All calculations were performed on the IBM ASCI Blue-Pacific computer at LLNL.

This data package presents sampling data and analytical results from the September 22 and 27, 1999, headspace vapor sampling of Hanford Site Tank 241-2-361 during sludge core removal. The Lockheed Martin Hanford Corporation (LMHC) sampling team collected the samples and Waste Management Laboratory (WML) analyzed the samples in accordance with the requirements specified in the 241-2361 Sludge Characterization Sampling and Analysis Plan, (SAP), HNF-4371, Rev. 1, (Babcock and Wilcox Hanford Corporation, 1999). Six SUMMA{trademark} canister samples were collected on each day (1 ambient field blank and 5 tank vapor samples collected when each core segment was removed). The samples were radiologically released on September 28 and October 4, 1999, and received at the laboratory on September 29 and October 6, 1999. Target analytes were not detected at concentrations greater than their notification limits as specified in the SAP. Analytical results for the target analytes and tentatively identified compounds (TICs) are presented in Section 2.2.2 starting on page 2B-7. Three compounds identified for analysis in the SAP were analyzed as TICs. The discussion of this modification is presented in Section 2.2.1.2.

This sampling and analysis plan (SAP) identifies characterization objectives pertaining to sample collection, laboratory analytical evaluation, and reporting requirements for grab samples obtained to address waste compatibility. It is written in accordance with requirements identified in Data Quality Objectives for Tank Farms Waste Compatibility Program (Mulkey et al. 1999) and Tank Farm Waste Transfer Compatibility Program (Fowler 1999). In addition to analyses to support Compatibility, the Waste Feed Delivery program has requested that tank samples obtained for Compatibility also be analyzed to confirm the high-level waste and/or low-activity waste envelope(s) for the tank waste (Baldwin 1999). The analytical requirements to confirm waste envelopes are identified in Data Quality Objectives for TWRS Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for Low-Activity Waste Feed Batch X (Nguyen 1999a) and Data Quality Objectives for RPP Privatization Phase I: Confirm Tank T is an Appropriate Feed Source for High-Level Waste Feed Batch X (Nguyen 1999b).