This report documents user instructions for several simplified subroutines and driver programs that can be used to estimate various aspects of the long-term performance of cement-based barriers used in low-level radioactive waste disposal facilities. The subroutines are prepared in a modular fashion to allow flexibility for a variety of applications. Three levels of codes are provided: the individual subroutines, interactive drivers for each of the subroutines, and an interactive main driver, CEMENT, that calls each of the individual drivers. The individual subroutines for the different models may be taken independently and used in larger programs, or the driver modules can be used to execute the subroutines separately or as part of the main driver routine. A brief program description is included and user-interface instructions for the individual subroutines are documented in the main report. These are intended to be used when the subroutines are used as subroutines in a larger computer code.

Sandia National Laboratories has been involved with rocket systems for many years. Some of these systems have carried high explosive onboard, while others have had FTS for destruction purposes whenever a potential hazard is detected. Recently, Sandia has also been involved with flight tests in which a target vehicle is intentionally destroyed by a projectile. Such endeavors always raise questions about the safety of personnel and the environment in the event of a premature detonation of the explosive or an activation of the FTS, as well as intentional vehicle destruction. Previous attempts to investigate fragmentation hazards for similar configurations have analyzed fragment size and shape in detail but have computed only a limited number of trajectories to determine the probabilities of impact and casualty expectations. A computer program SAFETIE has been written in support of various SNL flight experiments to compute better approximations of the hazards. SAFETIE uses the AMEER trajectory computer code and the Engineering Sciences Center LAN of Sun workstations to determine more realistically the probability of impact for an arbitrary number of exclusion areas. The various debris generation models are described.

Elementary particle physics experiments often have to deal with high data rates. In order to avoid having to write out all data that is occurring online processors, triggers, are used to cull out the uninteresting data. These triggers are based on some particular aspect of the physics being examined. At times these aspects are often equivalent to simple pattern recognition problems. The reliability of artificial neural networks(ANNs) in pattern recognition problems in many fields has been well demonstrated. We present here the results of a study on the feasibility of using ANNs as an online trigger for high energy physics experiments.

The purpose of scientific visualization is to simplify the analysis of numerical data by rendering the information as an image. Even when the image is familiar, as in the case of terrain data, preconceptions about what the image should look like and deceptive image artifacts can create misconceptions about what information is actually contained in the scene. One way of aiding the development of unambiguous visualizations is to add stereoscopic depth to the image. Despite the recent proliferation of affordable stereoscopic viewing equipment, few researchers are at this time taking advantage of stereo in their visualizations. It is generally perceived that the rendering time will have to be doubled in order to generate the pair, and so stereoscopic viewing is sacrificed in the name of expedient rendering. We show that this perception is often invalid. The second half of a stereoscopic image can be generated from the first half for a fraction of the computational cost of complete rendering, usually no more than 50% of the cost and in many cases as little as 5%. Using the techniques presented here, the benefits of stereoscopy can be added to existing visualization systems for only a small cost over current single-frame rendering …

The Utility Battery Storage Systems Program, sponsored by the US Department of Energy (DOE), is addressing needed improvements so that the full benefits of these systems can be realized. A key element of the Program is the quantification of the benefits of batteries used in utility applications. The analyses of the applications and benefits are ongoing, but preliminary results indicate that the widespread introduction of battery storage by utilities could benefit the US economy by more than $26 billion by 2010 and create thousands of new jobs. Other critical elements of the DOE Program focus on improving the batteries, power electronics, and control subsystems and reducing their costs. These subsystems are then integrated and the systems undergo field evaluation. Finally, the most important element of the Program is the communication of the capabilities and benefits of battery systems to utility companies. Justifiably conservative, utilities must have proven, reliable equipment that is economical before they can adopt new technologies. While several utilities are leading the industry by demonstrating battery systems, a key task of the DOE program is to inform the entire industry of the value, characteristics, and availability of utility battery systems so that knowledgeable decisions can be made regarding …

Sandia National Laboratories, New Mexico, conducts the Utility Battery Storage Systems Program, which is sponsored by the US Department of Energy`s Office of Energy Management. In this capacity, Sandia is responsible for the engineering analyses, contract development, and testing of rechargeable batteries and systems for utility-energy-storage applications. This report details the technical achievements realized during fiscal year 1993.

Argonne National Laboratory`s Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor (ALMR) that uses a metallic (U-Pu-Zr alloy) fuel material in a steel cladding. The intimate contact between the fuel and fission products with the cladding at reactor operating temperatures (<600{degrees}C) can lead to chemical interaction and potential degradation of the cladding. One possible way to minimize the diffusion of the fuel and fission products into the steel cladding during irradiation is to place a physical barrier between the fuel and cladding. The barrier material chosen would have to be less susceptible to interaction at both the fuel and cladding interfaces. While there may be several methods by which a barrier can be placed between the fuel and cladding in the IFR fuel element, the two that have been pursued most recently are casting the fuel into a mold of the barrier material and then placing the casting and the mold into the steel cladding, and producing a lined, or ``duplex,`` cladding and placing the cast fuel ingot into the duplex cladding. The first method had some significant advantages, but it did not prove to be an effective barrier for fuel/cladding interaction. The second concept is the subject of …

A verification and validation (V&V) process has been performed for the System Analysis Programs for Hands-on Integrated Reliability Evaluation (SAPHIRE). SAPHIRE is a set of four computer programs that the Nuclear Regulatory Commission (NRC) developed to perform probabilistic risk assessments (PRAs). These programs allow an analyst to create, quantify, and evaluate the risk associated with a facility or process being analyzed. The programs included in this set are Integrated Reliability and Risk Analysis System (IRRAS), System Analysis and Risk Assessment (SARA), Models and Results Database (MAR-D), and Fault Tree/Event Tree/Piping and Instrumentation Diagram (FEP) graphical editor. The V&V steps included a V&V plan to describe the process and criteria by which the V&V would be performed; a software requirements documentation review to determine the correctness, completeness, and traceability of the requirements; a user survey to determine the usefulness of the user documentation, identification and testing of vital and non-vital features, and documentation of the test results.

A model is developed to estimate the volatile organic compound (VOC) concentration in the headspace of the innermost layer of confinement in a lab-scale vented waste drum containing simulated waste sludge. The VOC transport model estimates the concentration using the measured VOC concentration beneath the drum lid and model parameters defined or estimated from process knowledge of drum contents and waste drum configuration. Model parameters include the VOC diffusion characteristic across the filter vent, VOC diffusivity in air, size of opening in the drum liner lid, the type and number of layers of polymer bags surrounding the waste, VOC permeability across the polymer, and the permeable surface area of the polymer bags. Comparison of model and experimental results indicates that the model can accurately estimate VOC concentration in the headspace of the innermost layer of confinement. The model may be useful in estimating the VOC concentration in actual waste drums.

The Volatile Organic Compounds In Arid Soils Integrated Demonstration (VOC-Arid ID) focuses on technologies to clean up volatile organic compounds and associated contaminants in soil and groundwater at arid sites. The initial host site is the 200 West Area at DOE`s Hanford site in southeastern Washington state. The primary VOC contaminant is carbon tetrachloride, in association with heavy metals and radionuclides. An estimated 580--920 metric tons of carbon tetrachloride were disposed of between 1955 and 1973, resulting in extensive soil and groundwater contamination. The VOC-Arid ID schedule has been divided into three phases of implementation. The phased approach provides for: rapid transfer of technologies to the Environmental Restoration (EM-40) programs once demonstrated; logical progression in the complexity of demonstrations based on improved understanding of the VOC problem; and leveraging of the host site EM-40 activities to reduce the overall cost of the demonstrations. During FY92 and FY93, the primary technology demonstrations within the ID were leveraged with an ongoing expedited response action at the Hanford 200 West Area, which is directed at vapor extraction of VOCs from the vadose (unsaturated) zone. Demonstration efforts are underway in the areas of subsurface characterization including: drilling and access improvements, off-gas and borehole monitoring …

The Volatile Organic Compounds (VOCs) in Non-Arid Soils Integrated Demonstration (ID) was initiated in 1989. Objectives for the ID were to test the integrated demonstration concept, demonstrate and evaluate innovative technologies/systems for the remediation of VOC contamination in soils and groundwater, and to transfer technologies and systems to internal and external customers for use in fullscale remediation programs. The demonstration brought together technologies from DOE laboratories, other government agencies, and industry for demonstration at a single test bed. The Savannah River Site was chosen as the location for this ID as the result of having soil and groundwater contaminated with VOCS. The primary contaminants, trichlorethylene and tetrachloroethylene, originated from an underground process sewer line servicing a metal fabrication facility at the M-Area. Some of the major technical accomplishments for the ID include the successful demonstration of the following: In situ air stripping coupled with horizontal wells to remediate sites through air injection and vacuum extraction; Crosshole geophysical tomography for mapping moisture content and lithologic properties of the contaminated media; In situ radio frequency and ohmic heating to increase mobility, of the contaminants, thereby speeding recovery and the remedial process; High-energy corona destruction of VOCs in the off-gas of vapor recovery …

To maintain capabilities in nuclear weapons technologies, the Department of Energy (DOE) has to maintain a plutonium processing facility that meets all the current and emerging standards of environmental regulations. A strategic goal to transform the Plutonium Processing Facility at Los Alamos into an environmentally benign operation is identified. A variety of technologies and systems necessary to meet this goal are identified. Two initiatives now in early stages of implementation are described in some detail. A highly motivated and trained work force and a systems approach to waste minimization and pollution prevention are necessary to maintain technical capabilities, to comply with regulations, and to meet the strategic goal.

The purpose of this paper is to provide an update on what we`ve accomplished and have planned in our plating operation at Lawrence Livermore National Laboratory (LLNL) in the area of waste minimization. Our efforts have included issues other than waste minimization and, therefore, fall under the wider umbrella entitled pollution prevention or environmentally conscious electroplating. Approximately one year has passed since our last report on pollution prevention and since this topic remains a high-effort activity much more has been accomplished. Our efforts to date fall under the first two generation categories of waste reduction. Good housekeeping practices, inventory control, and minor changes in operating practices (first generation) resulted in an impressive amount of waste reduction. In the second generation of waste reduction, current technology, separation technologies, and material substitutions were used to reduce emission and wastes. The third generation of improvements requires significant technological advances in process synthesis and engineering. We are presently starting some projects in this third generation phase and these will be discussed at the end of this paper.

This task supports the tank-vapor project, mainly by providing organic analytical support and by analyzing Tank 241-C-103 (Tank C-103) vapor-space samples, collected via SUMMA{trademark} canisters, by gas chromatography (GC) and GC/mass spectrometry (MS). In the absence of receiving tank-vapor samples, we have focused our efforts toward validating the normal paraffin hydrocarbon (NPH) sampling and analysis methods and preparing the SUMMA{trademark} laboratory. All required milestones were met, including a report on the update of phase I sampling and analysis on August 15, 1993. This update described the work involved in preparing to analyze phase I samples (Appendix A). This report describes the analytical support provided by Pacific Northwest Laboratory (PNL){sup (a)} to the Hanford Tank Safety Vapor Program.

The advent of micro- or binary optics technology has made possible the fabrication of a variety of new optical devices. Optical fabrication is no longer limited by surfaces that can be made by grinding and polishing, or even diamond turning. In fact, optics with no symmetry, no smooth surfaces, and that perform multiple functions can be readily fabricated. While these optics have a large number of applications, they are extremely useful for systems that require arrays of small optics or aperture multiplexing, since these are fabricated using computer controlled photo-lithography and etching processes. We have applied binary optics technology to construct various wavefront sensing using four mask processes to create 16 level optics. They are binary in the sense that they use discrete phase levels, not in the sense of using only two levels (they might more properly be called digital optics). We have found that 16 levels is adequate for most systems, giving greater than 99% of efficiency.

This paper describes the evolution of the Westinghouse Hanford Company (WHC) Unclassified Computer Security (UCS) Program over the past seven years. The intent has been to satisfy the requirements included in the DOE Order 1360.2B (DOE 1992) for Unclassified Computer Security in the most efficient and cost-effective manner.

One- and two-dimensional, time resolved x-ray radiographic imaging at high photon energy (5-7 keV) is used to study shock propagation, material motion and compression, and the effects of shear flow in solid density samples which are driven by x-ray ablation with the Nova laser. By backlighting the samples with x-rays and observing the increase in sample areal density due to shock compression, the authors directly measure the trajectory of strong shocks ({approx}40 Mbar) in flight, in solid density plastic samples. Doping a section of the samples with high-Z material (Br) provides radiographic contrast, allowing the measurement of the shock induced particle motion. Instability growth due to shear flow at an interface is investigated by imbedding a metal wire in a cylindrical plastic sample and launching a shock in the axial direction. Time resolved radiographic measurements are made with either a slit-imager coupled to an x-ray streak camera or a pinhole camera coupled to a gated microchannel plate detector, providing {approx} 10-{mu}m spatial and {approx} 100-ps temporal resolution.

This document contains results of a variety of studies on the SRS (Savannah River Site) resorcinol-formaldehyde ion exchange resin with a simulant of the high-level liquid waste found in the Hanford 101-AW tank. Small column studies indicate that flow rates of 2.5 column volumes or less per hour give well-defined breakthrough curves. More rapid flow rates of three to twenty column volumes per hour produce leakage of cesium ion before 50% breakthrough has been reached after processing about 100 column volumes of feed. Upflow elution of the small columns with three concentrations of nitric acid show that about 85% of the cesium, sodium, and potassium ions on the resin can be removed simultaneously with 0.5 M HNO{sub 3}. Radiolysis studies at doses as high as 1E+09 rads have shown that the resin is more stable to radiation in water than in the 101-AW simulant. Radiation doses up to 1 E+08 rads did not alter the performance of the resin for cesium removal. Exposure to radiation or storage did not affect the thermal stability of the resin. Hydrogen gas is produced from radiolysis of resin in 101-AW simulant. Other gases that were measured were N{sub 2}, O{sub 2}, CO{sub 2}, N{sub …

The Z + {gamma} cross-section x branching ratio in the electron channel has been measured using the inclusive Z data sample from the CDF 1988--1989 collider run, for which the total integrated luminosity was 4.05 {plus_minus} 0.28 pb{sup {minus}1}. Two Z{gamma} candidates are observed from central photon events with {Delta}R/{sub {gamma}} > 0.7 and E{sub t}{sup {gamma}} > 5.0 GeV. From these events the {sigma} * BR(Z + {gamma}) is measured and compared with SM predictions: {sigma} * BR(Z + {gamma}){sub e} = 6.8{sub {minus}5.7}{sup +5.7}(stat + syst)pb {sigma} * BR(Z + {gamma})SM = 4.7{sub {minus}4.7}{sup +0.7}(stat + syst)pb. From this ZZ{sub {gamma}} cross section measurement limits on the Z{sub {gamma}{gamma}} and couplings for three different choices of compositeness scale {Lambda}{sub Z} are obtained. The experimental sensitivity to the h{sub 30}{sup Z,{gamma}}/h{sub 10}{sup Z,{gamma}} couplings is in the range of {Lambda}{sub Z} {approximately} 450--500 GeV and for the h{sub 40}{sup Z{gamma}}/h{sub 20}{sup Z,{gamma}} couplings {Lambda}{sub Z} {approximately} 300 GeV.

The authors have studied the kinetics of oxylose/xylulose isomerization in significant detail over a variety of zeolites and obtained the pseudo-first order reaction rate constants. The authors have found that HY zeolite is still the best material and zeolites are more selective than homogeneous acid catalysts where decomposition of the sugar compounds is much faster. They have completed, as described in the Year 2 Work Plan, the study of cellobiose hydrolysis with an ion exchange resin. The kinetics of the solid-catalyzed reaction is qualitatively similar to that for catalysis by homogeneous acids. The planned program of NMR studies has revealed the dynamics of sugar molecules within the zeolite cavities. Two chemisorbed and a physisorbed state have been identified in HY zeolite. A new state, accounting for as much as a half of the sugar, has been found in ZSM-5 zeolite.