A report is given on progress made during the second year of a three year contract studying the feasibility of nuclear pumping the atomic iodine laser. Experimental results are presented showing efficiencies of 25--38% at converting neutron-induced nuclear reaction energy in the excimer XeBr into UV photons which can be used to pump the laser. Parametric studies were done utilizing the {sup 10}B(n,{alpha}){sup 7}Li reaction, with three bromine donor chemicals, over a range of pressures and mix ratios, to optimize the fluorescence efficiency.

Laser-plasma instability experiments for laser fusion have followed three developments. These are advances in the technology and design of experiments, advances in diagnostics, and evolution of the design of high-gain targets. This paper traces the history of these three topics and discusses their present state. Today one is substantially able to produce controlled plasma conditions and to diagnose specific instabilities within such plasmas. Experiments today address issues that will matter for future laser facilities. Such facilities will irradiate targets with {approx}1 MJ of visible or UV light pulses that are tens of nanoseconds in duration, very likely with a high degree of spatial and temporal incoherence. 58 refs., 4 figs.

The meeting began with presentations by the facilitator, Mr. Spiegel, and Dr. Lewis, the program director from DOE. The facilitator introduced those on the podium. He then described the general structure of the meeting and its purpose: to hear the issues and concerns of those present regarding the proposed Hawaiian Geothermal Project. He described his role in ensuring the impartiality and fairness of the meeting. Dr. Lewis further defined the scope of the project, introduced members of the EIS team, briefly described the EIS process, and answered several process questions, noting that cable feasibility would be examined and that Native Hawaiian concerns would be addressed. Ms. Borgstrom stated that the ISIS Implementation Plan will be continuously refined and that impacts of reasonably foreseeable future activities would be examined. During the meeting, more than 90% of the commenters requested that the EIS identify and assess the relative merits and impacts of energy alternatives to the proposed action. Nearly 80% requested that the EIS investigate conservation and renewable forms of energy, such as wind, solar, and biomass. They suggested that integrated resource planning should be used, noting that the State is initiating such a process. More than 30% of the commenters asked …

The following discussion summarizes the survey approach and results of the Department of Public Service's survey of retail fuel oil and propane prices during the 1990--91 heating season. The semi-monthly phone surveys were conducted in cooperation with the US Department of Energy's State Fuel Oil and Propane Program, which coordinated surveys of heating fuel prices by 25 eastern and midwest states. This federal/state program serves as a method for fast collection, analysis, and dissemination of information on current residential prices. No other information source meets needs for timely retail price information over the course of the heating season. For the 1990--91 heating season, the Minnesota Department of Public Service (MN/DPS) expanded the scope of its survey effort to include regional price data. Surveys were conducted with 160 retailers, including 59 respondents from the DOE samples, to provide a reasonable sample size for each region. Fuel oil retailers were also asked for updates on their secondary inventory levels.

This paper specifies the usage of structural bolts in terms of their design, selection and application, in accordance with the American Institute of Steel Construction (AISC) Ninth Edition. Manual of Steel Construction.''

We compare angular distributions calculated by folding nucleon- nucleon scattering kernels, using the theory of Feshbach, Kerman and Koonin, and the systematics of Kalbach, with a wide range of data. The data range from (n,xn) at 14 MeV incident energy to (p,xn) at 160 MeV incident energy. The FKK theory works well with one adjustable parameter, the depth of the nucleon-nucleon interaction potential. The systematics work well when normalized to the hybrid model single differential cross section prediction. The nucleon- nucleon scattering approach seems inadequate. 9 refs., 10 figs.

The stresses developed in the solenoid and VLPC transfer lines have been investigated with the PipePlus v4.5 software package from Algor. 4 cases were considered for each transfer line and the following results were obtained. Pipe deflections have also been kept to a minimum by carefully considering the location of spider guides. Their placement should be as close as possible to the locations shown in Figures 4-7. With regard to chosen pipe sizes, the 2.5-inch OD Cu radiation shield in the solenoid transfer line should be replaced with a 3.5-inch OD tube. The vacuum jackets should also be replaced with 5-inch or larger pipe. These changes should safely accommodate the maximum displacements caused by thermal loading. This engineering note investigates the ability of the solenoid and VLPC cryogenic transfer lines to accommodate thermal stresses. The solenoid and VLPC transfer lines are similar in their construction in that they consist of an outer vacuum jacket, liquid nitrogen supply and return lines, a copper thermal radiation shield, and liquid helium supply and return lines. See Figure 1 for details on their specific construction. Line drawings for the solenoid and VLPC transfer lines are shown in Figures 2 and 3, respectively. The transfer …

A report is given on progress made during the second year of a three year contract studying the feasibility of nuclear pumping the atomic iodine laser. Experimental results are presented showing efficiencies of 25--38% at converting neutron-induced nuclear reaction energy in the excimer XeBr into UV photons which can be used to pump the laser. Parametric studies were done utilizing the {sup 10}B(n,{alpha}){sup 7}Li reaction, with three bromine donor chemicals, over a range of pressures and mix ratios, to optimize the fluorescence efficiency.

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.

This procedure will document the satisfactory operation of the 101-SY tank Camera Purge System (CPS) and 101-SY in tank Color Camera Video Imaging System (CCVIS). Included in the CPRS is the nitrogen purging system safety interlock which shuts down all the color video imaging system electronics within the 101-SY tank vapor space during loss of nitrogen purge pressure.

This report presents ``reference`` computations that can be used by safety analysts in the evaluations of the consequences of postulated atmospheric releases of radionuclides from the Rocky Flats Environmental Technology Site. These computations deal specifically with doses and health risks to the public. The radionuclides considered are Class W Plutonium, all classes of Enriched Uranium, and all classes of Depleted Uranium. (The other class of plutonium, Y, was treated in an earlier report.) In each case, one gram of the respirable material is assumed to be released at ground leveL both with and without fire. The resulting doses and health risks can be scaled to whatever amount of release is appropriate for a postulated accident being investigated. The report begins with a summary of the organ-specific stochastic risk factors appropriate for alpha radiation, which poses the main health risk of plutonium and uranium. This is followed by a summary of the atmospheric dispersion factors for unfavorable and typical weather conditions for the calculation of consequences to both the Maximum Offsite Individual and the general population within 80 km (50 miles) of the site.

Research efforts during this quarter concentrated on two issues. The first issue is related to the chemistry of oxygen conducting materials that could be used as dense membranes in the membrane reactors. Mixed oxides of La, Sr, Fe, Ce, Yb etc., were synthesized, characterized and studied for their catalytic activity towards the oxidative coupling of methane. Heavy metal oxides of lanthanum, strontium and iron, which form good oxygen conductors, showed very poor methane coupling activity. Perovskites of the Strontium-Cerium-Yitribium series showed moderate activity for methane coupling. These could be potential candidates for dense membrane synthesis, since they also have moderate oxygen conduction properties. The second area of research focus was the development of a radial flow catalytic membrane reactor in which methane coupling was carried out over a catalyst that was deposited inside the pores of a ceramic porous membrane. Catalytic results from the high temperature oxidative coupling of methane in these radial flow membrane reactors are presented in this report. By exploring the reactor performance in membranes of pore diameters of 2.0{mu}m, 0.2{mu}m, and 0.02{mu}m, the effect of the diffusional regime on the methane. coupling activity was demonstrated. The smallest pore diameter membranes exhibited lowest hydrocarbon selectivities.

This document provides the structural analysis of the Sodium Loop framework in a drop condition. The drop is similar to the US Department of Transportation non-bulk, performance-oriented packaging (Packaging Group I) drop test. The drop height evaluated for the Sodium Loop framework is 5.9 ft.

The following discussion summarizes the survey approach and results of the Department of Public Service`s survey of retail fuel oil and propane prices during the 1990--91 heating season. The semi-monthly phone surveys were conducted in cooperation with the US Department of Energy`s State Fuel Oil and Propane Program, which coordinated surveys of heating fuel prices by 25 eastern and midwest states. This federal/state program serves as a method for fast collection, analysis, and dissemination of information on current residential prices. No other information source meets needs for timely retail price information over the course of the heating season. For the 1990--91 heating season, the Minnesota Department of Public Service (MN/DPS) expanded the scope of its survey effort to include regional price data. Surveys were conducted with 160 retailers, including 59 respondents from the DOE samples, to provide a reasonable sample size for each region. Fuel oil retailers were also asked for updates on their secondary inventory levels.

The Integrated DWPF Melter System (IDMS) is designed and constructed to provide an engineering-scale representation of the DWPF melter and its associated feed preparation and off-gas systems. The facility is the first pilot-scale melter system capable of processing mercury, and flowsheet levels of halides and noble metals. In order to characterize the processing of noble metals (Pd, Rh, Ru, and Ag) on a large scale, the IDMS will be operated batchstyle for at least nine feed preparation cycles. The first two of these operations are complete. The major observation to date occurred during the second run when significant amounts of hydrogen were evolved during the feed preparation cycle. The runs were conducted between June 7, 1990 and March 8, 1991. This time period included nearly six months of ``fix-up`` time when forced air purges were installed on the SRAT MFT and other feed preparation vessels to allow continued noble metals experimentation.

In fusion laser designs, the laser pulse has a complicated temporal shape which undergoes significant change as it passes through the laser. Our damage data, however, was taken with pulses whose temporal shapes were (more or less) Gaussian. We want to determine the damage propensity of a material exposed to a pulse of arbitrary temporal shape , given data taken with Gaussian pulses of different pulse widths. To do so, we must adopt a physical model of damage. This model will contain some number of parameters that depend on material properties, geometry, and so forth. We determine the parameters of the model appropriate to each material by fitting the model to the Gaussian data for that material. The resulting normalized model is then applied, using the appropriate pulse shape, to find the damage level for a specific material subjected to a specific pulse. The model we shall assume is related to diffusion, although (as we shall see) the experimental results do not fit any simple diffusion model. Initially, we will discuss simple diffusion models. We then examine some experimental data, and then develop a modified diffusive model from that data. That modified model is then used to predict damage levels …

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Fluor Daniel Hanford. Inc., is the prime contractor for the US, Department of Energy, Richland Operations Office at the Hanford Site, which is located near Richland, Washington, in the southeastern portion of the state. Six major subcontractors for Fluor Daniel Hanford, Inc., provide operations and maintenance in waste management, environmental restoration, science and energy for 24 major facilities, programs or utilities on the Site that covers 1,465 square kilometers (560 square miles). Hanford was established in secrecy during the Second World War to produce plutonium for America's nuclear weapons. Peak production was reached in the 1960s when nine production reactors were in operation at the Site. All weapons material production was halted in the late 1980s and the Site is now engaged in the world's largest environmental cleanup project. The mission at Hanford is to manage waste products; researching, developing, applying, and commercializing technologies; waste management; cleanup and environmental restoration. Engineering, scientific and research programs are conducted on environmental restoration, tank waste remediation, waste management, nuclear energy, and energy research.

The Tank Waste Remediation System (TWRS) pretreatment facility project W-236B, known as the Initial Pretreatment Module (IPM), requires samples of supernatants and sludges from 200 Area tank farms for planned hot testing work in support of IPM design. The IPM project has proposed the development of several new sampler systems. These systems include a 0.5-l supernatant sampler, 3-l and 25-l supernatant and sludge samplers, and a 4,000-l sampler system. The 0.5-l sampler will support IPM sampling needs in the 1 to 3 l range starting in late fiscal year 1995. This sampler is intended to be used in conjunction with the existing 100 ml bottle-on-a-string. The 3-l and 25-l systems will be based on the Savannah River Site`s sampler system and will support IPM sampling needs in the 3 to 100 liter range. Most of the hot testing required for design of the IPM must be accomplished in the next 3 years. This work plan defines the tasks associated with the development of a 0.5-l sampler system. This system will be referred to as the Half-Liter Supernatant Sampler System (HLSSS). Specifically, this work plan will define the scope of work, identify organizational responsibilities, identify major technical requirements, describe configuration control …

Advanced, coal-fueled, power generation systems utilizing pressurized fluidized bed combustion (PFBC) and integrated gasification combined cycle (IGCC) technologies are currently being developed for high-efficiency, low emissions, and low-cost power generation. In spite of the advantages of these promising technologies, the severe operating environment often leads to material degradation and loss of performance in the barrier filters used for particle entrapment. To address this problem, LoTEC Inc., and Oak Ridge National Laboratory are jointly designing and developing a monolithic cross-flow ceramic hot-gas filter. The filter concept involves a truly monolithic cross-flow design that is resistant to delamination, can be easily fabricated, and offers flexibility of geometry and material make-up. During Phase I of the program, a thermo-mechanical analysis was performed to determine how a cross-flow filter would respond both thermally and mechanically to a series of thermal and mechanical loads. The cross-flow filter mold was designed accordingly, and the materials selection was narrowed down to Ca{sub 0.5}Sr{sub 0.5}Zr{sub 4}P{sub 6}O{sub 24} (CS-50) and 2Al{sub 2}O{sub 3}-3SiO{sub 2} (mullite). A fabrication process was developed using gelcasting technology and monolithic cross-flow filters were fabricated. The program focuses on obtaining optimum filter permeability and testing the corrosion resistance of the candidate materials.

Highly alkaline radioactive waste solutions originating from production of plutonium for military purposes are stored in underground tanks at the U.S. Department of Energy Hanford Site. The purification of alkaline solutions from neptunium and plutonium is important in the treatment and disposal of these wastes. This report describes scoping tests with sodium hydroxide solutions, where precipitation techniques were investigated to perform the separation. Hydroxides of iron (III), manganese (II), cobalt (II, III), and chromium (III); manganese (IV) oxide, and sodium uranate were investigated as carriers. The report describes the optimum conditions that were identified to precipitate these carriers homogeneously throughout the solution by reductive, hydrolytic, or catalytic decomposition of alkali-soluble precursor compounds by a technique called the Method of Appearing Reagents. The coprecipitation of pentavalent and hexavalent neptunium and plutonium was investigated for the candidate agents under optimum conditions and is described in this report along with the following results. Plutonium coprecipitated well with all tested materials except manganese (IV) oxide. Neptunium only coprecipitated well with uranate. The report presents a hypothesis to explain these behaviors. Further tests with more complex solution matrices must be performed.