This document is the final laboratory report for B Plant Tk-21-1. A Resource Conservation and Recovery Act (RCRA) sample was taken from Tk-21 -1 September 26, 1996. This sample was received at 222-S Analytical Laboratory on September 27, 1996. Analyses were performed in accordance with the accompanying Request for Sample Analysis (RSA) and Letter of Instruction B PLANT RCRA SAMPLES TO 222S LABORATORY, LETTER OF INSTRUCTION (LOI) 2B-96-LOI-012-01 (LOI) (Westra, 1996). LOI was issued subsequent to RSA and replaces Letter of Instruction 2C-96-LOI-004-01 referenced in RSA.

The laser architecture of the NIF beamlines requires small-area beam dumps to safely absorb back reflections from the output and leakage through the PEPC switch. The problems presented by these beam dumps are that fluences they must absorb are very large, beyond the damage threshold of any material, and ablation of beam dump materials potentially contaminates adjacent optical components. Full scale tests have demonstrated that a stainless steel beam dump will survive fluence levels and energies as high as 820 j/CM{sup 2} and 2.5 kJ, respectively. Small scale tests with tungsten, tantalum, and stainless steel have demonstrated erosion rates less than about 0.5 {mu}m/shot, with stainless steel having the smallest rate. They also suggest that increased angles of incidence ({ge}60{degree}) will greatly reduce the material ablated directly back along the beam path.

Glass has become a preferred waste form worldwide for radioactive wastes: however, there are limitations. Halogen-containing wastes can not be converted to glass because halogens form poor-quality waste glasses. Furthermore, halides in glass melters often form second phases that create operating problems. A new waste vitrification process, the Glass Material Oxidation and dissolution System (GMODS), removes these limitations by converting halogen-containing wastes into borosilicate glass and a secondary, clean, sodium-halide stream.

The workshop was devoted to discussion of the status and future directions of work on plasma-based neutron sources. The workshop presentations demonstrated significant progress in development of the concepts of these sources and in broadening the required data base. Two main groups of neutron source designs were presented at the workshop: tokamak-based and mirror-based. Designs of the tokamak- based devices use the extensive data base generated during decades of tokamak research. Their plasma physics performance can be predicted with a high degree of confidence. On the other hand, they are relatively large and expensive, and best suited for Volumetric Neutron Sources (VNSes) or other large scale test facilities. They also have the advantage of being on the direct path to a power- producing reactor as presently conceived, although alternatives to the tokamak are presently receiving serious consideration for a reactor. The data base for the mirror-based group of plasma sources is less developed, but they are generally more flexible and, with appropriate selection of parameters, have the potential to be developed as compact Accelerated Test Facilities (ATFs) as well as full-scale VNSes. Also discussed at the workshop were some newly proposed but potentially promising concepts, like those based on the …

A preliminary error budget for the third harmonic converter for the National Ignition Facility (NIF) laser driver has been developed using a root-sum-square-accumulation of error sources. Such a budget sets an upper bound on the allowable magnitude of the various effects that reduce conversion efficiency. Development efforts on crystal mounting technology and crystal quality studies are discussed.

This is the eighth in a series of quarterly reports describing the activities performed under Contract No. DE-AC21-94MC31160. Analyses of Hot Gas Stream Cleanup (HGCU) ashes and descriptions of filter performance address aspects of filter operation that are apparently linked to the characteristics of the collected ash or the performance of the ceramic barrier filter elements. Task 1 is designed to generate a data base of the key characteristics of ashes collected from operating advanced particle filters (APFS) and to relate these ash properties to the operation and performance of these filters. Task 2 concerns testing and failure analysis of ceramic filter elements. Under Task I during the past quarter, additional analyses were performed on ashes from the Ahlstrom 10 MWt Pressurized Fluidized Circulating Fluid Bed (PCFB) facility located at Karhula, Finland. Work continued on the HGCU data base being constructed in Microsoft Access. A variety of information has been entered into the data base, including numerical values, short or long text entries, and photographs. Detailed design of a bench top device for high temperature measurement of ash permeability has also begun. In addition to these activities, a paper was prepared and a poster was presented summarizing recent work performed …

This Safety Analysis Report for Packaging (SARP) Upgrade Plan reflects a SARP upgrade schedule based on the most current program needs. A performance agreement has been assigned, beginning in FY 1997, to update, revise, and/or cancel 20 percent of the existing onsite SARPS, so that 100 percent are reviewed and within current standards by the completion of the Project Hanford Management Contract (five-year period).

This paper presents the comparison of the COMOPS benchmark performance in MPI and shared memory on three different shared memory platforms: the DEC AlphaServer 8400/300, the SGI Power Challenge, and the HP-Convex Exemplar SPP1600. The paper also qualitatively analyzes the obtained performance data based on an understanding of the corresponding architecture and the MPI implementations. Some conclusions are made for the inter-processor communication performance on these three shared memory platforms.

Experiments and calculations indicate that the threshold pressure in spatial filters for distortion of a transmitted pulse scales approximately as I{sup O.2} and (F{number_sign}){sup 2} over the intensity range from 10{sup 14} to 2xlO{sup 15} W/CM{sup 2} . We also demonstrated an interferometric diagnostic that will be used to measure the scaling relationships governing pinhole closure in spatial filters.

Several years ago, it was proposed that a dense nonneutral plasma could be produced in a Penning trap. Nonneutral plasmas have excellent confinement. Thus, such a dense plasma might produce simultaneously high density and good confinement (as needed for fusion). Recently, this theoretical conjecture has been demonstrated in a small (3 mm radius) electron experiment (PFX). Densities up to 35 times the Brillouin density (limiting number density in a static trap) have been inferred from the observed strong (100:1) spherical focussing. Electrons are injected at low energy from a single pole of the sphere. A surprising observation is the self-organization of the system into a spherical state, which occurs precisely when the trap parameters are adjusted to produce a spherical well. This organization is observed by a bootstrapping which produces a hysteresis. Additional observations which confirm the dense spherical focus are energy-scattered electrons and deflections of an electron probe beam by the space charge of the central focus.

Toxicological consequences were calculated for a postulated maximum caustic soda (NaOH) solution spray leak during addition to a waste tank to adjust tank pH. Although onsite risk guidelines were exceeded for the unmitigated release, site boundary consequences were below the level of concern. Means of mitigating the release so as to greatly reduce the onsite consequences were recommended. Consequences for the mitigated release were estimated and both onsite and offsite consequences were found to negligible.

This Criticality Safety Evaluation allows a mix of up to five pin containers plus two assemblies in the same Core Component Container.

The development of coal-fired magnetohydrodynamic (MHD) power can be viewed as consisting of two parts; the topping cycle and the bottoming cycle. The topping cycle consists of the coal combustor, MHD generator and associated components. The bottoming cycle consists of the heat recovery, steam generation, seed recovery/regeneration, emissions control (gas and particulate), ash handling and deposition, and materials evaluation. The report concentrates on the bottoming cycle, for which much of the technology was developed at the University of Tennessee Space Institute (UTSI). Because of the complexity of the required technology, a number of issues required investigation. Of specific concern regarding the bottoming cycle, was the design of the steam cycle components and emissions control. First, the high combustion temperatures and the use of large quantities of potassium in the MHD combustor results in a difference in the composition of the gases entering the bottoming cycle compared to conventional systems. Secondly, a major goal of the UTSI effort was to use a variety of coals in the MHD system, especially the large reserves of high-sulfur coals available in the United States.

Testing was carried out in the Engineering Testing Laboratory, 305 Building- 300 Area, during June, July and August of 1996. This testing was to develop and proof test a new sampler insert which would prevent purge gas from flowing through a push-mode core drilling bit - and subsequently prevent rotation of the Rotary Mode Core Sampling System (RMCSS) when the push bit was used. The testing involved push-mode sampling with both a new push mode insert and a rotary insert in a push mode bit into two simulants. A total of sixty final test runs showed that the inserts are sucessful in preventing purge flow and hence in preventing rotation with a push-mode bit installed.

This document describes testing to be carried out at the Pittsburgh Research Center to determine the effects of an explosion occuring within a length of drill pipe. The results will help quantify hazards involved with core sampling in a Flammable Watch List Tank on the Hanford Nuclear Site.

This document provides the toxicological dose caculations related to the toxic chemical releases from spill accidents at T Plant Facility.

During this quarterly period, the author has made progress in a number of areas. He has continued to evaluate potential candidates for high load/high speed antiwear action using the approach of generating tribopolymers capable of withstanding high temperatures. Results are promising for ceramics as well as steel. The construction of a new instrument for high temperature studies of both liquid and vapor phase lubrication is almost complete. This will permit studies up to 350 C bulk temperature and considerably higher surface temperatures in controlled vapor-phase and liquid-phase studies. Selected monomers and monomer combinations found to be effective in hexadecane as a carrier fluid have also been tested in other fluids, including synthetic ester lubricant carriers. Additional studies using FTIRM for surface analysis of wear tracks have been made and are continuing. Further industrial contacts have been made to arrange for field testing of selected compounds as antiwear additives. The applications include the lubrication of 2-stroke and 4-stroke engines, machining and cutting, and fuel injector wear, particularly in gas (e.g., natural gas) engines.

This plan delineates the requirements for control of software developed and supported by the Tank Waste Remediation System (TWRS) Technical Integration organization. The information contained in this plan shall assist employees involved with software modification and configuration control.

This Sampling and Analysis Plan contains requirements for characterizing the 340 vault tank 1. The objective of the sampling and characterization is to determine if the tank is homogeneous when agitated and which sampling method provides the most representative sample. A secondary objective is to collect and characterize solid samples.

The activity of TRIGA core components was estimated.

The purpose of this calculation note is to provide the basis for evaporator dump consequence for the Tank Farm Safety Analysis Report (FSAR). Evaporator Dump scenario is developed and details and description of the analysis methods are provided.

The purpose of this calculation note is to provide the basis for In-Tank Fuel fire/Deflageration consequence for the Tank Farm Safety Analysis Report (FSAR). Tank Fuel Fire/Deflageration scenario is developed and details and description of the analysis methods are provided.

Numerous computer programs are available to help accelerator physicists and engineers model and design accelerator cavities and other microwave components. This article discusses the problems these programs solve and the principles upon which these programs are based. Some examples of how these programs are used in the design of accelerator cavities are also given.

This program was aimed at creating a quantitative physical description, at the micrometer and nanometer levels, of the physical interactions of the alpha particles from radon and its daughters with cells at risk in the bronchial epithelium. The authors calculated alpha-particle energy spectra incident upon the cells and also energy deposition spectra in micrometer- and nanometer-sized sites as a function of cell depth, site size, airway diameter, activities of {sup 218}Po and {sup 214}Po, and other parameters. These data are now being applied, using biophysical models of radiation effects, to predict cell killing, mutations, and cell transformation. The model predictions are then compared to experimental biophysical, biochemical, and biological information. These studies contribute to a detailed understanding of the mechanisms of the biological effectiveness of the radiations emitted by radon and its progeny.