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  Partner: UNT Libraries Government Documents Department
 Decade: 1990-1999
 Year: 1995
1.2 MW klystron for Asymmetric Storage Ring B Factory
A cw klystron operating at 476 MHz has been developed jointly by SLAC and Varian Associates. The unique set of characteristics of this tube were strongly guided by requirements of the fast feedback necessary to prevent oscillations of the storage ring beams caused by the detuned accelerating cavity. This requires a combination of bandwidth and short group delay within the klystron. The RF feedback stabilization scheme also requires amplitude modulation making it necessary to operate the klystron about 10% below saturation. Performance specifications and initial operating results are presented. digital.library.unt.edu/ark:/67531/metadc666784/
A 1.5 GeV compact light source with superconducting bending magnets
This paper describes the design of a compact electron synchrotron light source for producing X-rays for medical imaging, protein crystallography, nano-machining and other uses up to 35 keV. The source will provide synchrotron light from six 6.9 tesla superconducting 60{degree} bending magnet stations. In addition the ring, contains conventional quadrupoles and sextupoles. The light source has a circumference of 26 meters, which permits it to be located in a variety of industrial and medical facilities. digital.library.unt.edu/ark:/67531/metadc793152/
2-D image segmentation using minimum spanning trees
This paper presents a new algorithm for partitioning a gray-level image into connected homogeneous regions. The novelty of this algorithm lies in the fact that by constructing a minimum spanning tree representation of a gray-level image, it reduces a region partitioning problem to a minimum spanning tree partitioning problem, and hence reduces the computational complexity of the region partitioning problem. The tree-partitioning algorithm, in essence, partitions a minimum spanning tree into subtrees, representing different homogeneous regions, by minimizing the sum of variations of gray levels over all subtrees under the constraints that each subtree should have at least a specified number of nodes, and two adjacent subtrees should have significantly different average gray-levels. Two (faster) heuristic implementations are also given for large-scale region partitioning problems. Test results have shown that the segmentation results are satisfactory and insensitive to noise. digital.library.unt.edu/ark:/67531/metadc628011/
N = 2 string amplitudes
In physics, solvable models have played very important roles. Understanding a simple model in detail teaches us a lot about more complicated models in generic situations. Five years ago, C. Vafa and I found that the closed N = 2 string theory, that is a string theory with the N = 2 local supersymmetry on the worldsheet, is classically equivalent to the self-dual Einstein gravity in four spacetime dimensions. Thus this string theory is solvable at the classical level. More recently, we have examined the N = 2 string partition function for spacial compactifications, and computed it to all order in the string perturbation expansion. The fact that such computation is possible at all suggests that the N = 2 string theory is solvable even quantum mechanically. digital.library.unt.edu/ark:/67531/metadc622294/
2 {times} 2 TeV {mu}{sup +}{mu}{sup {minus}} collider: Lattice and accelerator-detector interface study
The design for a high-luminosity {mu}{sup +}{mu}{sup {minus}} superconducting storage ring is presented based on first-pass calculations. Special attention is paid to two Iowa interaction regions (IR) whose optics are literally interlaced with the collider detectors. Various sources of backgrounds in IR are explored via realistic Monte Carlo simulations. An improved design of the collider lattice in the neighborhood of the interaction points (EP) is determined by the need to reduce significantly background levels in the detectors. digital.library.unt.edu/ark:/67531/metadc710146/
3-D field computation: The near-triumph of commerical codes
In recent years, more and more of those who design and analyze magnets and other devices are using commercial codes rather than developing their own. This paper considers the commercial codes and the features available with them. Other recent trends with 3-D field computation include parallel computation and visualization methods such as virtual reality systems. digital.library.unt.edu/ark:/67531/metadc794259/
A 3-D numerical study of pinhole diffraction to predict the accuracy of EUV point diffraction interferometry
A 3-D electromagnetic field simulation is used to model the propagation of extreme ultraviolet (EUV), 13-nm, light through sub-1500 {Angstrom} dia pinholes in a highly absorptive medium. Deviations of the diffracted wavefront phase from an ideal sphere are studied within 0.1 numerical aperture, to predict the accuracy of EUV point diffraction interferometersused in at-wavelength testing of nearly diffraction-limited EUV optical systems. Aberration magnitudes are studied for various 3-D pinhole models, including cylindrical and conical pinhole bores. digital.library.unt.edu/ark:/67531/metadc687713/
3-D woven, mullite matrix, composite filter
Westinghouse, with Techniweave as a major subcontractor, is conducting a three-phase program aimed at providing advanced candle filters for a 1996 pilot scale demonstration in one of the two hot gas filter systems at Southern Company Service`s Wilsonville PSD Facility. The Base Program (Phases I and II) objective is to develop and demonstrate the suitability of the Westinghouse/Techniweave next generation composite candle filter for use in Pressurized Fluidized Bed Combustion (PFBC) and/or Integrated Gasification Combined Cycle (IGCC) power generation systems. The Optional Task (Phase M, Task 5) objective is to fabricate, inspect and ship to Wilsonville Hot gas particulate filters are key components for the successful commercializaion of advanced coal-based power-generation systems such as Pressurized Fluidized-bed Combustion (PFBC), including second-generation PFBC, and Integrated Gasification Combined Cycles (IGCC). Current generation monolithic ceramic filters are subject to catastrophic failure because they have very low resistance to crack propagation. To overcome this problem, a damage-tolerant ceramic filter element is needed. digital.library.unt.edu/ark:/67531/metadc623027/
4 MW upgrade to DIII-D FWCD system: System commissioning and initial operation
The initial installation of the 4 MW fast wave current drive (FWCD) upgrade started in 1992 with the purchase of two ABB/Thomcast AG rf power amplifiers. These amplifiers cover the frequency range 30 MHz to 120 MHz. A maximum output power of over 2 MW between 30 MHz and 80 MHz and 1 MW at 120 MHz were the specification requirements. The system as installed is comprised of the two mentioned rf amplifiers, coaxial transmission and matching components, rf phase and amplitude monitoring, and a SUN SparcStation 10 control system. Due to various reasons almost every major component in the system required redesign and engineering in order to meet the system requirements. The failures, probable cause and the final redesigns will be discussed as well as some thoughts on how better to specify system requirements for future systems. digital.library.unt.edu/ark:/67531/metadc683710/
5. international workshop on the identification of transcribed sequences
This workshop was held November 5--8, 1995 in Les Embiez, France. The purpose of this conference was to provide a multidisciplinary forum for exchange of state-of-the-art information on mapping the human genome. Attention is focused on the following topics: transcriptional maps; functional analysis; techniques; model organisms; and tissue specific libraries and genes. Abstracts are included of the papers that were presented. digital.library.unt.edu/ark:/67531/metadc679753/
The 8-GeV transfer line injection into main ring
Included in this report are a brief review of the design lattice of the 8-GeV beam transfer line and the Main Ring, the recent measurements on the 8-GeV line lattice function as well as that of the Main Ring at 8-GeV. The injection matching is a very important part of the MR operation. Mismatches such as energy, timing, or position are easily corrected because they cause oscillations which are visible on the Turn-By-Turn (TBT) TV monitor display. Mis-matches due to beta and dispersion functions are detected only by using the Flying Wire or by doing measurements during beam study. A new method which makes use of the available data from TBT hardware was used to obtain the beam phase space ellipse. Data taken from Main Ring at injection gives the beta function needed for transfer matching from 8-GeV line. The result of this measurement is also presented here. digital.library.unt.edu/ark:/67531/metadc793221/
9. international mouse genome conference
This conference was held November 12--16, 1995 in Ann Arbor, Michigan. The purpose of this conference was to provide a multidisciplinary forum for exchange of state-of-the-art information on genetic mapping in mice. This report contains abstracts of presentations, focusing on the following areas: mutation identification; comparative mapping; informatics and complex traits; mutagenesis; gene identification and new technology; and genetic and physical mapping. digital.library.unt.edu/ark:/67531/metadc687281/
10 CFR 830.120 Criterion 10, Independent Assessment: We`re here to help you!
Each organization performing activities in the DOE Weapons Complex is required to have an pendent assessment function. This is consistent from DOE Order 5700.6C, Quality Assurance to 10 CFR 830-120, sometimes referred to as the Price-Anderson rule. DOE Order 5700.6C, Criterion 10 Independent Assessment requires, `` Planned and periodic independent assessments shall be conducted to measure item quality and process effectiveness and to promote improvement. The organization performing independent assessments shall have sufficient authority and freedom from the line organization to carry out its responsibilities. Persons conducting independent assessments shall be technically qualified and knowledgeable in the areas assessed.`` 10 CFR 830.120, (c) Quality assurance criteria -- (3) Assessment -- (ii) Independent Assessment requires,``Independent assessments shall be planned and conducted to measure item and service quality, to measure the adequacy of work performance, and to promote improvement. The group performing independent assessments shall have sufficient authority and freedom from the line to carry out its responsibilities. Persons conducting independent assessments shall be technically qualified and knowledgeable in the areas assessed.`` digital.library.unt.edu/ark:/67531/metadc793206/
A 10-GeV, 5-MW proton source for a muon-muon collider
The performance parameters of a proton source which produces the required flux of muons for a 2-TeV on 2-TeV muon collider are: a beam energy of 10 GeV, a repetition rate of 30 Hz, two bunches per pulse with 5 x 10{sup 13} protons per bunch, and an rms bunch length of 3 nsec (1). Aside from the bunch length requirement, these parameters are identical to those of a 5-MW proton source for a spallation neutron source based on a 10-GeV rapid cycling synchrotron (RCS) (2). The 10-GeV synchrotron uses a 2-GeV accelerator system as its injector, and the 2-GeV RCS is an extension of a feasibility study for a I-MW spallation source described elsewhere (3--9). A study for the 5-MW spallation source was performed for ANL site-specific geometrical requirements. Details are presented for a site-independent proton source suitable for the muon collider utilizing the results of the 5-MW spallation source study. digital.library.unt.edu/ark:/67531/metadc669513/
A 10-GeV, 5-MW proton source for a pulsed spallation source
A feasibility study for a pulsed spallation source based on a 5-MW, 10-GeV rapid proton synchrotron (RCS) is in progress. The integrated concept and performance parameters of the facility are discussed. The 10-GeV synchrotron uses as its injector the 2-GeV accelerator system of a 1-MW source described elsewhere. The 1-MW source accelerator system consists of a 400-MeV H{sup {minus}} linac with 2.5 MeV energy spread in the 75% chopped (25% removed) beam and a 30-Hz RCS that accelerates the 400-MeV beam to 2 GeV. The time averaged current of the accelerator system is 0.5 mA, equivalent to 1.04 {times} 10{sup 14} protons per pulse. The 10-GeV RCS accepts the 2 GeV beam and accelerates it to 10 GeV. Beam transfer from the 2-GeV synchrotron to the 10-GeV machine u highly efficient bunch-to-bucket injection, so that the transfer can be made without beam loss. The synchrotron lattice uses FODO cells of 90{degrees} phase advance. Dispersion-free straight sections are obtained using a missing magnet scheme. The synchrotron magnets are powered by dual-frequency resonant circuits. The magnets are excited at a 20-Hz rate and de-excited at 60-Hz. resulting in an effective 30-Hz rate. A key feature of the design of this accelerator system is that beam losses are minimized from injection to extraction, reducing activation to levels consistent with hands-on maintenance. Details of the study are presented. digital.library.unt.edu/ark:/67531/metadc667953/
10-MW demonstration of the gas suspension absorption process at TVA`s Center for Emissions Research. Final report
The Tennessee Valley Authority (TVA) in cooperation with AirPol Inc., and the U.S. Department of Energy (DOE), has recently completed a successful 17-month test program with the AirPol Gas Suspension Absorption (GSA) flue gas desulfurization (FGD) process at TVA`s Center for Emissions Research (CER). This project was selected by DOE for funding in the third round of the Clean Coal Technology Program. This 10-MW demonstration of the GSA FGD system at the CER was the first application of this technology in the U.S. The GSA test program, which was cofunded two-thirds by TVA and one-third by DOE/AirPol, was completed over a 17-month period from November 1, 1992 to March 31, 1993. This test program demonstrated that the GSA FGD technology could achieve high SO{sub 2} removal efficiencies (90+ percent) for a 2.7 percent sulfur (as-fired) coal application, while maintaining particulate emissions below the New Source Performance Standards (NSPS), i.e., 0.03 lb/MBtu, in a four-field electrostatic precipitator. The reliability and operability of this system was also demonstrated in a 28-day, 24 hour/day, continuous run during which the GSA unit simultaneously achieved high SO{sub 2} removal efficiencies (90+ percent) and maintained particulate emissions below the NSPS. Also, the air toxics removal capabilities of the GSA system were determined in a series of tests. A 1-MW pulsejet baghouse (PJBH) pilot plant was also tested in conjunction with this GSA test program. This PJBH testing was initially cofunded by TVA and the Electric Power Research Institute, who were later joined by AirPol and DOE in sponsoring this PJBH testing. A 14-day PJBH demonstration run was also completed to confirm the reliability of this system. digital.library.unt.edu/ark:/67531/metadc621760/
15. international conference on plant growth substances: Program -- Abstracts
Since the 14th Conference in Amsterdam in 1991, progress in plant hormone research and developmental plant biology has been truly astonishing. The five ``classical`` plant hormones, auxin, gibberellin, cytokinin, ethylene, and abscisic acid, have been joined by a number of new signal molecules, e.g., systemin, jasmonic acid, salicylic acid, whose biosynthesis and functions are being understood in ever greater detail. Molecular genetics has opened new vistas in an understanding of transduction pathways that regulate developmental processes in response to hormonal and environmental signals. The program of the 15th Conference includes accounts of this progress and brings together scientists whose work focuses on physiological, biochemical, and chemical aspects of plant growth regulation. This volume contains the abstracts of papers presented at this conference. digital.library.unt.edu/ark:/67531/metadc678130/
A 30-T pulsed magnet suitable for neutron scattering experiments
We describe a conceptual design for a 30-T vertical-field split-pair magnet suitable for neutron scattering studies. While the magnet is primarily intended for diffraction and spectroscopic studies using a pulsed neutron source, it might also have application for relaxational studies,at steady-state sources. The magnet will have a 5-cm bore for sample environment equipment, a 1-cm gap for the neutrons to illuminate the sample and through which to observe the scattering. It will run with a repetition frequency of 2 Hz, and a pulse length of 3 ms. We discuss scientific and engineering considerations that led to this specification and describe the designs of both magnet and power supply. digital.library.unt.edu/ark:/67531/metadc793922/
45-day safety screen results and final report for tank 241-C-202, auger samples 95-Aug-026 and 95-Aug-027
Two auger samples from tank 241-C-202 (C-202) were received at the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. Two samples were submitted for energetics determination by DSC. Within the triplicate analyses of each sample, one of the results for energetics exceeded the notification limit. The sample and duplicate analyses for both augers exceeded the notification limit for TGA. As required by the Tank Characterization Plan, the appropriate notifications were made within 24 hours of official confirmation that the limits were violated. digital.library.unt.edu/ark:/67531/metadc792323/
45-day safety screen results and final report for Tank 241-C-203, Auger samples 95 AUG-020 and 95-AUG-021
This document serves as the 45-day report deliverable for the tank C-203 auger samples collected on April 5, 1995 (samples 95-AUG-20 and 95-AUG-021). As no secondary analyses were required and no other analyses have been requested, this document also serves as the final report for C-203 auger sampling. Each sample was received, extruded, and analyzed by the 222-S Laboratories in accordance with the Tank Characterization Plan (TCP) referenced below. Included in this report are the primary safety screening results (DSC, TGA, and alpha) and density results. The worklists and raw data are included in this report. Photographs of the auger samples were taken during extrusion and, although not included in this report, are available. digital.library.unt.edu/ark:/67531/metadc711652/
45-Day safety screen results and final report for Tank 241-SX-113, Auger samples 94-AUG-028 and 95-AUG-029
This document serves as the 45-day report deliverable for tank 241-SX-113 auger samples collected on May 9 and 10, 1995. The samples were extruded, and analyzed by the 222-S Laboratory. Laboratory procedures completed include: differential scanning calorimetry; thermogravimetric analysis; and total alpha analysis. This report incudes the primary safety screening results obtained from the analyses. As the final report, the following are also included: chains of custody; the extrusion logbook; sample preparation data; and total alpha analysis raw data. digital.library.unt.edu/ark:/67531/metadc793946/
45-Day safety screen results for Tank 241-B-112, auger samples 95-AUG-014 and 95-AUG-015
Two auger samples from Tank 241-B-112 (B-112) were received in the 222-S Laboratories and underwent safety screening analyses, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. All results for all analyses (DSC, TGA, and total alpha) were within the safety screening notification limits specified in the Tank Characterization Plan (TCP). No notification nor secondary analyses were required. Tank B-112 is not part of any of the four Watch Lists. digital.library.unt.edu/ark:/67531/metadc695886/
45-Day safety screen results for Tank 241-BY-103, auger samples 95-AUG-012 and 95-AUG-013
Two auger samples from tank 241-BY-103 (BY-103) were received by the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. Analytical results for the TGA analyses for both samples were less than the safety screening notification limit. Since notification is made if the sample is analyzed at less than 17% water, notification was made on April 20, 1995. Although the sample results were below this limit, no secondary analyses were required or performed. Included in this report are the primary safety screening results obtained from the analyses and copies of all DSC and TGA raw data scans as requested per the TCP. Photographs of the auger samples were taken during extrusion and, although not included in this report, are available. Tank BY-103 is on the ferrocyanide Watch List. digital.library.unt.edu/ark:/67531/metadc704363/
45-Day safety screen results for Tank 241-C-101, auger sample 95-AUG-019
One auger sample from Tank 241-C-101 was received by the 222-S Laboratory and underwent safety screening analyses--differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha analysis--in accordance with the tank characterization plan. Analytical results for the TGA on the crust sample (the uppermost portion of the auger sample) (sample number S95T000823) were less than the safety screening notification limit of 17 weight percent water. Verbal and written notifications were made on May 3, 1995. No exotherms were observed in the DSC analyses and the total alpha results were well below the safety screening notification limit. This report includes the primary safety screening results obtained from the analyses and copies of all DSC and TGA raw data scans as requested per the TCP. Although not included in this report, a photograph of the extruded sample was taken and is available. This report also includes bulk density measurements required by Characterization Plant Engineering. Additional analyses (pH, total organic carbon, and total inorganic carbon) are being performed on the drainable liquid at the request of Characterization Process Control; these analyses will be reported at a later date in a final report for this auger sample. Tank C-101 is not part of any of the four Watch Lists. digital.library.unt.edu/ark:/67531/metadc740162/
45-Day safety screen results for tank 241-C-105, push mode, cores 72 and 76
This document is a report of the analytical results for samples collected between March 14 and March 22, 1995 from the radioactive wastes in Tank 241-C-105 at the Hanford Reservation. Core samples were collected from the solid wastes in the tank and underwent safety screening analyses including differential scanning calorimetry, thermogravimetric analysis, and total alpha analysis. digital.library.unt.edu/ark:/67531/metadc707732/
45-Day safety screen results for Tank 241-C-201, Auger samples 95-AUG-025 and 95-AUG-026
Two auger samples from tank 241-C-201 (C-201) were received by the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. Analytical results for the DSC analyses of both samples exceeded the notification limit of 481 J/g (dry weight basis). As well, the TGA analyses for both samples were less than the safety screening notification limit (notification is made if the sample is analyzed at less than 17 percent water). Notification of both of these occurrences was made on May,15, 1995, and secondary analysis of total organic carbon (TOC) was initiated. These TOC analysis results are also included in this report. digital.library.unt.edu/ark:/67531/metadc794196/
45-day safety screen results for tank 241-C-204, auger samples 95-Aug-022 and 95-Aug-023
Two auger samples from tank 241-C-204 (C-204) were received at the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. The three samples submitted to energetics determination by DSC exceeded the notification limit. As required by the Tank Characterization Plan, the appropriate notifications were made within 24 hours of official confirmation that the limit was exceeded. Secondary analyses have been initiated. Results from secondary analyses will be included in a revision to this report. digital.library.unt.edu/ark:/67531/metadc794763/
45-Day safety screen results for Tank 241-U-201, push mode, cores 70, 73 and 74
Three core samples, each having two segments, from Tank 241-U-201 (U-201) were received by the 222-S Laboratories. Safety screening analysis, such as differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity were conducted on Core 70, Segment 1 and 2 and on Core 73, Segment 1 and 2. Core 74, Segment 1 and 2 were taken to test rotary bit in push mode sampling. No analysis was requested on Core 74, Segment 1 and 2. Analytical results for the TGA analyses for Core 70, Segment 1, Upper half solid sample was less than the safety screening notification limit of 17 percent water. Notification was made on April 27, 1995. No exotherm was associated with this sample. Analytical results are presented in Tables 1 to 4, with the applicable notification limits shaded. digital.library.unt.edu/ark:/67531/metadc736754/
45-Day safety screen results for tank 241-U-202, push mode, cores 75 and 78
This document is a report of the analytical results for samples collected from the radioactive wastes in Tank 241-U-202 at the Hanford Reservation. Core samples were collected from the solid wastes in the tank and underwent safety screening analyses including differential scanning calorimetry, thermogravimetric analysis, and total alpha analysis. Results indicate that no safety screening notification limits were exceeded. digital.library.unt.edu/ark:/67531/metadc710267/
45-Day safety screen results for tank 241-U-203, push mode, cores 79 and 80
Two one-segment core samples from tank 241-U-203 (U-203) were received by the 222-S Laboratories and underwent safety screening analysis, consisting of differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), and total alpha activity. In addition to the safety screening requirements, inductively coupled plasma (ICP) spectrographic analysis for lithium was performed to determine the extent of hydrostatic head fluid contamination during the sampling event. No notification limits were exceeded for these analyses. digital.library.unt.edu/ark:/67531/metadc703523/
45-day safety screen results for tank 241-U-204, push mode, cores 81 and 82
This is the 45-Day report for the fiscal year 1995 tank 241-U-204 (U-204) push-mode characterization effort. Included are a summary of analytical results and copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans. Core samples 81 and 82 from tank U-204, obtained by the push-mode core sampling method, were received by the 222-S Laboratories. Each core consisted of only one segment. Both core samples and the field blank were extruded, subsampled, and analyzed in accordance with Reference 1. Drainable liquids and the field blank were analyzed at the segment level for energetics by DSC, percent water by TGA, and total organic carbon (TOC) by furnace oxidation. In addition, the presence or absence of any separable, presumably organic, layer in drainable liquid samples was noted and none was observed. The solids were analyzed directly at the half segment level for energetics by DSC, percent water by TGA, and TOC by persulfate oxidation. Total alpha activity was determined on fusion digestions of the sludge subsamples. No immediate notifications were necessary on samples from cores 81 or 82. digital.library.unt.edu/ark:/67531/metadc734350/
45-Day safety screening report for grab samples from Tank 241-AP-107
Three samples; 107-AP-1C, 107-AP-2c and 107-AP-3C; were received at 222-S Laboratory for analysis of DSC, TGA and visual appearance. Four additional samples; 107-AP-1D, 107-AP-2D, 107-AP-3D and 107-AP-6; were received for visual appearance only. No results exceeded the safety screen notification criteria. This report compiles the analytical results. Tank 241-AP-107 is a double-shell tank which is not on any of the four Watch Lists. digital.library.unt.edu/ark:/67531/metadc684916/
45-day safety screening results and final report for Tank 241-BX-110, auger samples 95-AUG-045 and 95-AUG-046
This document summarizes the final results for the safety screening of tank 241-BX-110. digital.library.unt.edu/ark:/67531/metadc682258/
60-day safety screen results and final report for tank 241-C-111, auger samples 95-Aug-002, 95-Aug-003, 95-Aug-016, and 95-Aug-017
This report presents the details of the auger sampling events for underground waste tank C-111. The samples were shipped to the 222-S laboratories were they underwent safety screening analysis and primary ferricyanide analysis. The samples were analyzed for alpha total, total organic carbon, cyanide, Ni, moisture, and temperature differentials. The results of this analysis are presented in this document. digital.library.unt.edu/ark:/67531/metadc793079/
60-day safety screen results for tank 241-BY-106, rotary mode, cores 64 and 65
Core samples 64 and 65 from tank BY-106, obtained by rotary-mode core sampling, were received by the 222-S Laboratories. Differential scanning calorimetry and thermogravimetric analysis were carried out. digital.library.unt.edu/ark:/67531/metadc695519/
90-Day safety screen results and final report for tank 241-B-104 push-mode, cores 88 and 89. Revision 1
This document reports the final screen results for tank 241-B-104 Push Mode, Cores 88 and 89 digital.library.unt.edu/ark:/67531/metadc681059/
A 100 ps gated x-ray spectrometer
Material opacities are of interest in many fields. We have developed a Bragg reflection spectrometer that is gated for imaging samples in a laser heated environment for opacity measurement. A micro-channel plate is coated with a photocathode material and a fast pulse is launched across it. Electrons are converted to photons in a phosphor and recorded on film. Optical gate pulse widths of 100 ps are achieved. Some optical pulse width and sensitivity enhancements are noted at launch and termination. Events of interest are 200 ps long. The framing window is approximately 250 ps in length. Timing jitter is a problem. The instrument timing networks have been examined, and the source of jitter is still unknown. Timing to 50 ps resolution is desired. Close in proximity to the laser-driven event leads to complications in shielding from hard x-rays, hot electrons and shock-driven damage. High Z materials provide shielding from hard x-rays. Magnets screen out hot electrons produced by laser-matter interactions Filters provide energy fiducials. PCD`s provide high resolution timing measurements. Data is recorded on film in a specially designed film pack. The instrument is designed to be used in the NOVA Laser Facility at Lawrence Livermore National Laboratory. digital.library.unt.edu/ark:/67531/metadc625561/
101-SY Dome pressure issues surrounding mitigation pump decontamination during removal
This document addresses issues related to use of the spraywands and ring used to decontaminate the mitigation pump installed in 101-SY. It has been determined that use of the wands will influence tank dome pressures as a function of ventilation system configuration, spray drop size, rinse water temperature, and rate at which spraywand flows are established. digital.library.unt.edu/ark:/67531/metadc685082/
105-DR Large Sodium Fire Facility decontamination, sampling, and analysis plan
This is the decontamination, sampling, and analysis plan for the closure activities at the 105-DR Large Sodium Fire Facility at Hanford Reservation. This document supports the 105-DR Large Sodium Fire Facility Closure Plan, DOE-RL-90-25. The 105-DR LSFF, which operated from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility in the 100-D Area of the Hanford Site. The LSFF was established to investigate fire fighting and safety associated with alkali metal fires in the liquid metal fast breeder reactor facilities. The decontamination, sampling, and analysis plan identifies the decontamination procedures, sampling locations, any special handling requirements, quality control samples, required chemical analysis, and data validation needed to meet the requirements of the 105-DR Large Sodium Fire Facility Closure Plan in compliance with the Resource Conservation and Recovery Act. digital.library.unt.edu/ark:/67531/metadc793733/
105 K east ion exchange and cartridge filter restart computer software configuration management plan
Configuration Management Plan for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc687530/
105 K east ion exchange and cartridge filter restart computer software design description
Computer Software Design Description for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc678232/
105 K East ion exchange and cartridge filter restart computer software documentation
Computer Software Documentation for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc686352/
105 K east ion exchange and cartridge filter restart computer software requirements specification
Computer Software Requirements Specification for the Cartridge Filter Restart Project. digital.library.unt.edu/ark:/67531/metadc685564/
105 K east ion exchange and cartridge filter restart computer software user documentation
Computer software user documentation for the cartridge filter restart project. digital.library.unt.edu/ark:/67531/metadc674835/
105 K East isolation barrier acceptance analysis report
The objective of this document is to report and interpret the findings of the isolation barrier acceptance tests performed in 105KE/100K. The tests were performed in accordance with the test plan (McCracken 1995c) and acceptance test procedure (McCracken 1995a). The test report (McCracken 1995b) contains the test data. This document compares the test data (McCracken 1995b) against the criteria (McCracken 1995a, c). A discussion of the leak rate analytical characterization (Irwin 1995) describes how the flow characteristics and the flow rate will be determined using the test data from the test report (McCracken 1995b). The barriers must adequately control the leakage from the main basin to the discharge chute to less than the 1,500 gph (5,680 lph) Safety Analysis Report (SAR 1994) limit. digital.library.unt.edu/ark:/67531/metadc791918/
105-K East sandfilter backwash line sample analysis report: first campaign
This document summarizes the sandfilter backwash for 105-K East. digital.library.unt.edu/ark:/67531/metadc687323/
105 K-West isolation barrier leak recovery plan
Leak testing is being performed in 105 KW to verify the performance of the isolation barriers which have been recently installed. When an 11 inch differential head is established between the main basin and the discharge chute, a leak-rate of approximately 30 - 35 gpm is observed. The leak-rate would be achieved by a 1.65`` - 2`` diameter hole (or equivalent). Analyses suggest that the flow is turbulent/laminar transitional (dominantly turbulent), which would be indicative of a single point leak, typical of a pipe or large opening. However, local vortex rotation is observed in the entry to the West transfer chute while no observable motion was seen in the East transfer chute: this may be an indication of seal leakage in the East isolation barrier. The potential for leakage had been considered during the design and field work planning stages. Review of potential leak detection technologies had been made; at the planning stage it was determined that location specific leak detection could be established relatively quickly, applying existing K Basins technology (dye or ultrasonics). The decision was made not to pre-stage leak detection since the equipment development is highly dependent on the nature and location of the leak, and the characteristics of the leak rate provides data which guides leak characterization technology. The expense could be deferred and potentially avoided without risk to critical path activity. Consistent with the above, a systematic recovery plan has been developed utilizing phased activities to provide for management discipline combined with timely diagnosis and correction. Because this activity is not critical path at this time, activities will be coordinated with other plant activity to optimize overall plant work. Particular care will be exercised in assuring that information gained from this recovery can be utilized in the more critical work in 105 KE. digital.library.unt.edu/ark:/67531/metadc678918/
105-KE Basin isolation barrier leak rate test analytical development. Revision 1
This document provides an analytical development in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used to determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under postulated accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage: viscous laminar and turbulent flow. An analytical development is presented for each flow regime. The basic geometry and nomenclature of the postulated leak paths are denoted. digital.library.unt.edu/ark:/67531/metadc793772/
105-KE Isolation Barrier Leak Rate Acceptance Test Report
This Acceptance Test Report (ATR) contains the completed and signed Acceptance Procedure (ATP) for the 105-KE Isolations Barrier Leak Rate Test. The Test Engineer`s log, the completed sections of the ATP in the Appendix for Repeat Testing (Appendix K), the approved WHC J-7s (Appendix H), the data logger files (Appendices T and U), and the post test calibration checks (Appendix V) are included. digital.library.unt.edu/ark:/67531/metadc793988/
105-KW Sandfilter Backwash Pit sludge volume calculation
The volume of sludge contained in the 100-KW Sandfilter Backwash Pit (SFBWP) was calculated from depth measurements of the sludge, pit dimension measurements and analysis of video tape recordings taken by an underwater camera. The term sludge as used in this report is any combination of sand, sediment, or corrosion products visible in the SFBWP area. This work was performed to determine baseline volume for use in determination of quantities of uranium and plutonium deposited in the pit from sandfilter backwashes. The SFBWP has three areas where sludge is deposited: (1) the main pit floor, (2) the transfer channel floor, and (3) the surfaces and structures in the SFBWP. The depths of sludge and the uniformity of deposition varies significantly between these three areas. As a result, each of the areas was evaluated separately. The total volume of sludge determined was 3.75 M{sup 3} (132.2 ft{sup 3}). digital.library.unt.edu/ark:/67531/metadc667682/
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