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Office of Scientific & Technical Information Technical Reports
8,261
Congressional Research Service Reports
146
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130
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105
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64
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25
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3
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Texas Motor Vehicle Traffic Accident Summaries
40
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37
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33
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33
United States Geological Survey Reports
30
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20
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20
Winter Fuels Report
19
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16
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Results:
1 - 24 of
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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.
Date:
September 1995
Creator:
Xu, Y. & Uberbacher, E. C.
System:
The UNT Digital Library
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.
Date:
December 1, 1995
Creator:
Lane, J. E.; Painter, C. J.; Radford, K. C. & LeCostaouec, J. F.
System:
The UNT Digital Library
A 6.3 T Bend Magnet for the Advanced Light Source
The Advanced Light Source (ALS) is a 1.5 to 1.9 GeV high-brightness electron storage ring operating at Lawrence Berkeley Laboratory (LBL) that provides synchrotron radiation for a large variety of users. It Is proposed to replace three of the thirty six 1.5T, one meter long bend magnets with very sbort high-field superconductlng (SC) dipoles. These magnets would provide bend-magnet synchrotron radiation to six bcamlines with a critical energy of at least 6 keV that is much better suited for protein crystallography and other small-sample x-ray diffraction and adsorption studies, than is currently available at the ALS. The magnet design is described, including coil, yoke, magnetic field analysis, and cyrostat. A prototype magnet is under construction at LBL.
Date:
June 7, 1995
Creator:
Taylor, C. E. & Caspi, S.
System:
The UNT Digital Library
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.
Date:
June 1, 1995
Creator:
Yang, M. J.
System:
The UNT Digital Library
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 …
Date:
March 1995
Creator:
unknown
System:
The UNT Digital Library
12 Batch coalescing studies
The purpose of the study was to identify and correct the problems in the 12 batch coalescing. The final goal is to be able to coalesce 12 booster batches of 11 bunches each into 12 bunches spaced at 21 buckets apart with an average intensity of 200 E9 ppb.
Date:
January 1, 1995
Creator:
Kourbanis, I. & Wildman, D.
System:
The UNT Digital Library
26.7 Mhz Cavity Mechanical Tuner Requirements
The Report is a description of Project about 26.7 Mhz Cavity Mechanical Tuner Requirements.
Date:
February 1, 1995
Creator:
Rose, J.
System:
The UNT Digital Library
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.
Date:
June 19, 1995
Creator:
Baldwin, J.H.
System:
The UNT Digital Library
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.
Date:
May 18, 1995
Creator:
Conner, J.M.
System:
The UNT Digital Library
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.
Date:
June 22, 1995
Creator:
Sasaki, L.M.
System:
The UNT Digital Library
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.
Date:
May 1, 1995
Creator:
Conner, J.M.
System:
The UNT Digital Library
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.
Date:
April 21, 1995
Creator:
Schreiber, R. D.
System:
The UNT Digital Library
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 …
Date:
May 11, 1995
Creator:
Sasaki, L.M.
System:
The UNT Digital Library
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.
Date:
May 3, 1995
Creator:
Sasaki, L.M.
System:
The UNT Digital Library
45 Day safety screen results for Tank 241-C-108 -- Augers 94-012, 94-014 and 94-015
Three auger samples from Tank C-108 (on the Ferrocyanide Watch List) were received by the 222-S laboratories. These samples underwent safety screening analysis (DSC, TGA, and Alpha Total) in accordance with reference below. No results exceeded the notification criteria. Due to the calculated depth of sludge at riser 7, two augers were used to sample the sludge. The first (94-AUG-012) was a ten inch auger, the second (94-AUG-014) was a 20 inch auger. One 20 inch auger (94-AUG-015) was used to sample the tank C-108 contents at riser 4. Results are compiled in this report.
Date:
January 31, 1995
Creator:
Rice, A. D.
System:
The UNT Digital Library
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.
Date:
June 15, 1995
Creator:
Schreiber, R. D.
System:
The UNT Digital Library
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.
Date:
August 15, 1995
Creator:
Conner, J.M.
System:
The UNT Digital Library
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.
Date:
May 4, 1995
Creator:
Sathyanarayana, P.
System:
The UNT Digital Library
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.
Date:
May 5, 1995
Creator:
Jo, J.
System:
The UNT Digital Library
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.
Date:
May 5, 1995
Creator:
Schreiber, R. D.
System:
The UNT Digital Library
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.
Date:
May 17, 1995
Creator:
Bell, Kevin E.
System:
The UNT Digital Library
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.
Date:
March 8, 1995
Creator:
Miller, George L.
System:
The UNT Digital Library
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.
Date:
November 1, 1995
Creator:
Schreiber, R. D.
System:
The UNT Digital Library
50 Watt Recooler ASME Boiler Code Calculations
This Report contains ASME Boiler and Pressure Vessel code Calculations for the RHIC 50 watt recooler.
Date:
May 1995
Creator:
DeLalio, J.
System:
The UNT Digital Library