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Subcritical Crack Growth in Ceramic Composites at High Temperature Measured Using Digital Image Correlation

Description: An in situ experimental technique is described that allows high resolution, high sensitivity determination of displacements and full-field strains during high temperature mechanical testing. The technique is used to investigate elevated temperature crack growth in SiC/Nicalon sub f composites. At 1150 degrees C, the reinforcing fibers have a higher creep susceptibility than the matrix. Fiber creep leads to relaxation of crack bridging tractions, resulting in subcritical crack growth. Differenti… more
Date: January 11, 1996
Creator: Mumm, D. R.; Morris, W. L.; Dadkhah, M. S. & Cox, B. N.
Partner: UNT Libraries Government Documents Department
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Organic and TRU screening for 200 West Area SST interim stabilization activities

Description: This SD documents the preliminary work performed during the effort to better understand the magnitude and nature of transuranic (TRU) and/or complexed wastes contained in the 200 West Area single shell tank (SSTs). This preliminary work identified which of the SST interstitial liquids in question had adequate characterizations and performed a limited compatibility assessment based upon those characterizations. This allowed a determination of the TRU activity in the liquid and the waste type whi… more
Date: January 1, 1996
Creator: Estey, S.D.
Partner: UNT Libraries Government Documents Department
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Functional design criteria for the self-installing liquid observation well

Description: This document presents the functional Design Criteria for installing liquid observation wells (LOWs) into single-shell tanks containing ferrocyanide and organic wastes. The LOWs will be designed to accommodate the deployment of gamma, neutron, and electromagnetic induction probes and to interface with the existing tank structure and environment.
Date: January 1, 1996
Creator: Parra, S.A.
Partner: UNT Libraries Government Documents Department
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Fissile material disposition program: Screening of alternate immobilization candidates for disposition of surplus fissile materials

Description: With the end of the Cold War, the world faces for the first time the need to dismantle vast numbers of ``excess`` nuclear weapons and dispose of the fissile materials they contain, together with fissile residues in the weapons production complex left over from the production of these weapons. If recently agreed US and Russian reductions are fully implemented, tens of thousands of nuclear weapons, containing a hundred tons or more of plutonium and hundreds of tonnes* of highly enriched uranium (… more
Date: January 8, 1996
Creator: Gray, L.W.
Partner: UNT Libraries Government Documents Department
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Neutralized current acid waste consolidation management plan

Description: The scope of this evaluation is to recommend a management plan for the high-heat tank waste, including neutralized current acid waste (NCAW) in AY and AZ Tank Farms, and tank C-106 waste. The movement of solids, liquids and salt cake in the designated tank farms is included. Decision analysis techniques were used to determine a recommended alternative. The recommended course of action was replacement of a 75-hp mixer pump in tank AY-102 and in-tank concentration of tank AZ-102 supernate. The al… more
Date: January 1996
Creator: Powell, W. J.; Brown, R. G.; Galbraith, J.; Jensen, C.; Place, D. E.; Reddick, G. W. et al.
Partner: UNT Libraries Government Documents Department
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CSER 95-014: Criticality storage category for K Basin spent cartridge filters in ECOROK casks at central waste complex

Description: This CSER justifies storing K Basin spent cartridge filters in ECOROK 25-11 casks with liners under the limits in an existing criticality prevention specification, CPS-SW-149-00002, Rev./Mod. B-1, because the worst case fissionable material inventory is less then 1/2 the CPS limit and the cask is larger than allowed containers, the cask and liner have adequate iron content to meet the CPS requirements, and the cask concrete walls are thick enough to isolate the fissionable contents of each cask… more
Date: January 3, 1996
Creator: Miller, E. M.
Partner: UNT Libraries Government Documents Department
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Description of double-shell tank selection criteria for inspection

Description: Technical criteria for selecting double-shelf tanks`s (DST`s) for inspection are presented. Inspection of DST`s is planned to non-destructively determine the general condition of their inner wall and bottom knuckle. Inspection of representative tanks will provide a basis for evaluating the integrity of all the DST`s and provide a basis for estimating remaining life. The selection criteria recommended are tank age based on date-of-first fluid entry, waste temperature, corrosion inhibitor levels,… more
Date: January 1, 1996
Creator: Schwenk, E. B. & Scott, K. V.
Partner: UNT Libraries Government Documents Department
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Increased oil production and reserves utilizing secondary/tertiary recovery techniques on small reservoirs in the Paradox basin, Utah. Final technical progress report, October 1--December 31, 1995

Description: The primary objective of this project is to enhance domestic petroleum production by demonstration and technology transfer of an advanced oil recovery technology in the Paradox basin, southeastern Utah. If this project can demonstrate technical and economic feasibility, the technique can be applied to approximately 100 additional small fields in the Paradox basin alone, and result in increased recovery of 150 to 200 million barrels of oil. This project is designed to characterize five shallow-s… more
Date: January 15, 1996
Creator: Allison, M. L.
Partner: UNT Libraries Government Documents Department
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Tank farm potential ignition sources

Description: This document identifies equipment, instrumentation, and sensors that are located in-tank as well as ex-tank in areas that may have communication paths with the tank vapor space. For each item, and attempt is made to identify the potential for ignition of flammable vapors using a graded approach. The scope includes all 177 underground storage tanks.
Date: January 1, 1996
Creator: Scaief, C. C., III
Partner: UNT Libraries Government Documents Department
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Assessment of the potential for ferrocyanide propagating reaction accidents

Description: This report contains safety criteria for the storage of ferrocyanide bearing waste sludges in Hanford underground waste storage tanks. In addition, the tank wastes are categorized with this criteria into SAFE, CONDITIONALLY SAFE, and UNSAFE categories based on available historical records and sample information. Fourteen (14) tanks are classified as CONDITIONALLY SAFE, while four (4) C-Farm tanks are categorized as SAFE. This report therefore provides a technical basis to resolve the ferrocyani… more
Date: January 1, 1996
Creator: Meacham, J. E.; Cash, R. J. & Dickinson, D. R.
Partner: UNT Libraries Government Documents Department
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A fast multipole transformation for global climate calculations

Description: A fast multipole transformation is adapted to the evaluation of summations that occur in global climate calculations when transforming between spatial and spherical harmonic representations. For each summation, the timing of the fast multipole transformation scales linearly with the number of latitude gridpoints, but the timing for direct evaluations scales quadratically. In spite of a larger computational overhead, this scaling advantage renders the fast multipole method faster than direct eva… more
Date: January 1, 1996
Creator: Holmes, J.A.; Wang, Z.; Drake, J.B.; Lyon, B.F. & Chen, W.T.
Partner: UNT Libraries Government Documents Department
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Task 1.6 -- Mixed waste. Topical report, April 1994--September 1995

Description: For fifty years, the United States was involved in a nuclear arms race of immense proportions. During the majority of this period, the push was always to design new weapons, produce more weapons, and increase the size of the arsenal, maintaining an advantage over the opposition in order to protect US interests. Now that the Cold War is over, the US is faced with the imposing tasks of dismantling, cleaning up, and remediating the wide variety of problems created by this arms race. The ability to… more
Date: January 1, 1996
Creator: Rindt, John R. & Jones, Frank A.
Partner: UNT Libraries Government Documents Department
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Test and evaluation document for DOT Specification 7A Type A Packaging. Revision 3

Description: The US Department of Energy (DOE) has been conducting, through several of its operating contractors, an evaluation and testing program to qualify Type A radioactive material packagings per US Department of Transportation (DOT) Specification 7A (DOT-7A) of the Code of Federal Regulations (CFR), Title 49, Part 178 (49 CFR 178). The program is currently administered by the DOE, Office of Facility Safety Analysis, DOE/EH-32, at DOE-Headquarters (DOE-HQ) in Germantown, Maryland. This document summar… more
Date: January 30, 1996
Partner: UNT Libraries Government Documents Department
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Interim safety equipment list for 241-C-106 waste retrieval, project W-320

Description: The purpose of this supporting document is to provide safety classifications for systems, structures, and components of the Tank 241-C-106 Waste Retrieval Sluicing System (WRSS) and to document the methodology used to develop these safety classifications. The WRSS requires two transfer lines, one to carry sluiced waste slurry to tank 241-AY-102 and the other to return supernatant to tank 241-C-106; pumps in each tank; sluicers to direct the supernatant stream inside tank 241-C-106; a slurry dis… more
Date: January 25, 1996
Creator: Conner, J. C.
Partner: UNT Libraries Government Documents Department
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Title list of documents made publicly available, November 1-30, 1995

Description: The Title List of Documents Made Publicly Available is a monthly publication. It contains descriptions of the information received and generated by the U.S. Nuclear Regulatory Commission (NRC). This information includes (1) docketed material associated with civilian nuclear power plants and other uses of radioactive materials and (2) nondocketed material received and generated by NRC pertinent to its role as a regulatory agency. As used here, docketed does not refer to Court dockets; it refers … more
Date: January 1, 1996
Partner: UNT Libraries Government Documents Department
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Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

Description: Pacific Northwest National Laboratory (Northwest National Laboratory) conducted this study as a joint effort between the ``Develop and Test Sorbents`` task for the Efficient Separations and Processing Cross-Cutting Program (ESP) and the ``Batch Testing of Crystalline Silico-Titanates (CSTs)`` subtask, which is part of the Northwest National Laboratory Tank Waste Remediation System (TWRS) Pretreatment Technology Development Project. The objective of the study is to investigate radionuclide uptak… more
Date: January 1, 1996
Creator: Brown, G.N.; Bray, L.A. & Carlson, C.D.
Partner: UNT Libraries Government Documents Department
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On the convergence of the phase gradient autofocus algorithm for synthetic aperture radar imaging

Description: Synthetic Aperture Radar (SAR) imaging is a class of coherent range and Doppler signal processing techniques applied to remote sensing. The aperture is synthesized by recording and processing coherent signals at known positions along the flight path. Demands for greater image resolution put an extreme burden on requirements for inertial measurement units that are used to maintain accurate pulse-to-pulse position information. The recently developed Phase Gradient Autofocus algorithm relieves thi… more
Date: January 1, 1996
Creator: Hicks, Mary Jane
Partner: UNT Libraries Government Documents Department
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Validation of MCNP4a for highly enriched uranium using the Battelle process safety and risk management IBM RS/6000 workstation

Description: This document has been prepared to allow use of the Radiation Shielding and Information Center (RSIC) release of MCNP4a, which has been installed on the Battelle Process Safety and Risk Management (PSRM) IBM RS/6000 workstation, for production calculations for the Portsmouth Gaseous Diffusion Plant (PORTS). This hardware/software configuration is under the configuration control plan listed in Reference 1. The first portion of this document outlines basic information with regard to validation of… more
Date: January 1, 1996
Creator: Negron, S.B.; Lee, B.L. Jr. & Tayloe, R. W., Jr.
Partner: UNT Libraries Government Documents Department
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The Office of Environmental Management technical reports: A bibliography

Description: The Office of Environmental Management`s (EM) technical reports bibliography is an annual publication that contains information on scientific and technical reports sponsored by the Office of Environmental Management added to the Energy Science and Technology Database from July 1, 1994 through June 30, 1995. This information is divided into the following categories: Focus Areas, Cross-Cutting Programs, and Support Programs. In addition, a category for general information is included. EM`s Office… more
Date: January 1, 1996
Partner: UNT Libraries Government Documents Department
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Mixed waste focus area integrated technical baseline report. Phase I, Volume 2: Revision 0

Description: This document (Volume 2) contains the Appendices A through J for the Mixed Waste Focus Area Integrated Technical Baseline Report Phase I for the Idaho National Engineering Laboratory. Included are: Waste Type Managers` Resumes, detailed information on wastewater, combustible organics, debris, unique waste, and inorganic homogeneous solids and soils, and waste data information. A detailed list of technology deficiencies and site needs identification is also provided.
Date: January 16, 1996
Partner: UNT Libraries Government Documents Department
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Validation of nuclear criticality safety software and 27 energy group ENDF/B-IV cross sections. Revision 1

Description: The original validation report, POEF-T-3636, was documented in August 1994. The document was based on calculations that were executed during June through August 1992. The statistical analyses in Appendix C and Appendix D were completed in October 1993. This revision is written to clarify the margin of safety being used at Portsmouth for nuclear criticality safety calculations. This validation gives Portsmouth NCS personnel a basis for performing computerized KENO V.a calculations using the Lock… more
Date: January 1, 1996
Creator: Lee, B.L. Jr. & D`Aquila, D.M.
Partner: UNT Libraries Government Documents Department
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