Country
States
Decade
Month
Day
Language
3,417 Matching Results
Results open in a new window/tab.
Status of irradiations performed by testing and irradiation services for BNW as of March 10, 1968
This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Specific data given is TISR No., Request number, Material, Piece number, operating time, CMK Absorbed, charge date, location, exposure to date, discharge date and time, and shipping date.
Date:
March 25, 1968
Creator:
Barker, L. V.
Object Type:
Report
System:
The UNT Digital Library
Understanding and Tailoring the Mechanical Properties of LIGA Fabricated Materials
LIGA fabricated materials and components exhibit several processing issues affecting their metallurgical and mechanical properties, potentially limiting their usefulness for MEMS applications. For example, LIGA processing by metal electrodeposition is very sensitive to deposition conditions which causes significant processing lot variations of mechanical and metallurgical properties. Furthermore, the process produces a material with a highly textured lenticular rnicrostructural morphology suggesting an anisotropic material response. Understanding and controlling out-of-plane anisotropy is desirable for LIGA components designed for out-of-plane flexures. Previous work by the current authors focused on results from a miniature servo-hydraulic mechanical test frame constructed for characterizing LIGA materials. Those results demonstrated microstructural and mechanical properties dependencies with plating bath current density in LIGA fabricated nickel (LIGA Ni). This presentation builds on that work and fosters a methodology for controlling the properties of LIGA fabricated materials through processing. New results include measurement of mechanical properties of LIGA fabricated copper (LIGA Cu), out-of-plane and localized mechanical property measurements using compression testing and nanoindentation of LIGA Ni and LIGA Cu.
Date:
January 25, 1999
Creator:
Buchheit, T.E.; Christenson, T.R.; Lavan, D.A. & Schmale, D.T.
Object Type:
Article
System:
The UNT Digital Library
Engineering development of advanced physical fine coal cleaning for premium fuel applications. Quarterly technical progress report 9, October 1, 1994--December 31, 1994
The primary goal of this project is the engineering development of two advanced physical fine coal cleaning processes, column flotation and selective agglomeration, for premium fuel applications. The project scope includes laboratory research and bench-scale testing on six coals to optimize these processes, followed by design, and construction of a 2-t/hr process development unit (PDU). The PDU will then be operated to generate 200 ton lots of each of three project coals, by each process. The project began in October, 1992 and is scheduled for completion by March, 1997. During Quarter 9 (October--December, 1995), parametric and optimization testing was completed for the Taggart, Sunnyside, and Indiana VII coal using a 12-inch Microcel{trademark} flotation column. The detailed design of the 2-t/hr PDU grinding, flotation, and dewatering circuits neared completion with the specification of the major pieces of capital equipment to be purchased for these areas. Selective agglomeration test work investigated the properties of various industrial grades of heptane for use during bench- and PDU-scale testing. It was decided to use a hydrotreated grade of commercial heptane due to its low cost and low concentration of aromatic compounds. The final Subtask 6.4 CWF Formulation Studies Test Plan was issued. A draft version …
Date:
January 25, 1995
Creator:
Moro, N.; Shields, G. L.; Smit, F. J. & Jha, M. C.
Object Type:
Report
System:
The UNT Digital Library
Engineering report standard hydrogen monitoring system problems
Engineering Report to document moisture problems found during the sampling of the vapors in the dome space for hydrogen in the storage tanks and a recommended solution.
Date:
September 25, 1996
Creator:
Golberg, R.L.
Object Type:
Report
System:
The UNT Digital Library
Development of radiological concentrations and unit liter doses for TWRS FSAR radiological consequence calculations
The analysis described in this report develops the Unit Liter Doses for use in the TWRS FSAR. The Unit Liter Doses provide a practical way to calculate conservative radiological consequences for a variety of potential accidents for the tank farms.
Date:
April 25, 1996
Creator:
Cowley, W. L.
Object Type:
Report
System:
The UNT Digital Library
Metal detector study for Hanford
This study was undertaken at the request of the Hanford Works to investigate the possibility of detecting 3/8 inch diameter boron-steel control-balls which become lodged within cracks between the graphite blocks of an atomic pile. The cracks concerned occur radially from 4 3/16 inch diameter holes which pass vertically through the pile. The problem is complicated by the following facts: The graphite blocks are conducting and will therefore give rise to spurious signals primarily due to the cracks between blocks. Numerous aluminum tubes containing water and bars of uranium pass horizontally through the pile at distances closer to the hole than the ball at its extreme position. The vertical holes themselves are warped in an arbitrary manner. Calculations were made to determine theoretically whether or not the ball could be detected. Best operating frequency and coil design were also determined. Tests were made utilizing a specially designed search coil and a test section of graphite pile. Measurements of particle voltage vs. position relative to the coil were made and compared with that resulting from the graphite.
Date:
March 25, 1952
Creator:
Hansen, W.O.
Object Type:
Report
System:
The UNT Digital Library
Advanced Reactors Transition program fiscal year 1998 multi-year work plan
The mission of the Advanced Reactors Transition program is two-fold. First, the program is to maintain the Fast Flux Test Facility (FFTF) and the Fuels and Materials Examination Facility (FMEF) in Standby to support a possible future role in the tritium production strategy. Secondly, the program is to continue deactivation activities which do not conflict with the Standby directive. On-going deactivation activities include the processing of non-usable, irradiated, FFTF components for storage or disposal; deactivation of Nuclear Energy legacy test facilities; and deactivation of the Plutonium Recycle Test Reactor (PRTR) facility, 309 Building.
Date:
September 25, 1997
Creator:
Gantt, D.A.
Object Type:
Report
System:
The UNT Digital Library
Calculation notes in support of TWRS FSAR spray leak accident analysis
This document contains the detailed calculations that support the spray leak accident analysis in the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The consequence analyses in this document form the basis for the selection of controls to mitigate or prevent spray leaks throughout TWRS. Pressurized spray leaks can occur due to a breach in containment barriers along transfer routes, during waste transfers. Spray leaks are of particular safety concern because, depending on leak dimensions, and waste pressure, they can be relatively efficient generators of dispersible sized aerosols that can transport downwind to onsite and offsite receptors. Waste is transferred between storage tanks and between processing facilities and storage tanks in TWRS through a system of buried transfer lines. Pumps for transferring waste and jumpers and valves for rerouting waste are located inside below grade pits and structures that are normally covered. Pressurized spray leaks can emanate to the atmosphere due to breaches in waste transfer associated equipment inside these structures should the structures be uncovered at the time of the leak. Pressurized spray leaks can develop through holes or cracks in transfer piping, valve bodies or pump casings caused by such mechanisms as corrosion, erosion, thermal stress, …
Date:
September 25, 1996
Creator:
Hall, B.W.
Object Type:
Report
System:
The UNT Digital Library
Supporting document for the historical tank content estimate for the SX-tank farm
This Supporting Document provides historical in-depth characterization information on SX-Tank Farm, such as historical waste transfer and level data, tank physical information, temperature plots, liquid observation well plots, chemical analyte and radionuclide inventories for the Historical Tank Content Estimate Report for the Southwest Quadrant of the Hanford 200 West Area.
Date:
February 25, 1997
Creator:
Brevick, C. H.
Object Type:
Report
System:
The UNT Digital Library
Mobile X-ray imaging systems for the tank waste characterization project at the Hanford site
Stored waste tank sampling of radioactive high-level nuclear waste is reilu ired for continued operations, waste characterization, and site safety. The Hanford site tank farms consist of 28 double- shell and 1.49 single-shell underground storage tanks. The ``full`` capacity of each of these tanks is approximately 1 million gallons. The waste stored in these tanks was generated as a result of defense materials production over the course of 4 decades. The single shell tanks are out-of-service and no longer receive liquid waste. Core samples of salt cake, liquid and sludge are remotely obtained using truck-mounted core drill platforms. Samples are recovered from the tanks through a 2.25-inch diameter drill pipe,, in segments contained in specially designed stainless steel samplers approximately 1.5-inch in outside diameter and 26-inches long. The sampled material in a given segment can include crystalline salt-cake, liquid, sludge and entrained gas. Drilling parameters will necessarily vary with different waste types, e.g., crystalline salt-cake versus sludge. At times, the core sample recovery has been marginal and inadequate for laboratory analysis needs. This necessitated a system to provide the drill-truck operators with ``real-time`` feedback about the physical condition of the sampled ``formation`` and the percent recovery, prior to receiving .,isual …
Date:
September 25, 1996
Creator:
Weber, J.R.
Object Type:
Report
System:
The UNT Digital Library
Experimental evaluation of solids suspension uniformity in canyon process vessels
Experimental evaluation of solids suspension in canyon process vessels was performed at several paddle agitator speeds and different volume levels in a geometrically similar vessel. The paddle agitator speeds examined were 280, 370, 528, and 686 rpm and volume levels were 30%, 50%, and 70% fill capacity. Experiments were conducted with simulated solid particles that have particle size range and density similar to plutonium particles and corrosion products typically seen in canyon vessels. Solids suspension took place in baffled cylindrical vessel equipped with two flat-blade agitators and cooling helices.
Date:
June 25, 1996
Creator:
Hassan, N. M.
Object Type:
Report
System:
The UNT Digital Library
Coal Conversion Wastewater Treatment by Catalytic Oxidation in Supercritical Water
In previous reports, we showed that CARULITE 150 from Carus Chemical Company was so effective with oxidation of phenol in supercritical water (SCW) that the results we obtained were likely influenced by internal mass-transfer resistance. We also reported that oxidation of phenol over MnO{sub 2} powder in SCW improved the conversions of both phenol and total organic carbon (TOC) relative to non-catalytic oxidation while the catalytic oxidation kinetics was free from mass-transfer limitation. In this report we continued the investigation of oxidation over the MnO{sub 2} powder in SCW.
Date:
August 25, 1997
Creator:
Savage, P.E.
Object Type:
Report
System:
The UNT Digital Library
Tank characterization report for single-shell tank 241-T-110
This document summarizes the information on the historical uses, present status, and the sampling and analysis results of waste stored in Tank 241-T-110. This report supports the requirements of the Tri-Party Agreement Milestone M-44-15B. Tank 241-T-110 is listed on the Hydrogen Watch List.
Date:
February 25, 1998
Creator:
McCain, D.J.
Object Type:
Report
System:
The UNT Digital Library
CO{sub 2} Hugg-n-Puff process in a light oil shallow shelf carbonate reservoir. Quarterly technical progress report, 2nd quarter 1996
The principal objective of the Central Vacuum Unit (CVU) CO{sub 2} Huff-n-Puff (H-n-P) project is to determine the feasibility and practicality of the technology in a waterflooded shallow shelf carbonate environment. The results of parametric simulation of the CO{sub 2} H-n-P process, coupled with the CVU reservoir characterization components will determine if this process is technically and economically feasible for field implementation. The technology transfer objective of the project is to disseminate the knowledge gained through an innovative plan in support of the Department of Energy`s (DOE) objective of increasing domestic oil production and deferring the abandonment of shallow shelf carbonate (SSC) reservoirs. Tasks associated with this objective are carried out in what is considered a timely effort for near-term goals.
Date:
July 25, 1996
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Prediction of dissolved actinide concentrations in concentrated electrolyte solutions: a conceptual model and model results for the Waste Isolation Pilot Plant (WIPP)
The conceptual model for WIPP dissolved concentrations is a description of the complex natural and artificial chemical conditions expected to influence dissolved actinide concentrations in the repository. By a set of physical and chemical assumptions regarding chemical kinetics, sorption substrates, and waste-brine interactions, the system was simplified to be amenable to mathematical description. The analysis indicated that an equilibrium thermodynamic model for describing actinide solubilities in brines would be tractable and scientifically supportable. This paper summarizes the conceptualization and modeling approach and the computational results as used in the WIPP application for certification of compliance with relevant regulations for nuclear waste repositories. The WIPP site contains complex natural brines ranging from sea water to 10x more concentrated than sea water. Data bases for predicting solubility of Am(III) (as well as Pu(III) and Nd(III)), Th(IV), and Np(V) in these brines under potential repository conditions have been developed, focusing on chemical interactions with Na, K, Mg, Cl, SO{sub 4}, and CO{sub 3} ions, and the organic acid anions acetate, citrate, EDTA, and oxalate. The laboratory and modeling effort augmented the Harvie et al. parameterization of the Pitzer activity coefficient model so that it could be applied to the actinides and oxidation states …
Date:
October 25, 1996
Creator:
Novak, C.F.; Moore, R.C. & Bynum, R.V.
Object Type:
Article
System:
The UNT Digital Library
Free boundary, high beta equilibrium in a large aspect ratio tokamak with nearly circular plasma boundary
An analytic solution is obtained for free-boundary, high-beta equilibria in large aspect ratio tokamaks with a nearly circular plasma boundary. In the absence of surface currents at the plasma-vacuum interface, the free-boundary equilibrium solution introduces constraints arising from the need to couple to an external vacuum field which is physically realizable with a reasonable set of external field coils. This places a strong constraint on the pressure profiles that are consistent with a given boundary shape at high {epsilon}{beta}{sub p}. The equilibrium solution also provides information on the flux surface topology. The plasma is bounded by a separatrix. Increasing the plasma pressure at fixed total current causes the plasma aperture to decrease in a manner that is described.
Date:
September 25, 1996
Creator:
Qin, H. & Reiman, A.
Object Type:
Report
System:
The UNT Digital Library
324 Building radiochemical engineering cells, high-level vault, low-level vault, and associated areas closure plan
The Hanford Site, located adjacent to and north of Richland, Washington, is operated by the US Department of Energy, Richland Operations Office (RL). The 324 Building is located in the 300 Area of the Hanford Site. The 324 Building was constructed in the 1960s to support materials and chemical process research and development activities ranging from laboratory/bench-scale studies to full engineering-scale pilot plant demonstrations. In the mid-1990s, it was determined that dangerous waste and waste residues were being stored for greater than 90 days in the 324 Building Radiochemical Engineering Cells (REC) and in the High-Level Vault/Low-Level Vault (HLV/LLV) tanks. [These areas are not Resource Conservation and Recovery Act of 1976 (RCRA) permitted portions of the 324 Building.] Through the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement) Milestone M-89, agreement was reached to close the nonpermitted RCRA unit in the 324 Building. This closure plan, managed under TPA Milestone M-20-55, addresses the identified building areas targeted by the Tri-Party Agreement and provides commitments to achieve the highest degree of compliance practicable, given the special technical difficulties of managing mixed waste that contains high-activity radioactive materials, and the physical limitations of working remotely in the areas within the subject …
Date:
March 25, 1998
Creator:
Barnett, J. M.
Object Type:
Report
System:
The UNT Digital Library
Microseismic Monitoring of the Mounds Drill Cuttings Injection Tests
This paper describes the microseismic mapping of repeated injections of drill cuttings into two separate formations at a test site near Mounds, OK. Injections were performed in sandstone and shale formations at depths of 830 and 595 m, respectively. Typical injection disposal was simulated using multiple small-volume injections over a three-day period, with long shut-in periods interspersed between the injections. Microseismic monitoring was achieved using a 5-level array of wireline-run, triaxial- accelerometer receivers in a monitor well 76 m from the disposed well. Results of the mapped microseismic locations showed that the disposal domti W= generally aligns with the major horizontal stress with some variations in azimuth and that wide variations in height and length growth occurred with continued injections. These experiments show that the cuttings injection process cm be adequately monitored from a downhole, wireline-run receiver array, thus providing process control and environmental assurance.
Date:
January 25, 1999
Creator:
Branagan, P. T.; Mahrer, K. D.; Moschovidis, Z. A.; Warpinski, N. R. & Wolhart, S. L.
Object Type:
Article
System:
The UNT Digital Library
Project W-320, backup: 1000 CFM portable exhausters acceptance for beneficial use
This document is to identify the Project W-320 1000 CFM portable exhauster documentation required to be turned over from the Projects Organization to the Tank Farm Operations as part of the acceptance of the 1000 CFM portable exhausters for beneficial use.
Date:
July 25, 1998
Creator:
Nelson, O. D.
Object Type:
Report
System:
The UNT Digital Library
Development of chemical vapor composite (CVC) ceramic materials. Status report, April 1995--June 1997
The objective of the 94 DOE Chemical Vapor Composites (CVC) ceramics materials grant is to develop a reliable and flexible process to produce, in a single step, ceramic composites to final shape. This report is a brief summary of activities in the development of the CVC ceramics materials. Equipment has been designed and built to fabricate CVC silicon carbides with fibers such as Nextel, Nicalon, and carbon. Materials and shapes have been fabricated and characterized as to physical and mechanical properties and microstructure. Details will be given in the final report.
Date:
July 25, 1997
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
PUREX/UO{sub 3} facilities deactivation lessons learned: History
In May 1997, a historic deactivation project at the PUREX (Plutonium URanium EXtraction) facility at the Hanford Site in south-central Washington State concluded its activities (Figure ES-1). The project work was finished at $78 million under its original budget of $222.5 million, and 16 months ahead of schedule. Closely watched throughout the US Department of Energy (DOE) complex and by the US Department of Defense for the value of its lessons learned, the PUREX Deactivation Project has become the national model for the safe transition of contaminated facilities to shut down status.
Date:
November 25, 1997
Creator:
Gerber, M. S.
Object Type:
Report
System:
The UNT Digital Library
Energy and angular distributions of radiation power from bending magnet and wiggler sources at a 6-GeV ring
In order to design radiation ports and beam line components, it is essential to understand the distribution of power from a radiation source as a function of both the photon energy and the solid angle of emission. In this preliminary note, we assemble all the formula involved for the case of a bending magnet and a wiggler. Typical distributions are presented for the case of 6-Gev radiation.
Date:
September 25, 1985
Creator:
Shenoy, G. K. & Viccaro, P. J.
Object Type:
Report
System:
The UNT Digital Library
Cesium Removal from R-Reactor Building Disassembly Basin Using 3MEmpore Web-Membrane Filter Technology
A seven-day demonstration of the use of 3M Empore membrane filter loaded with ion exchange material (potassium cobalt hexacynoferrate (CoHex)) for cesium uptake was completed at the R-Disassembly Basin. The main goal of the demonstration was to evaluate the ability of the Process Absorber Development unit (PADU), a water pre-filtration /CoHex configuration on a skid, to remove cesium from R-Disassembly Basin at a linear processing flow rate of 22.71 liters (6 gallons) per minute.
Date:
June 25, 1998
Creator:
Oji, L.N.; Thompson, M.C.; Peterson, K.; May, C. & Kafka, T.M.
Object Type:
Report
System:
The UNT Digital Library
Hanford Site guide for preparing and maintaining generator group pollution prevention program documentation
This document provides guidance to contractor generator groups for developing and maintaining documentation of Pollution Prevention/Waste. Minimization (P2/WMin) Program activities. The program documentation is intended to demonstrate generator compliance with U.S. Department of Energy (DOE) requirements as well as state and Federal regulations.
Date:
November 25, 1997
Creator:
Place, B.G., Westinghouse Hanford, Richland, WA
Object Type:
Report
System:
The UNT Digital Library