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POC-scale testing of an advanced fine coal dewatering equipment/technique: Quarterly technical progress report,January--March 1997
Laboratory centrifugal dewatering tests were conducted to study the effects of anionic and cationic flocculants on filtration of PMCC compliance (low sulfur) and non-compliance (high sulfur) ultrafine coal slurry. The results obtained with compliance coal indicated that use of 30 g/t anionic flocculant reduced filter cake moisture from 32. 3 to 29.0 percent and increased solids recovery by two absolute percentage points. Use of cationic flocculant had no effects on solids recovery but lowered cake moisture to 27 percent at a dosage of 15 g/t. With the non-compliance coal slurry addition of 15 g/t anionic flocculant lowered cake moisture from 30 to 28.5 percent with marginal effects on solids recovery; addition of cationic flocculant reduced cake moisture by one absolute percentage point. Both flocculants showed marginal effects on solids recovery. Laboratory vacuum filter leaf filtration studies showed that use of flocculants considerably increased filtration kinetics. For example, addition of 15 g/t anionic flocculant to the compliance coal slurry increased filtration kinetics by 10 times and addition of 15 g/t.
Date:
May 7, 1997
Creator:
Tao, D.; Grappo, J. G. & Parekh, B. K.
Object Type:
Report
System:
The UNT Digital Library
Hanford Radiological Protection Support Services Annual Report for 2000
During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: 1) external dosimetry, 2) internal dosimetry, 3) in vivo monitoring, 4) radiological records, 5) instrument calibration and evaluation, and 6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.
Date:
May 7, 2001
Creator:
Lynch, Timothy P.; Bihl, Donald E.; Johnson, Michelle L.; Maclellan, Jay A. & Piper, Roman K.
Object Type:
Report
System:
The UNT Digital Library
Hanford Radiological Protection Support Services Annual Report for 2000
During calendar year 2000, the Pacific Northwest National Laboratory performed its customary radiological protection support services in support of the U.S. Department of Energy Richland Operations Office and the Hanford contractors. These services included: (1) external dosimetry, (2) internal dosimetry, (3) in vivo monitoring, (4) radiological records, (5) instrument calibration and evaluation, and (6) calibration of radiation sources traceable to the National Institute of Standards and Technology. Each program summary describes the routine operations, program changes and improvements, program assessments, supporting technical studies, and professional activities.
Date:
May 7, 2001
Creator:
Lynch, Timothy P; Bihl, Donald E; Johnson, Michelle L; Maclellan, Jay A & Piper, Roman K
Object Type:
Report
System:
The UNT Digital Library
N-Reactor Department monthly report, April 1963
This document details activities of the N-Reactor Department during the month of April 1963.
Date:
May 7, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Engineered Aerosol Production for Laboratory Scale Chemical / Biological Test and Evaluation
None
Date:
May 7, 2007
Creator:
Dougherty, G M; Hadley, D R; O'Connor, P R & Bottiger, J R
Object Type:
Report
System:
The UNT Digital Library
Notes on Object-Orientation
This report discusses the uses of programming by object-orientation. Included in this report are the following: overview of concepts; software development; user interfaces; and databases.
Date:
May 7, 1996
Creator:
Bush, Brian W.
Object Type:
Report
System:
The UNT Digital Library
Authorized Limits Request: Radiological Clearance of Select Hanford Reach National Monument Lands
This document describes development of radiological release criteria (Authorized Limits) for Hanford Reach National Monument lands that DOE plans to release to the U.S. Department of the Interior.
Date:
May 7, 2004
Creator:
Napier, Bruce A. & Glines, Wayne M.
Object Type:
Report
System:
The UNT Digital Library
Fuels Preparation Department monthly report, April 1961
This document details activities of the Fuels Preparation Department during the month of April 1961. (FI)
Date:
May 7, 1961
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Certification of MCNP version 4A for WHC computer platforms
MCNP is a general-purpose Monte Carlo code that can be used for neutron, photon, or coupled neutron/photon transport, including the capability to calculate eigenvalues for critical systems. The code treats an arbitrary three-dimensional configuration of materials in geometric cells bounded by first- and second-degree surfaces, and some special fourth-degree surfaces (elliptical tori).
Date:
May 7, 1996
Creator:
Carter, L.L., Westinghouse Hanford
Object Type:
Report
System:
The UNT Digital Library
Advanced Algorithms and Automation Tools for Discrete Ordinates Methods in Parallel Environments
This final report discusses major accomplishments of a 3-year project under the DOE's NEER Program. The project has developed innovative and automated algorithms, codes, and tools for solving the discrete ordinates particle transport method efficiently in parallel environments. Using a number of benchmark and real-life problems, the performance and accuracy of the new algorithms have been measured and analyzed.
Date:
May 7, 2003
Creator:
Haghighat, Alireza
Object Type:
Report
System:
The UNT Digital Library
Groundwater Quality Assessment Plan for Single-Shell Tank Waste Management Area B-BX-BY at the Hanford Site, Interim Change Notice 1
This ICN updates the assessment plan to reflect the addition of wells newly installed in FY2001. Project scientists will provide a schedule change request identifying the wells as new and providing a list of constituents and sample frequencies to the sample scheduler.
Date:
May 7, 2002
Creator:
Narbutovskih, Susan M.
Object Type:
Report
System:
The UNT Digital Library
GLYCOLIC-NITRIC ACID FLOWSHEET DEMONSTRATION OF THE DWPF CHEMICAL PROCESSING CELL WITH MATRIX SIMULANTS AND SUPERNATE
Savannah River Remediation (SRR) is evaluating changes to its current DWPF flowsheet to improve processing cycle times. This will enable the facility to support higher canister production while maximizing waste loading. Higher throughput is needed in the CPC since the installation of the bubblers into the melter has increased melt rate. Due to the significant maintenance required for the DWPF gas chromatographs (GC) and the potential for production of flammable quantities of hydrogen, reducing or eliminating the amount of formic acid used in the CPC is being developed. Earlier work at Savannah River National Laboratory has shown that replacing formic acid with an 80:20 molar blend of glycolic and formic acids has the potential to remove mercury in the SRAT without any significant catalytic hydrogen generation. This report summarizes the research completed to determine the feasibility of processing without formic acid. In earlier development of the glycolic-formic acid flowsheet, one run (GF8) was completed without formic acid. It is of particular interest that mercury was successfully removed in GF8, no formic acid at 125% stoichiometry. Glycolic acid did not show the ability to reduce mercury to elemental mercury in initial screening studies, which is why previous testing focused on using …
Date:
May 7, 2012
Creator:
Lambert, D.; Stone, M.; Newell, J. & Best, D.
Object Type:
Report
System:
The UNT Digital Library
EFFECTS OF MINERALOGY AND CATION-EXCHANGE CAPACITY ON LIGHIUM SORPTION TO YUCCA MOUNTAIN TUFFS.
None
Date:
May 7, 1998
Creator:
Anghel, I.; Turnin, H. J.; Reimus, P. W. & Carey, J. W.
Object Type:
Report
System:
The UNT Digital Library
MODEL 9975 SHIPPING PACKAGE FABRICATION PROBLEMS AND SOLUTIONS
The Model 9975 Shipping Package is the latest in a series (9965, 9968, etc.) of radioactive material shipping packages that have been the mainstay for shipping radioactive materials for several years. The double containment vessels are relatively simple designs using pipe and pipe cap in conjunction with the Chalfont closure to provide a leak-tight vessel. The fabrication appears simple in nature, but the history of fabrication tells us there are pitfalls in the different fabrication methods and sequences. This paper will review the problems that have arisen during fabrication and precautions that should be taken to meet specifications and tolerances. The problems and precautions can also be applied to the Models 9977 and 9978 Shipping Packages.
Date:
May 7, 2008
Creator:
May, C & Allen Smith, A
Object Type:
Article
System:
The UNT Digital Library
Instrumentation and control system for the AT-2 accelerator test stand
A data-driven subroutine package, written for our accelerator test stand (ATS), is described. This flexible package permits the rapid writing and modifying of data acquisition, control, and analysis programs for the many diverse experiments performed on the ATS. These structurally simple and easy to maintain routines help to control administratively the integrity of the ATS through the use of the database. Our operating experience indicates that the original design goals have been met. We describe the subroutines, database, and our experiences with this system.
Date:
May 7, 1984
Creator:
Wadlinger, E. A.; Holtkamp, D. B. & Holt, H. D.
Object Type:
Article
System:
The UNT Digital Library
Ventilation system consequence calculations to support salt well pumping single-shell tank 241-A-101
This document presents the radiological dose and toxicological exposure calculations for an accident scenario involved with the ventilation system used to support salt well pumping single-shell tank 241-A-101. This tank has been listed on the Hydrogen Watch List.
Date:
May 7, 1997
Creator:
Ryan, G.W.
Object Type:
Report
System:
The UNT Digital Library
Report on audit of Department of Energy contractor occupational injury and illness reporting practices
The Department and its contractors are responsible for ensuring that a safe and healthy work environment is provided to Department and contractor employees at its operating facilities. Contractors are responsible for establishing a comprehensive occupational safety and health program, which includes reporting of significant work-related employee injuries. The Department is responsible for monitoring the implementation of the contractor`s programs. Two performance indicators used by the Department to measure a contractor`s safety performance are the number and severity of work-related employee injuries and of lost workdays rates. The objective of the audit was to determine whether Department of Energy contractors accurately reported occupational injuries and illnesses in accordance with Departmental requirements.
Date:
May 7, 1997
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
The ASCI PSE Milepost: Run-Time Systems Performance Tests
The Accelerated Strategic Computing Initiative (ASCI) Problem Solving Environment (PSE) consists of the tools and libraries needed for the development of ASCI simulation codes on ASCI machines. The recently completed ASCI PSE Milepost demonstrated that this software environment is available and functional at the scale used for application mileposts on ASCI White. As part of the PSE Milepost, we performed extensive performance testing of several critical run-time based systems. In this paper, we present microbenchmark results that compare the MPI [5], Pthreads and OpenMP [7, 8] implementations on ASCI White and ASCI Blue Pacific. Our results demonstrate that these run-time systems on White have improved sufficiently to accommodate the machine's approximately four-fold increase in processing capability over Blue Pacific.
Date:
May 7, 2001
Creator:
de Supinski, B R
Object Type:
Article
System:
The UNT Digital Library
Plan for qualification of existing data for waste acceptance
Research and development in support of the DWPF began during the 1970`s at the Savannah River Technology Center (formerly the Savannah River Laboratory). A large amount of data relevant to compliance with the Waste Acceptance Product Specifications (WAPS) was generated prior to the preparation and issue of the WAPS. Thus, most of this data was not generated under a quality assurance program which meets the Office of Civilian Radioactive Waste Management`s requirements. The DWPF has developed a plan for qualification of existing data sets which will be used to establish compliance with the WAPS, which is reported here. In this document, the existing data sets which will be used for compliance are identified, and the method(s) of qualification of each data set for use in the Waste Form Qualification Report is defined. This document thus provides a link between the detailed descriptions of all of the compliance activities in the Waste Form Compliance Plans (WCP), and the requirements for qualification of existing data sets used for compliance purposes. All of these data sets will be qualified by the end of Qualification Runs in the DWPF.
Date:
May 7, 1993
Creator:
Plodinec, M. J. & Marra, S. L.
Object Type:
Report
System:
The UNT Digital Library
Updated ENDL99 Cross Sections for U(n.y) and U(n,f)
In this note, we describe the first of two updates to the uranium isotopes in Livermore's Evaluated Neutron Data Library, ENDL99. Here, we concentrate on improving the (n, f) and (n, {gamma}) evaluations for a limited set of uranium isotopes. The first improvement consisted of creating an evaluation for {sup 232}U using a combination of fission and capture cross sections from the JENDL-3.2 database and the outgoing particle distributions from the exiting ENDL99 {sup 234}U evaluation. The second improvement consisted of updating existing (n, f) and (n, {gamma}) evaluations for uranium isotopes with A=233-238. These improvements are particularly apparent in the neutron resonance region as ENDL99 often contains gross averages over the resonances. We have propagated these updates into various Livermore application libraries.
Date:
May 7, 2002
Creator:
Brown, D.; Dietrich, F.; Hill, T. & McNabb, D.
Object Type:
Report
System:
The UNT Digital Library
NEW METHOD FOR DETERMINATION OF ACTINIDES AND STRONTIUM IN ANIMAL TISSUE
The analysis of actinides in animal tissue samples is very important for environmental monitoring. There is a need to measure actinide isotopes with very low detection limits in animal tissue samples, including fish, deer, hogs, beef and shellfish. A new, rapid actinide separation method has been developed and implemented that allows the measurement of plutonium, neptunium, uranium, americium, curium and strontium isotopes in large animal tissue samples (100-200 g) with high chemical recoveries and effective removal of matrix interferences. This method uses stacked TEVA Resin{reg_sign}, TRU Resin{reg_sign} and DGA-Resin{reg_sign} cartridges from Eichrom Technologies (Darien, IL, USA) that allows the rapid separation of plutonium (Pu), neptunium (Np), uranium (U), americium (Am), and curium (Cm) using a single multi-stage column combined with alpha spectrometry. Sr-90 is collected on Sr Resin{reg_sign} from Eichrom Technologies (Darien, IL, USA). After acid digestion and furnace heating of the animal tissue samples, the actinides and Sr-89/90 are separated using column extraction chromatography. This method has been shown to be effective over a wide range of animal tissue matrices. By using vacuum box cartridge technology with rapid flow rates, sample preparation time is minimized.
Date:
May 7, 2007
Creator:
Maxwell, S; Jay Hutchison, J & Don Faison, D
Object Type:
Article
System:
The UNT Digital Library
Full-Scale Testing of Enhanced Mercury Control Technologies for Wet FGD Systems: Final Report
Wet flue gas desulfurization (wet FGD) systems are currently installed on about 25% of the coal-fired utility generating capacity in the U.S., representing about 15% of the number of coal-fired units. Depending on the effect of operating parameters such as mercury content of the coal, form of mercury (elemental or oxidized) in the flue gas, scrubber spray tower configuration, liquid-to-gas ratio, and slurry chemistry, FGD systems can provide cost-effective, near-term mercury emissions control options with a proven history of commercial operation. For boilers already equipped with FGD systems, the incremental cost of any vapor phase mercury removal achieved is minimal. To be widely accepted and implemented, technical approaches that improve mercury removal performance for wet FGD systems should also have low incremental costs and have little or no impact on operation and SO{sub 2} removal performance. The ultimate goal of the Full-scale Testing of Enhanced Mercury Control for Wet FGD Systems Program was to commercialize methods for the control of mercury in coal-fired electric utility systems equipped with wet flue gas desulfurization (wet FGD). The program was funded by the U.S. Department of Energy's National Energy Technology Laboratory, the Ohio Coal Development Office within the Ohio Department of Development, and …
Date:
May 7, 2003
Creator:
McDonald, D. K.; Amrhein, G. T.; Kudlac, G. A. & Yurchison, D. Madden
Object Type:
Report
System:
The UNT Digital Library
An Experimental Study of Drag Reduction Devices for a Trailer Underbody and Base
Low speed wind tunnel measurements are made on a 1/16th scale generic tractor-trailer model at a width-based Reynolds number of 325,000. The model is fixed to a turntable, allowing the yaw angle to be varied between {+-}14 degrees in 2 degree increments. Various add-on drag reduction devices are mounted to the model underbody and base. The wind-averaged drag coefficient at 65 mph is computed for each configuration, allowing the effectiveness of the add-on devices to be assessed. The most effective add-on drag reduction device for the trailer underbody is a wedge-shaped skirt, which reduces the wind-averaged drag coefficient by 2.0%. For the trailer base, the most effective add-on drag reduction device is a set of curved base flaps having a radius of curvature of 0.91 times the trailer width. These curved base flaps reduce the wind-averaged drag coefficient by 18.8%, providing the greatest drag reduction of any of the devices tested. When the wedge-shaped skirt and curved base flaps are used in conjunction with one another, the wind-averaged drag coefficient is reduced by 20%.
Date:
May 7, 2004
Creator:
Ortega, J M & Salari, K
Object Type:
Article
System:
The UNT Digital Library
Materials Testing Reactor Project Handbook
The following handbook was made for the purpose of: (1) to give a semidetailed description of the testing reactor, and (2) to explain, in so far as possible, the reasons for the design.
Date:
May 7, 1951
Creator:
Argonne National Laboratory
Object Type:
Report
System:
The UNT Digital Library