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263 Matching Results
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Development of coal-based technologies for Department of Defense Facilities. Semiannual technical progress report, March 28, 1997--September 27, 1997
The U.S. Department of Defense (DOD), through an Interagency Agreement with the U.S. Department of Energy (DOE), has initiated a three-phase program with the Consortium for Coal-Water Slurry Fuel Technology, with the aim of developing technologies which can potentially decrease DOD`s reliance on imported oil by increasing its use of coal. The program is being conducted as a cooperative agreement between the Consortium and DOE. Phase I was completed on November 1, 1995. Work in Phase II focused on emissions reductions, coal beneficiation/preparation studies, and economic analyses of coal use. Emissions reductions investigations included performing pilot-scale air toxics (i.e., trace elements and volatile organic compounds) testing and evaluating a ceramic filtering device on the demonstration boiler. Also, a sodium bicarbonate duct injection system was installed on the demonstration boiler. An economic analysis was conducted which investigated the benefits of decreased dependence on imported oil by using new coal combustion technologies. Work related to coal preparation and utilization was primarily focused on preparing the final report. Work in Phase III focused on coal preparation studies, pilot-scale NO{sub x} reduction studies, economic analyses of coal use, and evaluation of deeply-cleaned coal as boiler fuel. Coal preparation studies were focused on continuing activities …
Date:
January 6, 1998
Creator:
Miller, B.G.; Miller, S.F. & Morrison, J.L.
Object Type:
Report
System:
The UNT Digital Library
Conceptual design report for facilities capability assurance program (FCAP) roads and parking lot replacements FY 1994 line item
Mound, located in Montgomery County, Miamisburg, Ohio, on the east bank of the Great Miami River, was established in 1948 by the Atomic Energy Commission to develop and manufacture explosive devices for the United States Government. Mound occupies 305 acres and at present the facility is operated by EG&G Mound Applied Technologies. It is devoted to research, development, testing and manufacturing of components for nuclear weapons systems under the auspices of the United States Department of Energy (DOE). The complex employs approximately 2,200 people generating an annual payroll in excess of $75 million. Whereas Government sponsors have traditionally placed great emphasis on new technological concepts and manufacturing processes for weapons, unfortunately, such has not been the case in the maintenance of the roadway infrastructure. The roadway system which, for the most part is 40 years old, must be restored to a condition which will ensure smooth transportation of weapon component production, safe access for emergency and fire vehicles and safe ingress and egress for pedestrian personnel. This Facilities Capability Assurance Program (FCAP) project will provide this much needed restoration.
Date:
January 6, 1992
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Total Measurement Uncertainty (TMU) for Nondestructive Assay of Transuranic (TRU) Waste at the WRAP Facility
This report examines the contributing factors to NDA measurement uncertainty at WRAP The significance of each factor on the TMU is analyzed and a final method is given for determining the TMU for NDA measurements at WRAP. As more data becomes available and WRAP gains in operational experience this report will be reviewed semi annually and updated as necessary.
Date:
January 6, 2000
Creator:
WILLS, C.E.
Object Type:
Report
System:
The UNT Digital Library
Determination of trace impurities in uranium hexafluoride by an inductively coupled argon plasma spectrometer
A procedure has been developed to determine 21 trace impurity elements in uranium hexafluoride, using inductively coupled argon plasma emission spectrometry (ICAP). The method consists of a liquid-liquid extraction to separate uranium from the trace impurities with a mixture of tri-(2-ethyl-hexyl)-phosphate (TEHP) and heptane. The raffinate containing the elements is subsequently analyzed by ICAP. The impurity elements which can be analyzed by this method are: Al, B, Ba, Be, Bi, Ca, Cd, Co, Cr, Cu, Fe, Mg, Mn, Na, Ni, Pb, Sb, Sn, Ti, V and Zn.
Date:
January 6, 1983
Creator:
Short, B. W.; Spring, H. S. & Grant, R. L.
Object Type:
Report
System:
The UNT Digital Library
Weekly report - 100 areas - January 6, 1955
None
Date:
January 6, 1955
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Increased CPC batch size study for Tank 42 sludge in the Defense Waste Processing Facility
A series of experiments have been completed at TNX for the sludge-only REDOX adjusted flowsheet using Tank 42 sludge simulant in response to the Technical Task Request HLW/DWPT/TTR-980013 to increase CPC batch sizes. By increasing the initial SRAT batch size, a melter feed batch at greater waste solids concentration can be prepared and thus increase melter output per batch by about one canister. The increased throughput would allow DWPF to dispose of more waste in a given time period thus shortening the overall campaign.
Date:
January 6, 2000
Creator:
Daniel, W. E.
Object Type:
Report
System:
The UNT Digital Library
RADIATION TESTING OF SHIELD SPECIMEN: TEST LTH/sub x/-4.
None
Date:
January 6, 1958
Creator:
Lee, R.C.
Object Type:
Report
System:
The UNT Digital Library
CH Packaging Operations for High Wattage Waste
This document provides instructions for assembling the following CH packaging payload: Drum payload assembly Standard Waste Box (SWB) assembly Ten-Drum Overpack (TDOP)
Date:
January 6, 2006
Creator:
Washington TRU Solutions, LLC
Object Type:
Report
System:
The UNT Digital Library
Demonstration of Caustic-Side Solvent Extraction with Optimized Solvent in the 2-cm Centrifugal Contactor Apparatus Using Dissolved Salt Cake from Tank 37H
Researchers successfully demonstrated the chemistry of the Caustic-Side Solvent Extraction (CSSX) flow sheet with optimized solvent. This represents the third such process demonstration using actual Savannah River Site (SRS) high level waste (HLW). The present test differed from previous studies in the use of radioactive waste derived from Tank 37H dissolved salt cake, as opposed to supernate solutions used in previous demonstrations.
Date:
January 6, 2003
Creator:
Norato, M. A.
Object Type:
Report
System:
The UNT Digital Library
Hydraulic and Heat Transfer Transients During Power Ramp - Mark VII-AL Tests at Columbia University
Transient tests were run at Columbia University on a Mark VII-AL mockup to reproduce the hydraulics and heat transfer in a single fuel assembly during a power ramp resulting from the accidental withdrawal of control rods from a reactor. This document presents results of those tests.
Date:
January 6, 2003
Creator:
Durant, W. S.
Object Type:
Report
System:
The UNT Digital Library
Cryogenic moderator simulations : confronting reality.
The Intense Pulsed Neutron Source (IPNS) at Argonne National Laboratory is a spallation neutron source dedicated to materials research. Its three cryogenic methane moderators provide twelve neutron beams to fourteen instruments and test facilities. This report concerns ongoing activities for benchmarking our Monte Carlo model of the IPNS neutron generation system. This paper concentrates on the techniques (both experimental and calculational) used in such benchmarking activities.
Date:
January 6, 1999
Creator:
Iverson, E. B.
Object Type:
Article
System:
The UNT Digital Library
SuperLig(TM) 644 Ion Exchange Resin Stability in Nitric Acid at Elevated Temperatures
In the Hanford River Protection Project Waste Treatment Plan (RPP-WTP) flowsheet, opportunity exists for the organic SuperLig 644(TM) cation exchange resin to come in contact with concentrated (5 M) nitric acid at elevated temperatures in the acid recovery evaporator. These are similar conditions where other ion exchange resin (albeit usually anion) column explosions have occurred. The objective of these tests was to examine potential hazards by exposing the resin to conditions expected in the facility and examining the composition of the reaction products and their reactivity.
Date:
January 6, 2003
Creator:
Nash, C.A.
Object Type:
Report
System:
The UNT Digital Library
Engineering Task Plan for Preparing the Type 4 In Situ Vapor Samplers (ISVS) for Use
The DOE has identified a need to sample vapor space and exhaust ducts of several waste tanks The In-Situ Vapor Sampling (ISVS) Type IV vapor sampling cart has been identified as the appropriate monitoring tool. The ISVS carts have been out of service for a number of years. This ETP outlines the work to be performed to ready the type IV gas sampler for operation Characterization Engineering will evaluate the Type IV gas sampler carts to determine their state of readiness and will proceed to update procedures and equipment documentation to make the sampler operationally acceptable.
Date:
January 6, 2000
Creator:
Boger, R. M.
Object Type:
Report
System:
The UNT Digital Library
Plutonium finishing plant safety systems and equipment list
The Safety Equipment List (SEL) supports Analysis Report (FSAR), WHC-SD-CP-SAR-021 and the Plutonium Finishing Plant Operational Safety Requirements (OSRs), WHC-SD-CP-OSR-010. The SEL is a breakdown and classification of all Safety Class 1, 2, and 3 equipment, components, or system at the Plutonium Finishing Plant complex.
Date:
January 6, 1995
Creator:
Bergquist, G. G.
Object Type:
Report
System:
The UNT Digital Library
PROCEEDINGS OF RIKEN BNL RESEARCH CENTER WORKSHOP: VOLUME 69 RBRC SCIENTIFIC REVIEW COMMITTEE MEETING.
None
Date:
January 6, 2005
Creator:
Samios, N. P.
Object Type:
Report
System:
The UNT Digital Library
Primary rock excavation using the IKC Impact Kerfing Cutter (Excavation: rates, forces, and working life). Final report to the US DOE
The final report reviews the development of a rock cutting tool using impact. Use of the Ramex Mining Boom, a hydraulic breaker, and lab testing are described.
Date:
January 6, 2003
Creator:
Handewith, Howard J.
Object Type:
Report
System:
The UNT Digital Library
Tank waste remediation system mission analysis report
The Tank Waste Remediation System Mission Analysis Report identifies the initial states of the system and the desired final states of the system. The Mission Analysis Report identifies target measures of success appropriate to program-level accomplishments. It also identifies program-level requirements and major system boundaries and interfaces.
Date:
January 6, 1998
Creator:
Acree, C. D.
Object Type:
Report
System:
The UNT Digital Library
Source Term Determination for Spills of Binary Liquid Solutions
The methodology in this report results in the determination of an average vapor pressure over a predetermined time period of interest. The time period of interest is based on whether the most limiting constituent partial pressure increases or decreases over time. This average partial pressure is then used for determination of source terms for spills of the solution.
Date:
January 6, 1997
Creator:
Blanchard, A. & Hadlock, D.
Object Type:
Report
System:
The UNT Digital Library
Exploration of Optimization Options for Increasing Performance of a GPU Implementation of a Three-dimensional Bilateral Filter
This report explores using GPUs as a platform for performing high performance medical image data processing, specifically smoothing using a 3D bilateral filter, which performs anisotropic, edge-preserving smoothing. The algorithm consists of a running a specialized 3D convolution kernel over a source volume to produce an output volume. Overall, our objective is to understand what algorithmic design choices and configuration options lead to optimal performance of this algorithm on the GPU. We explore the performance impact of using different memory access patterns, of using different types of device/on-chip memories, of using strictly aligned and unaligned memory, and of varying the size/shape of thread blocks. Our results reveal optimal configuration parameters for our algorithm when executed sample 3D medical data set, and show performance gains ranging from 30x to over 200x as compared to a single-threaded CPU implementation.
Date:
January 6, 2012
Creator:
Bethel, E. Wes & Bethel, E. Wes
Object Type:
Report
System:
The UNT Digital Library
Robots Working with Hazardous Materials
While many research and development activities take place at Sandia National Laboratories' Intelligent Systems and Robotics Center (ISRC), where the "rubber meets the road" is in the ISRC'S delivered systems. The ISRC has delivered several systems over the last few years that handle hazardous materials on a daily basis, and allow human workers to move to a safer, supervisory role than the "hands-on" operations that they used to perform. The ISRC at Sandia performs a large range of research and development activities, including development and delivery of one-of-a-kind robotic systems for use with hazardous materials. Our mission is to create systems for operations where people can't or don't want to perform the operations by hand, and the systems described in this article are several of our first-of-a-kind deliveries to achieve that mission.
Date:
January 6, 1999
Creator:
Amai, W. & Fahrenholtz, J.
Object Type:
Article
System:
The UNT Digital Library
Experimental Determination of the Effect of Reactor Radiation on the Thermal Conductivity of Uranium-Impregnated Graphite
Experiments are described in which the change in thermal conductivity of U-impregnated graphite under neutron irradiation was measured. Thermal resistivities relative to the thermal resistivity of undamaged impregnated graphite are reorted as functions of exposure. From applications of the expermental results to the North American Aviation low-power research reactor the peak tem. of the core is determined for a given reactor power and time of operation.
Date:
January 6, 1953
Creator:
Hetrick, D. L.; McCarty, W. K.; Steele, G. N.; Brown, M. S.; Clark, E. V.; Holmes, F. R. et al.
Object Type:
Report
System:
The UNT Digital Library
Fire Hazards Analysis for the 200 Area Interim Storage Area
This documents the Fire Hazards Analysis (FHA) for the 200 Area Interim Storage Area. The Interim Storage Cask, Rad-Vault, and NAC-1 Cask are analyzed for fire hazards and the 200 Area Interim Storage Area is assessed according to HNF-PRO-350 and the objectives of DOE Order 5480 7A. This FHA addresses the potential fire hazards associated with the Interim Storage Area (ISA) facility in accordance with the requirements of DOE Order 5480 7A. It is intended to assess the risk from fire to ensure there are no undue fire hazards to site personnel and the public and to ensure property damage potential from fire is within acceptable limits. This FHA will be in the form of a graded approach commensurate with the complexity of the structure or area and the associated fire hazards.
Date:
January 6, 2000
Creator:
Johnson, D. M.
Object Type:
Report
System:
The UNT Digital Library
Status, plans, and capabilities of the Nuclear Criticality Information System
The Nuclear Criticality Information System (NCIS), in preparation since 1981, has substantially evolved and now contains a growing number of resources pertinent to nuclear criticality safety. These resources include bibliographic compilations, experimental data, communications media, and the International Directory of Nuclear Criticality Safety Personnel. These resources are part of the LLNL Technology Information System (TIS) which provides the host computer for NCIS. The TIS provides nationwide access to authorized members of the nuclear criticality community via interactive dial-up from computer terminals that utilize communication facilities such as commercial and federal telephone networks, toll-free WATS lines, TYMNET, and the ARPANET/MILNET computer network.
Date:
January 6, 1984
Creator:
Koponen, B. L.
Object Type:
Article
System:
The UNT Digital Library
Numerical Modeling Tools for the Prediction of Solution Migration Applicable to Mining Site
Mining has always had an important influence on cultures and traditions of communities around the globe and throughout history. Today, because mining legislation places heavy emphasis on environmental protection, there is great interest in having a comprehensive understanding of ancient mining and mining sites. Multi-disciplinary approaches (i.e., Pb isotopes as tracers) are being used to explore the distribution of metals in natural environments. Another successful approach is to model solution migration numerically. A proven method to simulate solution migration in natural rock salt has been applied to project through time for 10,000 years the system performance and solution concentrations surrounding a proposed nuclear waste repository. This capability is readily adaptable to simulate solution migration around mining.
Date:
January 6, 1999
Creator:
Martell, M. & Vaughn, P.
Object Type:
Article
System:
The UNT Digital Library