Serial/Series Title
Science & Technology Review
4
ARM Facilities Newsletter
3
Fiscal Year 1993
3
Analysis of Devonian Black Shales in Kentucky for Potential Carbon Dioxide Sequestration and Enhanced Natural Gas Production Quarterly Report
2
CO2 Capture by Absorption With Potassium Carbonate Quarterly Report
2
Chief Joseph Kokanee Enhancement Project
2
Enhancement of Equilibrium Shift in Dehydrogenation Reactions Using a Novel Membrane Reactor Semi-Annual Report
2
Fiscal Year 2008
2
A Real-Time Coal Content/Ore Grade (C2OG) Sensor, Technical Report
1
ANL Site Environmental Report
1
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E-1 common analog model. Revision 6.1 (RN-S-0469)
None
Date:
December 29, 1970
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
2-D Simulations of Drainage Winds and Diffusion Compared to Observations
A vertically integrated dynamical drainage flow model is developed from conservation equations for momentum and mass in a terrain-following coordinate system. Wind fields from the dynamical model drive a Monte Carlo transport and diffusion model. The model needs only topographic data, an Eulerian or Lagrangian time scale and a surface drag coefficient for input data, and can be started with a motionless atmosphere. Model wind and diffusion predictions are compared to observations from the rugged Geysers CA area. Model winds generally agree with observed surface winds, and in some cases may give better estimates of area-averaged flow than point observations. Tracer gas concentration contours agree qualitatively with observed contours, and point predictions of maximum concentrations were correctly predicted to within factors of 2 to 10. Standard statistical tests of model skill showed that the accuracy of the predictions varied significantly from canyon to canyon in the Geysers are a. Model wind predictions are also compared to observations from the Savannah River Plant of SC which has gently rolling terrain. The model correctly simulated the slower development of drainage winds and slower deepening of the drainage layer in the Savannah River Valley, relative to the Geysers CA simulations. The SC simulations …
Date:
May 29, 2001
Creator:
Garrett, A. J.
Object Type:
Article
System:
The UNT Digital Library
2-Page Summary for Neptunium solubility in the Near-field Environment of A Proposed Yucca Mountain Repository
The total system performance assessment (TSPA) for the proposed repository at Yucca Mountain, NV, includes a wide variety of processes to evaluate the potential release of radionuclides from the Engineered Barrier System into the unsaturated zone of the geosphere. The principal processes controlling radionuclide release and mobilization from the waste forms are captured in the model to assess the dissolved concentrations of radionuclides in the source-term. The TSPA model of the source-term incorporates the far-from-equilibrium dissolution of, for example, spent nuclear fuel (SNF) to capture bounding rates of radionuclide availability as the SNF degrades. In addition, for individual radionuclides, the source-term model evaluates solubility constraints that are more indicative of longer-term, equilibrium processes that can limit the potential mass transport from the source term in those cases. These solubility limits represent phase saturation and precipitation processes that can occur either at the waste form as it alters, or at other locations in the near-field environment (e.g., within the invert) if chemical conditions are different. Identification and selection of applicable constraints for solubility-limited radionuclide concentrations is a primary focus in formulating the source-term model for the TSPA. Neptunium is a long-lived radionuclide that becomes a larger fraction of the potential dose …
Date:
March 29, 2005
Creator:
Sassani, D.; van Luik, A. & Summerson, J.
Object Type:
Report
System:
The UNT Digital Library
3-D Characterization of the Structure of Paper and Paperboard and Their Application to Optimize Drying and Water Removal Processes and End-Use Applications
The three dimensional structure of paper materials plays a critical role in the paper manufacturing process especially via its impact on the transport properties for fluids. Dewatering of the wet web, pressing and drying will benefit from knowledge of the relationships between the web structure and its transport coefficients. The structure of the pore space within a paper sheet is imaged in serial sections using x-ray micro computed tomography. The three dimensional structure is reconstructed from these sections using digital image processing techniques. The structure is then analyzed by measuring traditional descriptors for the pore space such as specific surface area and porosity. A sequence of microtomographs was imaged at approximately 2 m intervals and the three-dimensional pore-fiber structure was reconstructed. The pore size distributions for both in-plane as well as transverse pores were measured. Significant differences in the in-plane (XY) and the transverse directions in pore characteristics are found and may help partly explain the different liquid and vapor transport properties in the in-plane and transverse directions. Results with varying sheet structures compare favorably with conventional mercury intrusion porosimetry data. Interestingly, the transverse pore structure appears to be more open with larger pore size distribution compared to the in …
Date:
August 29, 2004
Creator:
Shri Ramaswamy, University of Minnesota & B.V. Ramarao, State University of New York
Object Type:
Report
System:
The UNT Digital Library
3-D Measurement of Deformation Microstructure of Al(0.2%)Mg Using Submicron Resolution White X-Ray Microbeams
We have used submicron-resolution white x-ray microbeams on the MHATT-CAT beamline 7-ID at the Advanced Photon Source to develop techniques for three-dimensional investigation of the deformation microstructure in a 20% plane strain compressed Al(0.2%)Mg tri-crystal. Kirkpatrick-Baez mirrors were used to focus white radiation from an undulator to a 0.7 x 0.7 {micro}m{sup 2} beam that was scanned over bi- and tri-crystal regions near the triple-junction of the tri-crystal. Depth resolution along the x-ray microbeam of less than 5 microns was achieved by triangulation to the diffractibn source point using images taken at a series of CCD distances from the microbeam. Computer indexing of the deformation cell structure in the bi-crystal region provided orientations of individual subgrains to {approximately}0.01 degrees, making possible detailed measurements of the rotation axes between individual cells.
Date:
November 29, 1999
Creator:
Larson, B. C.; tamura, N.; Chung, J.-S.; Ice, G. E.; Budai, J. D.; Tischler, J. Z. et al.
Object Type:
Article
System:
The UNT Digital Library
3-D vertical seismic profiling at LLNL Site 300
The initial goal of the 3-D Vertical Seismic Profiling (VSP) work at LLNL was to characterize seismic wave velocities and frequencies below the vadose zone to design the acquisition geometry for a 3-D shallow surface seismic reflection survey. VSPs are also used routinely to provide a link between surface seismic data and well logs. However, a test 2-D seismic line recorded at LLNL in the Spring of 1994 indicated that obtaining high quality reflection images below the vadose zone, yet shallower that 50 m, would require an expensive, very finely sampled survey ({lt} 1 m receiver spacing). Extensive image processing of the LLNL 2-D test line indicated that the only reliable reflection was from the top of the water table. Surprisingly, these results were very different than recent 3-D seismic work recorded at other sites, where high quality, high frequency surface (up to 300 Hz) reflection images were obtained as shallow as 20m. We believe that the differences are primarily due to the comparatively deep vadose zone at LLNL (15 to 30m) as compared to 0-5m at other sites. The thick vadose zone attenuates the reflection signals, particularly at the high frequencies (above 100 @). In addition, the vadose zone …
Date:
January 29, 1997
Creator:
Bainer, R.; Rector, J. & Milligan, P.
Object Type:
Report
System:
The UNT Digital Library
4. pi. interferometric measurements of laser fusion targets
Apparatus is described for rapidly manipulating a hollow glass microsphere laser fusion target and scanning the entire wall with a double pass interference microscope.
Date:
September 29, 1977
Creator:
Weinstein, B.W.; Willenborg, D.L.; Weir, J.T. & Hendricks, C.D.
Object Type:
Article
System:
The UNT Digital Library
10 MW Supercritical CO2 Turbine Test
The Supercritical CO2 Turbine Test project was to demonstrate the inherent efficiencies of a supercritical carbon dioxide (s-CO2) power turbine and associated turbomachinery under conditions and at a scale relevant to commercial concentrating solar power (CSP) projects, thereby accelerating the commercial deployment of this new power generation technology. The project involved eight partnering organizations: NREL, Sandia National Laboratories, Echogen Power Systems, Abengoa Solar, University of Wisconsin at Madison, Electric Power Research Institute, Barber-Nichols, and the CSP Program of the U.S. Department of Energy. The multi-year project planned to design, fabricate, and validate an s-CO2 power turbine of nominally 10 MWe that is capable of operation at up to 700°C and operates in a dry-cooled test loop. The project plan consisted of three phases: (1) system design and modeling, (2) fabrication, and (3) testing. The major accomplishments of Phase 1 included: Design of a multistage, axial-flow, s-CO2 power turbine; Design modifications to an existing turbocompressor to provide s-CO2 flow for the test system; Updated equipment and installation costs for the turbomachinery and associated support infrastructure; Development of simulation tools for the test loop itself and for more efficient cycle designs that are of greater commercial interest; Simulation of s-CO2 power cycle …
Date:
January 29, 2014
Creator:
Turchi, Craig
Object Type:
Report
System:
The UNT Digital Library
A-11 seven cluster model: Phase V, flow induced vibration tests
This report summarizes the results of the fifth of a series of tests completed in the A-11 test program.
Date:
September 29, 1964
Creator:
Cherish, P. & Leff, G.J.
Object Type:
Report
System:
The UNT Digital Library
20-MW Magnicon for ILC
The 1.3 GHz RF power to drive ILC is now planned to be supplied by 600-1200, 10-MW peak power multi-beam klystrons. In this project, a conceptual design for 1.3 GHz magnicons with 20 MW peak power was developed as an alternative to the klystrons, with the possibility of cutting in half the numbers of high-power tubes and associated components. Design of a conventional magnicon is described, using TM110 modes in all cavities, as well as design of a modified magnicon with a TE111 mode output cavity. The latter has the advantage of much lower surface fields than the TM110 mode, with no loss of output power or electronic efficiency.
Date:
November 29, 2006
Creator:
Hirshfield, Jay L.
Object Type:
Report
System:
The UNT Digital Library
21-PWR Waste Package Side and End Impacts
The objective of this calculation is to determine the structural response of a 21-Pressurized Water Reactor (PWR) spent nuclear fuel waste package impacting an unyielding surface. A range of initial velocities and initial angles between the waste package and the unyielding surface is studied. The scope of this calculation is limited to estimating the area of the outer shell (OS) where the residual stress exceeds a given limit (hereafter ''damaged area''). The stress limit is defined as a fraction of the yield strength of the OS material, Alloy 22 (SB-575 N06022), at the appropriate temperature. The design of the 21-PWR waste package used in this calculation is that defined in Reference 8. However, a value of 4 mm was used for the gap between the inner shell and the OS, and the thickness of the OS was reduced by 2 mm. The sketch in Attachment I provides additional information not included in Reference 8. All obtained results are valid for this design only. This calculation is associated with the waste package design and was performed by the Specialty Analyses and Waste Package Design Section. The waste package (i.e. uncanistered spent nuclear fuel disposal container) is classified as Quality Level 1.
Date:
August 29, 2005
Creator:
Schmitt, T.
Object Type:
Report
System:
The UNT Digital Library
100 Areas technical activities report -- Engineering, February, 1950
This report covers work done by the Physical Chemistry Group and the Pile Engineering Groups. Subjects covered are as follows: metal exposure details; slug corrosion details; pile control -- thimble removal study; Van Stone flange corrosion details; process tube corrosion details; carbon dioxide experiment; graphite sampling; special pile measurements; routine pile measurements; 105 technical laboratories; P-10; boiling studies; pile annealing studies; gas tube experiment; thermal conductivity and electrical resistivity; x-ray diffraction studies; and stored energy.
Date:
March 29, 1950
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
100 Areas technical activities report -- Engineering, July, 1947
This monthly report covers activities for the production reactors. The 100 Area activities include: corrosion and blistering studies of slugs and flanges; study of the process tube leak at 105-D; graphite expansion studies which include galling of process tubes and stresses in biological shields; and irradiation studies.
Date:
August 29, 1947
Creator:
Woods, W. K.
Object Type:
Report
System:
The UNT Digital Library
100-F unit purge May 20, 1945
None
Date:
May 29, 1945
Creator:
Dahlen, P. A.
Object Type:
Report
System:
The UNT Digital Library
100-KEW coolant backup adequacy
None
Date:
April 29, 1964
Creator:
Heacock, H. W.
Object Type:
Report
System:
The UNT Digital Library
AZ-101 Mixer Pump Demonstration Data Acquisition System and Gamma Cart Data Acquisition Control System Software Configuration Management Plan
This Software Configuration Management Plan (SCMP) provides the instructions for change control of the AZ1101 Mixer Pump Demonstration Data Acquisition System (DAS) and the Sludge Mobilization Cart (Gamma Cart) Data Acquisition and Control System (DACS).
Date:
December 29, 1999
Creator:
White, D. A.
Object Type:
Report
System:
The UNT Digital Library
I-129 in SRP high-level waste and saltstone
Long-lived isotopes in nuclear waste can have the greatest impact on man and the environment because of the integrated dose over a long time period. Many long-lived radioactive isotopes are present in the waste at Savannah River Plant. Actinide elements make up a significant portion of these isotopes. But when the waste is incorporated into a glass waste form, the actinides are converted to chemically stable oxide species that are released at extremely low and controlled rates, even after the waste form has degraded. Because of their different chemistry, radioactive isotopes of carbon, technetium, and iodine could be released at a significantly higher rate. To establish the potential hazard from these isotopes, their concentration in waste forms for final disposal must be known. The concentrations of C-14 and T{sub c}-99 in SRP waste were previously estimated. Additional analytical data has now been obtained for I-129 in H-Area soluble waste to estimate its concentration in SRP waste. Because of the nature of processes at SRP, most of the I-129 in the waste is in the H-Area waste tanks.
Date:
February 29, 1984
Creator:
Fowler, J. R. & Cook, J. R.
Object Type:
Report
System:
The UNT Digital Library
200 Area weekly report
None
Date:
December 29, 1955
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
207-A retention basins system design description
The 242-A Evaporator is a waste treatment facility designed to reduce liquid waste volumes currently stored in the Hanford Area double shell Waste Storage Tanks. The evaporator uses evaporative concentration to achieve this volume reduction, returning the concentrated slurry to the double-shell tanks for storage. The process effluent is transferred to various retention/treatment facilities for eventual release to the environment. The process utilizes an evaporator vessel and various supporting systems for heating, evaporating, and condensing low-heat-generating liquid waste produced it the Hanford Site. The process reduces the total volume of the liquid waste requiring storage in a double shell tank, making it more manageable for current storage as well as for future treatment and disposal. The main components of the 242-A Evaporator are the Reboiler, Vapor-Liquid Separator, Recirculation Pump and Pump Loop, Slurry System, Condenser System, Steam Jet Vacuum System, Condensate Collection Tank, and Ion Exchange System.
Date:
September 29, 1994
Creator:
Wahlquist, R. A.
Object Type:
Report
System:
The UNT Digital Library
222-S laboratory complex hazards assessment
The US Department of Energy (DOE) Order 5500.3A, Emergency Planning and Preparedness for Operational Emergencies, requires that a facility specific hazards assessment be performed to support Emergency Planning activities. The Hazard Assessment establishes the technical basis for the Emergency Action Levels (EALs) and the Emergency Planning Zone (EPZ). Emergency Planning activities are provided under contract to DOE through the Westinghouse Hanford Company (WHC). This document represents the facility specific hazards assessment for the Hanford Site 222-S Laboratories. The primary mission of 222-S is to provide analytic chemistry support to the Waste Management, Chemical Processing, and Environmental programs at the Hanford Site.
Date:
August 29, 1994
Creator:
Broz, R. E.
Object Type:
Report
System:
The UNT Digital Library
241-Z-361 Sludge Characterization Sampling and Analysis Plan
This sampling and analysis plan (SAP) identifies the type, quantity, and quality of data needed to support characterization of the sludge that remains in Tank 241-2-361. The procedures described in this SAP are based on the results of the 241-2-361 Sludge Characterization Data Quality Objectives (DQO) (BWHC 1999) process for the tank. The primary objectives of this project are to evaluate the contents of Tank 241-2-361 in order to resolve safety and safeguards issues and to assess alternatives for sludge removal and disposal.
Date:
July 29, 1999
Creator:
BANNING, D.L.
Object Type:
Report
System:
The UNT Digital Library
242-A Evaporator/Liquid Effluent Retention Facility data quality objectives
The purpose of data quality objectives (DQO) is to determine the most cost effective methods of gathering the essential data necessary to make decisions to support successful operation of the facility. The essential data is defined by such information as sample amount, sample location, required analyses, and how sampling and analyses are performed. Successful operation is defined as meeting the campaign objectives while operating within established requirements. This DQO document addresses that portion of the system from 242-A Evaporator candidate feed tanks through discharge of process condensate to the Liquid Effluent Retention of Facility (LERF). Later revisions will incorporate and integrate the entire system, including the Effluent Treatment Facility (ETF).
Date:
September 29, 1994
Creator:
Von Bargen, B. H.
Object Type:
Report
System:
The UNT Digital Library
242-A Evaporator waste analysis plan. Revision 4
This waste analysis plan (WAP) provides the plan for obtaining information needed for proper waste handling and processing in the 242-A Evaporator located on the Hanford Site. Regulatory and safety issues are addressed by establishing boundary conditions for waste received and treated at the 242-A Evaporator. The boundary conditions are set by establishing limits for items such as potential exothermic reactions, waste compatibility, and control of vessel vent organic emissions. Boundary conditions are also set for operational considerations and to ensure waste acceptance at receiving facilities. The issues that are addressed in this plan include prevention of exotherms in the waste, waste compatibility, vessel vent emissions, and compatibility with the liner in the Liquid Effluent Retention Facility (LERF). The 242-A Evaporator feed stream is separated into two liquid streams: a concentrated slurry stream and a process condensate. A gaseous exhaust stream is also produced. The slurry contains the majority of the radionuclides and inorganic constituents. This stream is pumped back to the double shell tanks (DSTs) and stored for further treatment after being concentrated to target levels. The process condensate (PC) is primarily water that contains trace amounts of organic material and a greatly reduced concentration of radionuclides. The process …
Date:
September 29, 1994
Creator:
Basra, T. S. & Mulkey, C. H.
Object Type:
Report
System:
The UNT Digital Library
The 300 Area Integrated Field Research Challenge Quality Assurance Project Plan
Pacific Northwest National Laboratory and a group of expert collaborators are using the U.S. Department of Energy Hanford Site 300 Area uranium plume within the footprint of the 300-FF-5 groundwater operable unit as a site for an Integrated Field-Scale Subsurface Research Challenge (IFRC). The IFRC is entitled Multi-Scale Mass Transfer Processes Controlling Natural Attenuation and Engineered Remediation: An IFRC Focused on the Hanford Site 300 Area Uranium Plume Project. The theme is investigation of multi-scale mass transfer processes. A series of forefront science questions on mass transfer are posed for research that relate to the effect of spatial heterogeneities; the importance of scale; coupled interactions between biogeochemical, hydrologic, and mass transfer processes; and measurements/approaches needed to characterize and model a mass transfer-dominated system. This Quality Assurance Project Plan provides the quality assurance requirements and processes that will be followed by the 300 Area IFRC Project. This plan is designed to be used exclusively by project staff.
Date:
April 29, 2009
Creator:
Fix, N. J.
Object Type:
Report
System:
The UNT Digital Library