Serial/Series Title
Fiscal Year 2000
5
Application of Reservoir Characterization and Advanced Technology to Improve Recovery and Economics in a Lower Quality Shallow Shelf San Andres Reservoir Progress Report
2
Establishment of an Industry-Driven Consortium Focused on Improving the Production Performance of Domestic Stripper Wells Quarterly Report
2
Fiscal Year 2003
2
Fiscal Year 2008
2
Natural Gas Monthly
2
Science & Technology Review
2
Winter Fuels Report
2
A Real-Time Coal Content/Ore Grade (C2OG) Sensor, Technical Report
1
ARM Facilities Newsletter
1
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3-D Combinatorial Geometry in the MERCURY Monte Carlo Particle Transport Code
Lawrence Livermore National Laboratory is in the process of developing a new Monte Carlo Particle Transport code named MERCURY. This new code features a 3-D Combinatorial Geometry tracking algorithm. This paper details some of the characteristics of this Monte Carlo tracker
Date:
September 27, 2004
Creator:
Greenman, G
Object Type:
Article
System:
The UNT Digital Library
3-D Simulations of Plasma Wakefield Acceleration with Non-Idealized Plasmas and Beams
3-D Particle-in-cell OSIRIS simulations of the current E-162 Plasma Wakefield Accelerator Experiment are presented in which a number of non-ideal conditions are modeled simultaneously. These include tilts on the beam in both planes, asymmetric beam emittance, beam energy spread and plasma inhomogeneities both longitudinally and transverse to the beam axis. The relative importance of the non-ideal conditions is discussed and a worst case estimate of the effect of these on energy gain is obtained. The simulation output is then propagated through the downstream optics, drift spaces and apertures leading to the experimental diagnostics to provide insight into the differences between actual beam conditions and what is measured. The work represents a milestone in the level of detail of simulation comparisons to plasma experiments.
Date:
September 27, 2005
Creator:
Deng, S.; Katsouleas, T.; Lee, S.; Muggli, P.; Mori, W. B.; Hemker, R. et al.
Object Type:
Article
System:
The UNT Digital Library
3(omega) damage threshold evaluation of final optics components using Beamlet mule and off-line testing
A statistics-based model is being developed to predict the laser-damage-limited lifetime of UV optical components on the NIF laser. In order to provide data for the model, laser damage experiments were performed on the Beamlet laser system at LLNL. An early prototype NIF focus lens was exposed to twenty 35 1 nm pulses at an average fluence of 5 J/cm{sup 2}, 3ns. Using a high resolution optic inspection system a total of 353 damage sites was detected within the 1160 cm{sup 2} beam aperture. Through inspections of the lens before, after and, in some cases, during the campaign, pulse to pulse damage growth rates were measured for damage initiating both on the surface and at bulk inclusions. Growth rates as high as 79 {micro}m/pulse (surface diameter) were observed for damage initiating at pre-existing scratches in the surface. For most damage sites on the optic, both surface and bulk, the damage growth rate was approximately l0{micro}m/pulse. The lens was also used in Beamlet for a subsequent 1053 {micro}m/526 {micro}m campaign. The 352 {micro}m-initiated damage continued to grow during that campaign although at generally lower growth rate.
Date:
July 27, 1998
Creator:
Kozlowski, M. F.; Maricle, S.; Mouser, R.; Schwartz, S.; Wegner, P. & Weiland, T.
Object Type:
Article
System:
The UNT Digital Library
5-kWe Reactor Thermoelectric System: Summary
This report documents the systems and component requirements, design approaches, and performance and design characteristics for the 5-kwe system.
Date:
July 27, 1973
Creator:
Van Osdol, J. H.
Object Type:
Report
System:
The UNT Digital Library
S-11 and S-20 photocathode research activity. Rev. 1
The S-1 semi-transparent photocathode is the only one that can be used to study the 1.06 ..mu..m neodynium laser pulses of less than 10 ps duration. We first reviewed the recent results obtained at the Paris Observatory (research sponsored by the CEA), and then we tried to determine the role of the main constituents and their contributions in photoemission.
Date:
August 27, 1984
Creator:
Gex, F.; Huen, T. & Kalibjian, R.
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:
February 27, 2003
Creator:
Delabrosse, V.
Object Type:
Report
System:
The UNT Digital Library
40 YEARS OF EXPERIENCE WITH LIQUID-LIQUID EXTRACTION EQUIPMENT IN THE NUCLEAR INDUSTRY
Three types of liquid-liquid extraction equipment are used in industrial reprocessing plants. Each is described below, with a special focus on pulsed columns and centrifugal extractors, which have been the subject of an extensive R&D program by the French Atomic Energy Commission (CEA). Various models have been developed to simulate equipment behavior and flowsheets. The excellent results obtained during industrial operation of the UP3 and UP2-800 plants in La Hague have confirmed the validity of the choices made during the design phases and pave the way for future improvement of the reprocessing process, from a technical and a financial standpoint.
Date:
February 27, 2003
Creator:
Drain, F.; Vinoche, R. & Duhamet, J.
Object Type:
Article
System:
The UNT Digital Library
94-A13 Native American Initiative Short Course Management Plan
A training program conducted in Bartlesville by BDM-Oklahoma technical staff, which included geologists, geophysicists, exploration and drilling specialists, and environmental policy experts. The proposed training schedule offered four courses per year and included those coursed identified by the tribes in the survey. The training program was outlined for members of Native American Tribes whose lands have oil and gas resources. The proposed program contributed to meeting the goals of the U.S. Department of Energy's (DOE) Domestic Oil and Gas Initiative to help Native American tribes become more self-sufficient in developing and managing their resources through training in cost-effective, improved technologies for hydrocarbon production that will meet environmental regulations. The training program outlined was for adult tribal representatives who are responsible for managing tribal mineral holdings or setting policy, or who work in the oil and gas industry. The course content is in response to a survey that was developed by BDM-Oklahoma and sent in the Spring of 1995 to 26 tribal agencies identified through previous contact with DOE. Tribes were asked to indicate course content needs, levels, preferred time of year, and location. Six tribes responded with specific recommendations and needs. These tribes, were the Creek, Pueblo, Cherokee, St. Regis …
Date:
April 27, 1999
Creator:
Carroll, Herbert B.; Johnson, William I. & Kokesh, Judith H.
Object Type:
Report
System:
The UNT Digital Library
A 100-kV, 2-kA, 2.5-{micro}S Pulser for Developing and Calibrating Long-Pulse Diagnostics
The development of voltage and current probes for measuring an electron beam's current and position associated with several microsecond-long pulses from advanced Linear Induction Accelerators requires a precision pulser that can deliver both high voltages and high currents to a diagnostics Test Line. Seven-stage, type-E PFNs have been utilized in both a transformer and 4-stage Marx (plus/minus) configuration. The resulting 50-ohm pulser delivers to the Test Line a repeatable 100 kV, ca. 2 {micro}s flat-top ({+-} 1%), 2.5 {micro}s FWHM pulse with a rise time of 175 ns and 500 ns for the transformer and Marx options, respectively. Methods of reducing the rise time for both options are discussed and modeled. The coaxial Test Line is insulated at up to two atmospheres with SF{sub 6} and includes two transition regions to hold and test different diameter beam current and position monitors (BPMs). The center conductor incorporates both translation and tip/tilt with an accuracy of 100 {micro}m. Finally, the line is terminated in a matched radial resistor that provides a planar region at fields up to 40 kV/cm for the testing of voltage probes. Both the transformer and Marx options are modeled and compared to experimental results.
Date:
June 27, 1999
Creator:
Carlson, R.L.
Object Type:
Article
System:
The UNT Digital Library
S-102 Transfer Pump Restriction Modeling Results
It was determined that a radioactive waste leak in the Hanford S Farm in the vicinity of the S-102 retrieval pump discharge occurred because of over-pressurization and failure of the S-102 dilution water supply hose while operating the retrieval pump in reverse with an obstructed suction cavity and an unobstructed flow path to the dilution water supply hose. This report describes efforts to identify plausible scenarios for the waste leak to occur.
Date:
March 27, 2008
Creator:
Wells, Beric E.; Johnson, Kenneth I.; Rector, David R. & Trent, Donald S.
Object Type:
Report
System:
The UNT Digital Library
105-KE Basin Pilot Run design plan
None
Date:
September 27, 1994
Creator:
Sherrell, D. L.
Object Type:
Report
System:
The UNT Digital Library
183 KE Potable water system analysis plan
Sampling analysis plans (SAP) are a recognized manner of providing applicable requirements for conducting media sampling and analysis in a manner consistent with prescirbed objectives. This SAP has been prepared to satisfy the data quality objectives listed in this SAP with respect to the operation of the 183 KE potable water for K Area.
Date:
September 27, 1995
Creator:
Hunacek, G.S.
Object Type:
Report
System:
The UNT Digital Library
200 Area waste storage study
As a part of the five year budget study requested by HOO-AEC, a study of separations waste storage requirements for this period was made. This study took into consideration the variant estimates of amount of irradiated uranium to be processed, and the goals in the waste reduction research and development program. The conclusions of this study were at variance, to some extent, with prior studies. Interest has been expressed in publication of this study to permit independent assessment of its bases and assumptions.
Date:
March 27, 1956
Creator:
Hanthorn, H.E.
Object Type:
Report
System:
The UNT Digital Library
209-E Building -- Response to ventilation failure evaluation
This document provides an evaluation and recommendations for radiological workplace air monitoring and response to ventilation failure for the Critical Mass Laboratory, 209-E Building. The Critical Mass Laboratory, part of the 209-E Building, was designed to provide a heavily shielded room where plutonium and uranium liquid solutions could be brought into various critical configurations under readily controlled and monitored conditions. The facility is contained within a one-story L-shaped concrete block and reinforced concrete building. One wing houses offices, a control room, shops, and a common area while the other wing includes an equipment room, the change room, work areas, and the two-story Critical Assembly Room (CAR). Three of the rooms contain radiologically contaminated equipment and materials.
Date:
July 27, 1998
Creator:
Foust, D.J.
Object Type:
Report
System:
The UNT Digital Library
241-AZ-101 Mixer Pump Demonstration Test Gamma Cart Acceptance Test Procedure and Quality Test Plan (ATP and QTP)
Shop test of the sludge mobilization cart system to be used in the AZ-101 Mixer Pump Demonstration Test Tests hardware and software. This procedure involves testing the Instrumentation involved with the Gamma Cart System, local and remote, including depth indicators, speed controls, interface to data acquisition software and the raising and lowering functions. This Procedure will be performed twice, once for each Gamma Cart System. This procedure does not test the accuracy of the data acquisition software.
Date:
January 27, 2000
Creator:
White, D. A.
Object Type:
Report
System:
The UNT Digital Library
300-Area accident analysis for Emergency Planning Zones
The Department of Energy has requested SRL assistance in developing offsite Emergency Planning Zones (EPZs) for the Savannah River Plant, based on projected dose consequences of atmospheric releases of radioactivity from potential credible accidents in the SRP operating areas. This memorandum presents the assessment of the offsite doses via the plume exposure pathway from the 300-Area potential accidents. 8 refs., 3 tabs.
Date:
June 27, 1983
Creator:
Pillinger, W.L.
Object Type:
Report
System:
The UNT Digital Library
300 Area D4 Project Fiscal Year 2009 Building Completion Report
This report summarizes the deactivation, decontamination, decommissioning, and demolition activities of seven facilities in the 300 Area of the Hanford Site in fiscal year 2009. The D4 of these facilities included characterization; engineering; removal of hazardous and radiologically contaminated materials; equipment removal; utility disconnection; deactivation, decontamination, demolition of the structure; and stabilization or removal of slabs and foundations. This report also summarizes the nine below-grade slabs/foundations removed in FY09 of buildings demolished in previous fiscal years.
Date:
January 27, 2010
Creator:
Skwarek, B. J.
Object Type:
Report
System:
The UNT Digital Library
300 Area D4 Project Fiscal Year 2010 Building Completion Report
This report summarizes the deactiviation, decontamination, decommissioning, and demolition activities of facilities in the 300 Area of the Hanford Site in fiscal year 2010.
Date:
January 27, 2011
Creator:
Skwarek, B. J.
Object Type:
Report
System:
The UNT Digital Library
300 Area liquid effluent facilities computer software configuration management plan
This is the 300-area liquid effluent facilities computer software configuration management plan.
Date:
January 27, 1997
Creator:
Schermerhorn, D.S.
Object Type:
Report
System:
The UNT Digital Library
300 kWt core conceptual model thermal/hydraulic characteristics
This is a Report of a study that has been made Nak cooled reactor containing 199 ZrH-UO2 fuel elements to determine thermal-hydraulic characteristics of the core bundle, It contains nominal operating power of the reactor is 300kwt with the Nak existing from the core at 1200 F.
Date:
July 27, 1971
Creator:
Moody, E.
Object Type:
Report
System:
The UNT Digital Library
324 Facility B-cell quality process plan
Quality Process Plan for the Restart of Cell Hot-Work. Addition of Table 4.
Date:
October 27, 1998
Creator:
Carlson, J. L.
Object Type:
Report
System:
The UNT Digital Library
324 Facility B-cell quality process plan
Quality Process Plan for the Restart of Cell Hot-Work. Addition of Table 5a.
Date:
October 27, 1998
Creator:
RIDDELLE, J.G.
Object Type:
Report
System:
The UNT Digital Library
327 Building hazard baseline document
Applied technology legend removed per DOE/HQ on April 3, 2002
Date:
September 27, 1999
Creator:
STEFFEN, J.M.
Object Type:
Report
System:
The UNT Digital Library
340 and 310 drawing field verification
The purpose of the drawing field verification work plan is to provide reliable drawings for the 310 Treated Effluent Disposal Facility (TEDF) and 340 Waste Handling Facility (340 Facility). The initial scope of this work plan is to provide field verified and updated versions of all the 340 Facility essential drawings. This plan can also be used for field verification of any other drawings that the facility management directs to be so updated. Any drawings revised by this work plan will be issued in an AutoCAD format.
Date:
September 27, 1996
Creator:
Langdon, J.
Object Type:
Report
System:
The UNT Digital Library