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  Partner: UNT Libraries Government Documents Department
 Decade: 1990-1999
 Year: 1996
1.8.3 Site system engineering FY 1997 program plan
The FY 1997 Multi-Year Work Plan (MYWP) technical baseline describes the functions to be accomplished and the technical standards that govern the work. The following information is provided in this FY 1997 MYWP: technical baseline, work breakdown structure, schedule baseline, cost baseline, and execution year. digital.library.unt.edu/ark:/67531/metadc683550/
1: Mass asymmetric fission barriers for {sup 98}Mo; 2: Synthesis and characterization of actinide-specific chelating agents
Excitation functions have been measured for complex fragment emission from the compound nucleus {sup 98}Mo, produced by the reaction of {sup 86}Kr with {sup 12}C. Mass asymmetric fission barriers have been obtained by fitting the excitation functions with a transition state formalism. The extracted barriers are {approximately} 5.7 MeV higher, on average, than the calculations of the Rotating Finite Range Model (RFRM). These data clearly show an isospin dependence of the conditional barriers when compared with the extracted barriers from {sup 90}Mo and {sup 94}Mo. Eleven different liquid/liquid extractants were synthesized based upon the chelating moieties 3,2-HOPO and 3,4-HOPO; additionally, two liquid/liquid extractants based upon the 1,2-HOPO chelating moiety were obtained for extraction studies. The Pu(IV) extractions, quite surprisingly, yielded results that were very different from the Fe(III) extractions. The first trend remained the same: the 1,2-HOPOs were the best extractants, followed closely by the 3,2-HOPOs, followed by the 3,4-HOPOs; but in these Pu(IV) extractions the 3,4-HOPOs performed much better than in the Fe(III) extractions. 129 refs. digital.library.unt.edu/ark:/67531/metadc685938/
2-1/2-D electromagnetic modeling of nodular defects in high-power multilayer optical coatings
Advances in the design and production of high damage threshold optical coatings for use in mirrors and polarizers have been driven by the design requirements of high-power laser systems such as the proposed 1.8-MJ National Ignition Facility (NIF) and the prototype 12- kJ Beamlet laser system. The present design of the NIF will include 192 polarizers and more than 1100 mirrors. Currently, the material system of choice for high-power multilayer optical coatings with high damage threshold applications near 1.06 {mu}m are e-beam deposited HfO{sub 2}/Si0{sub 2} coatings. However, the optical performance and laser damage thresholds of these coatings are limited by micron-scale defects and insufficient control over layer thickness. In this report, we will discuss the results of our 2-1/2-D finite-element time- domain (FDTD) EM modeling effort for rotationally-symmetric nodular defects in multilayer dielectric HR coatings. We have added a new diagnostic to the 2-1/2-D FDTD EM code, AMOS, that enables us to calculate the peak steady-state electric fields throughout a 2-D planar region containing a 2-D r-z cross-section of the axisymmetric nodular defect and surrounding multilayer dielectric stack. We have also generated a series of design curves to identify the range of loss tangents for Si0{sub 2} and HfO{sub 2} consistent with the experimentally determined power loss of the HR coatings. In addition, we have developed several methods to provide coupling between the EM results and the thermal-mechanical simulation effort. digital.library.unt.edu/ark:/67531/metadc684881/
(02.2) Scoping experiments; (02.3) long-term corrosion testing and properties evaluation of candidate waste package basket material
The work described in this activity plan addresses Information Need 2.7.3 of the Yucca Mountain Site Characterization Plan (l), which reads Determination that the design criteria in lOCFR60.130 through 60.133 and any appropriate additional design objectives pertaining to criticality control have been met. This work falls under section WBS 1.2.2.5 2 (Basket Materials) of WBS 1.2.2.5 (Waste Package Materials) in the Work Breakdown Structure of the Yucca Mountain Site Characterization Project. digital.library.unt.edu/ark:/67531/metadc666681/
The 2.3 {angstrom} crystal structure of cholera toxin B subunit pentamer: Choleragenoid
Cholera toxin, a heterohexameric AB{sub 5} enterotoxin released by Vibrio cholera, induces a profuse secretory diarrhea in susceptible hosts. Choleragenoid, the B subunit pentamer of cholera toxin, directs the enzymatic A subunit to its target by binding to GM{sub 1} gangliosides exposed on the luminal surface of intestinal epithelial cells. We have solved the crystal structure of choleragenoid at 2.3 {Angstrom} resolution by combining single isomorphous replacement with non-crystallographic symmetry averaging. The structure of the B subunits, and their pentameric arrangement, closely resembles that reported for the intact holotoxin (choleragen), the heat-labile enterotoxin from E. coli, and for a choleragenoid-GM{sub 1} pentasaccharide complex. In the absence of the A subunit the central cavity of the B pentamer is a highly solvated channel. The binding of the A subunit or the receptor pentasaccharide to choleragenoid has only a modest effect on the local stereochemistry and does not perceptibly alter the subunit interface. digital.library.unt.edu/ark:/67531/metadc671655/
2 x 2 TeV mu(superscript +) mu (superscript) collider
The scenarios for high-luminosity 2 x 2 TeV and 250 x 250 GeV {mu}{sup +}{mu}{sup -} colliders are presented. Having a high physics potential, such a machine has specific physics and technical advantages and disadvantages when compared with an e{sup +}e{sup -} collider. Parameters for the candidate designs and the basic components - proton source, pion production and decay channel, cooling, acceleration and collider storage ring - are considered. Attention is paid to the areas mostly affecting the collider performance: targetry, energy spread, superconducting magnet survival, detector backgrounds, polarization, environmental issues. 13 refs., 9 figs., 4 tabs. digital.library.unt.edu/ark:/67531/metadc687319/
3-D electromagnetic modeling of wakefields in accelerator components
We discuss the use of 3-D finite-difference time-domain (FDTD) electromagnetic codes for modeling accelerator components. Computational modeling of cylindrically symmetric structures such as induction accelerator cells has been very successful in predicting the wake potential and wake impedances of these structures, but full 3-D modeling of complex structures has been limited due to substantial computer resources required for a full 3-D model. New massively parallel 3-D time domain electromagnetic codes now under development using conforming unstructured meshes allow a substantial increase in the geometric fidelity of the structures being modeled. Development of these new codes are discussed in context of applicability to accelerator problems. Various 3-D structures are tested with an existing cubical cell FDTD code and wake impedances compared with simple analytic models for the structures; results will be used as benchmarks for testing the new time time domain codes. Structures under consideration include a stripline beam position monitor as well as circular and elliptical apertures in circular waveguides. Excellent agreement for monopole and dipole impedances with models were found for these structures below the cutoff frequency of the beam line. digital.library.unt.edu/ark:/67531/metadc685010/
3-dimensional wells and tunnels for finite element grids
Modeling fluid, vapor, and air injection and extraction from wells poses a number of problems. The length scale of well bores is centimeters, the region of high pressure gradient may be tens of meters and the reservoir may be tens of kilometers. Furthermore, accurate representation of the path of a deviated well can be difficult. Incorporating the physics of injection and extraction can be made easier and more accurate with automated grid generation tools that incorporate wells as part of a background mesh that represents the reservoir. GEOMESH is a modeling tool developed for automating finite element grid generation. This tool maintains the geometric integrity of the geologic framework and produces optimal (Delaunay) tetrahedral grids. GEOMESH creates a 3D well as hexagonal segments formed along the path of the well. This well structure is tetrahedralized into a Delaunay mesh and then embedded into a background mesh. The well structure can be radially or vertically refined and each well layer is assigned a material property or can take on the material properties of the surrounding stratigraphy. The resulting embedded well can then be used by unstructured finite element models for gas and fluid flow in the vicinity of wells or tunnels. This 3D well representation allows the study of the free- surface of the well and surrounding stratigraphy. It reduces possible grid orientation effects, and allows better correlation between well sample data and the geologic model. The well grids also allow improved visualization for well and tunnel model analysis. 3D observation of the grids helps qualitative interpretation and can reveal features not apparent in fewer dimensions. digital.library.unt.edu/ark:/67531/metadc668722/
5-Volt and 4.6 V plateaus in LiMn{sub 2}O{sub 4} thin films
Additional plateaus with median voltages of {similar_to}4.6 V, and {similar_to}5 V have been observed on charging thin film lithium batteries with crystalline LiMn{sub 2}O{sub 4} cathodes to 5.3 V. Total charge extracted from the 4 V and the two additional plateaus corresponded to about 1Li/Mn{sub 2}O{sub 4}, but the distribution of capacity among the three plateaus varied from film to film. It is speculated that the additional plateaus result from formation of mixed spinel structures in which a fraction of the 8a sites areoccupied by Mn{sup 2+} or Mn{sup 4+} ions and a fraction of the Li{sup +} ions occupy the 16d sites. After charging to 5.3 V, the 4.6 V plateau disappeared, and the capacity of the 4 V plateau increased at the expense of that of the 5 V plateau. The latter change is attributed to movement of Mn{sup 3+} or Mn{sup 5+} ions from 8a to 16d sites. digital.library.unt.edu/ark:/67531/metadc672866/
6 GeV synchrotron x-ray source: Conceptual design report. Supplement B - conceptual design of proposed beam lines for the 6 GeV light source
In this document, preliminary conceptual designs are presented for ten sample beamlines for the 6 GeV Light Source. These beamlines will accommodate investigations in solid-state physics, materials science, materials technology, chemical technology, and biological and medical sciences. In future, the designs will be altered to include new developments in x-ray optics and hardware technologies. The research areas addressed by the samples beamlines are as follows: Topography and Radiography/Tomography (section 2); Inelastic Scattering with Ultrahigh Energy Resolution (Section 3); Surface and Bulk Studies Using High Momentum Resolution (Section 4); Inelastic Scattering from Charge and Spin (Section 5); Advanced X-Ray Photoelectron Spectroscopy Studies (Section 6); Small Angle X-Ray Scattering Studies (Section 7); General Purpose Scattering for Materials Studies (Section 8); Multiple-Energy Anomalous-Dispersion Studies of Proteins (Section 9); Protein Crystallography (Section 10); Time- and Space-resolved X-Ray Spectroscopy (Section 11); Medical Diagnostic Facility (Section 12); and Transuranium Research Facility (Section 13). The computer systems to be used on the beamlines are also discussed in Section 14 of this document. digital.library.unt.edu/ark:/67531/metadc683429/
The 10,000-year debate
Probabilistic Risk Assessment (PRA) has developed into a respected tool within the reactor community. Now, this PRA technique is being applied to a new arena, the distant future of the nuclear waste repository. Problems are already testing the credibility of PRA. digital.library.unt.edu/ark:/67531/metadc686881/
A 20 ampere shunt regulator for controlling individual magnets in a seriesed string
At the CEBAF accelerator, groups of dipole magnets are often connected together in series and powered from a single large constant-current regulated D-C supply, referred to locally as a {open_quotes}box{close_quotes} supply. Besides the economy realized, this configuration promotes correct field tracking of all elements of a beam transport channel. However, it is often desirable to vary the current in one element of a string independently of the others, particularly at the entrance and exits of transport channels. A 20 ampere programmable current shunt is described. Installed in parallel with the desired magnet, it permits shunting (bypassing) up to 5% of the string current around that magnet. The shunt regulator consists of a bank of MOSFET power transistors operated in linear mode. Regulation of current through the passbank is obtained by feedback from a manganin shunt maintained at a constant temperature for stability. The module is designed for remote operation and provides readbacks of various parameters useful for maintenance. To achieve complete electrical isolation, an onboard microprocessor provides remote communications via an opto-isolated serial data link. Constructional details and initial operating experience with the plug-in shunt are described. digital.library.unt.edu/ark:/67531/metadc686377/
45-day safety screening results and final report for Tank 241-BX-106, auger samples 95-AUG-049 and 95-AUG-050
Two Auger Samples from tank 241-BX-106 were received at the 222-S Laboratory and underwent safety screening analyses - differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), total alpha analysis, and bulk density measurements - in accordance with the sampling and analysis plan. digital.library.unt.edu/ark:/67531/metadc685488/
45-Day safety screening results for tank 241-U-102, push mode cores 143 and 144
This document is the 45-day report deliverable for tank 241-U-102 push mode core segments collected between April 16, 1996 and May 6, 1996 and received by the 222-S Laboratory between April 17, 1996 and May 8, 1996. The segments were subsampled and analyzed in accordance, with the Tank 241-U-102 Push Mode Core Sampling and analysis Plan (TSAP) (Hu, 1996) and the Safety Screening Data Quality Objective (DQO) (Dukelow, et al., 1995). The analytical results are included in Table 1. Attachment I is a cross reference to relate the tank farm identification numbers to the 222-S Laboratory LabCore sample numbers. The subsamples generated in the laboratory for analysis are identified in these diagrams with their sources shown. The diagram identifying the hydrostatic head fluid (HHF) blank is also included, Primary safety screening results and the raw data from Differential Scanning Calorimetry (DSC) and thermogravimetric analysis (TGA) analyses are included in this report. Two of the samples submitted for DSC analysis exceeded notification limits as stated in the Safety Screening DQO (Dukelow, et al., 1995). Cyanide analysis was requested on these samples and a Reactive System Screening Tool analysis was requested for the sample exhibiting the highest exothenn in accordance with the TSAP (Hu, 1996). The results for these analyses will be reported in a revision to this document. digital.library.unt.edu/ark:/67531/metadc685242/
60-day waste compatibility safety issue and final results for 244-TX DCRT, grab samples TX-95-1, TX-95-2, and TX-95-3
Three grab samples (TX-95-1, TX-95-2, and TX-95-3) were taken from tank 241- TX-244 riser 8 on November 7, 1995 and received by the 222-S Laboratory on that same day. Samples TX-95-1 and TX-95-2 were designated as supernate liquids, and sample TX-95-3 was designated as a supernate/sludge. These samples were analyzed to support the waste compatibility safety program. Accuracy and precision criteria were met for all analyses. No notifications were required based on sample results. This document provides the analysis to support the waste compatibility safety program. digital.library.unt.edu/ark:/67531/metadc675649/
94-1 Research and Development Project lead laboratory support: Fiscal year 1997. Progress report
On May 26, 1994, the Defense Nuclear Facilities Safety Board (DNFSB) issued Recommendation 94-1, which expressed the board`s concern about nuclear materials left in the manufacturing pipeline after the US halted its nuclear weapons production activities. The DNFSB emphasized the need for remediation of these materials. As part of Recommendation 94-1, the DNFSB defined research objectives as follows: that a research program be established to fill any gaps in the information base needed for choosing among the alternate processes to be used in safe conversion of various types of fissile materials to optimal forms for safe interim storage and the longer-term disposition. To achieve this objective a research and technology development program with two elements is needed: a technology-specific program that is focused on treating and storing materials safety, with concomitant development of storage criteria and surveillance requirements, centered around 3- and 8-year targets; and a core technology program to augment the knowledge base about general chemical and physical processing and storage behavior and to assure safe interim material storage until disposition policies are formulated. The paper reports the progress on the following: materials identification and surveillance; stabilization process development; surveillance and monitoring; core technologies; and project management. digital.library.unt.edu/ark:/67531/metadc696896/
94-1 Research and Development Project Lead Laboratory Support. Status report, April 1, 1996--June 30, 1996
This document reports status and technical progress for Los Alamos 94-1 Research and Development projects concerned with the management of plutonium and plutonium contaminated materials during the third quarter of FY96. digital.library.unt.edu/ark:/67531/metadc679867/
94-1 Research and development project lead laboratory support. Status report, January 1--March 31, 1996
This document reports status and technical progress for Los Alamos National Laboratories 94-1 Research and Development projects. An introduction to the project structure and an executive summary are included. Projects described include Electrolytic Decontamination, Combustibles, Detox, Sand, Slag, and Crucible, Surveillance, and Core Technology. digital.library.unt.edu/ark:/67531/metadc689086/
94-1 Research and Development Project Lead laboratory support. Status report, October 1--December 31, 1995
This is a quarterly progress report of the 94-1 Research and Development Lead Laboratory Support Technical Program Plan for the first quarter of FY 1996. The report provides details concerning descriptions, DOE-complex-wide material stabilization technology needs, scientific background and approach, progress, benefits to the DOE complex, and collaborations for selected subprojects. An executive summary and report on end-of-quarter spending is included. digital.library.unt.edu/ark:/67531/metadc668090/
100 Femtosecond laser absorption in solid density targets
Experimental short pulse lasers are rapidly approaching energy levels where target irradiances exceeding 10{sup 20} W/CM{sup 2} are routinely achievable. These high intensity levels will open up a new class of solid target interaction physics where relativistic effects must be included and non-traditional absorption mechanisms become significant. However much remains to be understood of the absorption physics at lower intensities where classical absorption is dominated by collisional and resonance absorption. If attention is paid to producing clean laser pulses that do not significantly pre-pulse interact with the target, it is possible to produce plasmas of sufficiently short scale length that near-solid density interactions are observable at intensities exceeding 10{sup 18} W/CM{sup 2} for 100 fs laser irradiation. We report here extensions to our previous efforts at normal incidence that expand our observations to non-normal angles including the effect of polarization for several target materials. Between 10{sup 13} W/CM{sup 2} and 10{sup 14} W/CM{sup 2} we observe that the target absorption retains a signature of the intra-band atomic transitions. At higher intensities a more material independent ion-electron collisional absorption and short scale length resonance absorption dominate. P - polarized absorption in short scale length plasmas has been observed to exceed 60 percent. digital.library.unt.edu/ark:/67531/metadc692443/
100-FR-3 groundwater/soil gas supplemental limited field investigation report
In 1993, a Limited Field Investigation (LFI) was conducted for the 100-FR-3 Operable Unit which identified trichloroethylene (TCE) as a contaminant of potential concern (COPC) (DOE-RL 1994). In groundwater samples collected for the LFI, TCE was detected in well 199-177-1 at a concentration exceeding the U.S. Environmental Protection Agency (EPA) maximum contaminant level (5 {mu}g/L) and Washington State groundwater criteria (3 {mu}g/L). With the concurrence of the EPA and the Washington State Department of Ecology (Ecology), a supplemental LFI was conducted to determine the extent and potential source of TCE groundwater contamination associated with the 100-FR-3 Operable Unit. This report summarizes the activities and results of the groundwater/soil gas supplemental LFI for the 100-FR-3 Operable Unit. The primary objective of this investigation was to assess the lateral distribution of TCE in shallow (3 to 5 ft below the water table) groundwater associated with the 100-FR-3 Operable Unit. The second objective was to assess soil gas (3 to 5 concentrations in the study area in an attempt to identify potential sources of TCE and develop a correlation between soil gas and groundwater concentrations). Finally, the third objective of the investigation was to refine the site conceptual model. digital.library.unt.edu/ark:/67531/metadc667271/
A 100 MVA generator utilizing high temperature superconducting windings -- design assessment & component development. Final report
The operation of a high temperature superconducting generator rotor using closed-cycle refrigeration to indirectly cool the field windings was considered to be the best choice for an HTS application. The SPI program proposed to achieve the following goals: In Task 1 a 100 MVA generator with a HTS rotor field winding would be designed. An energy and economic benefits analysis was to be a key part of the program. In addition, the generator/grid interactions were to be modeled. Concurrently, Task 2 was to include further development of Bi-2223 silver-clad tape as well as an alternate Tl-1223 conductor, manufacture of 3,000 meters of tape, and development and fabrication of a prototype field coil. Details of progress have been reported in the quarterly status reports and summarized in the final reports on the tasks. Therefore this report will give a review of the original goals of each task and summary of results for each. digital.library.unt.edu/ark:/67531/metadc693965/
105-DR Large Sodium Fire Facility closure activities evaluation report
This report evaluates the closure activities at the 105-DR Large Sodium Fire Facility. The closure activities discussed include: the closure activities for the structures, equipment, soil, and gravel scrubber; decontamination methods; materials made available for recycling or reuse; and waste management. The evaluation compares these activities to the regulatory requirements and closure plan requirements. The report concludes that the areas identified in the closure plan can be clean closed. digital.library.unt.edu/ark:/67531/metadc688077/
105-DR Large sodium fire facility soil sampling data evaluation report
This report evaluates the soil sampling activities, soil sample analysis, and soil sample data associated with the closure activities at the 105-DR Large Sodium Fire Facility. The evaluation compares these activities to the regulatory requirements for meeting clean closure. The report concludes that there is no soil contamination from the waste treatment activities. digital.library.unt.edu/ark:/67531/metadc674679/
105 K East and 105 K West fuel transfer bay crane use strategy for spent nuclear fuel path-forward
The purpose of this document is to outline the K Basins 30 ton crane qualification strategy for use in the Spent Nuclear Fuel Project fuel relocation campaign. digital.library.unt.edu/ark:/67531/metadc687833/
105 K east ion exchange and cartridge filter restart instrumentation acceptance test report
Acceptance Test Report following the completion of ATP-012 for the 105KE CP-A and CP-A Computer and PLC Panels. The test was conducted from 11/13/95 to 12/11/95. Three test discrepancies were generated during the ATP and all were dispositioned and closed. All sections were completed except Section 5.9 which was deleted per ECN 190556. digital.library.unt.edu/ark:/67531/metadc687199/
105-K east sandfilter backwash line sample analysis report. Second campaign
This project seeks to produce uranium (U) and plutonium (Pu) analyses of samples taken from the KE basin filter backwash line each time the sand filter is backwashed. K Basin operations will use the analytical results to determine additions of fissile materials to the backwash sludge pit and thereby maintain a running inventory of fissile elements in the pit. K Basin Operations must not exceed a certain total inventory in order to be within a criticality specification. The second campaign of this project consisted of three samples, numbered by the customer 208KEB, 209KEB, and 210KEB. digital.library.unt.edu/ark:/67531/metadc679910/
105-K east sandfilter backwash line sample analysis report: Third campaign
This project seeks to produce uranium (U) and plutonium (Pu) analyses of samples taken from the KE basin filter backwash line each time the sand filter is backwashed. K Basin operations will use the analytical results to determine additions of fissile materials to the backwash sludge pit and thereby maintain a running inventory of fissile elements in the pit. K Basin operations must not exceed a certain total inventory in order to be within a criticality specification. The third campaign of this project consisted of three samples, numbered by the customer 245KEB, 246KEB, and 247KEB. A revised letter of instruction controlled their processing. digital.library.unt.edu/ark:/67531/metadc684251/
150-MW S-band klystron program at the Stanford Linear Accelerator Center
Two S-Band klystrons operating at 150 MW have been designed, fabricated and tested at the Stanford Linear Accelerator Center (SLAC) during the past two years for use in an experimental accelerator at Deutsches Elektronen-Synchrotron (DESY) in Hamburg, Germany. Both klystrons operate at the design power, 60 Hz repetition rate, 3 {micro}s pulsewidth, with an efficiency {gt} 40%, and agreement between the experimental results and simulations is excellent. The 535 kV, 700 A electron gun was tested by constructing a solenoidal focused beam stick which identified a source of oscillation, subsequently engineered out of the klystron guns. Design of the beam stick and the two klystrons is discussed, along with observation and suppression of spurious oscillations. Differences in design and the resulting performance of the Klystrons is emphasized. digital.library.unt.edu/ark:/67531/metadc694313/
200-BP-5 operable unit treatability test report
The 200-BP-5 Operable Unit was established in response to recommendations presented in the 200 East Groundwater Aggregate Area Management Study Report (AAMSR) (DOE-RL 1993a). Recognizing different approaches to remediation, the groundwater AAMSR recommended separating groundwater from source and vadose zone operable units and subdividing 200 East Area groundwater into two operable units. The division between the 200-BP-5 and 200-PO-1 Operable Units was based principally on source operable unit boundaries and distribution of groundwater plumes derived from either B Plant or Plutonium/Uranium Extraction (PUREX) Plant liquid waste disposal sites. digital.library.unt.edu/ark:/67531/metadc664341/
222-S Analytical services final results for Tank 241-U-101, grab samples 1U-96-1 through 1U-96-4
This document is the final, format IV, laboratory report for characterization of tank 241-U-101 (U-101) grab samples from risers 1 and 7. It transmits additional analytical data for specific gravity (Sp.G.), and all raw analytical data which were not provided in the 45-day report. The 45-day report is attached to this final report as Part II. Secondary analyses were not performed on any of the U-101 samples. This is because none of the primary analyte limits, which trigger the performance of secondary analyses, were exceeded. Grab samples were taken on May 29, 1996 and May 30, 1996 from risers 1 and 7, respectively, and were received at the 222-S Laboratory on the same days that they were collected. Analyses were performed in accordance with the Tank Sampling and Analysis Plan (TSAP) for this tank and the Safety Screening Data Quality Objective (DQO). The samples were analyzed for differential scanning calorimetry (DSC), thermogravimetric analysis (TGA), total alpha activity (AT), visual appearance, bulk density, and specific gravity. A sample data summary table, includes sample analytical data accompanied by quality control data (for example, duplicate, spike, blank and standard results and detection limits and counting efforts). The table includes data for DSC, TGA, AT, bulk density, volume percent solids and Sp.G. analyses. Data regarding the visual appearance of samples, volume percent solids and density of the solids are provided in tabular form of the 45-day report (attached as Part II). The table of the 45-day report also associates the original customer sample number with corresponding laboratory sample numbers. The TSAP specified notification limits for only DSC and total alpha. Notification limits were not exceeded for DSC or total alpha analyses for any of the samples, consequently immediate notifications were not necessary and were not made. digital.library.unt.edu/ark:/67531/metadc674164/
222-S Laboratory analytical report for tank 241-C-106, grab samples 6C-96-1 through 6C-96-16 {ampersand} 6C-96-17-FB
This document is the analytical report for grab samples 6C-96-1through 6C-96-16 and 6C-96-17-FB from tank 241-C-106. digital.library.unt.edu/ark:/67531/metadc623267/
225-B ion exchange piping design documentation
This document describes the interface between the planned permanent ion exchange piping system and the planned portable ion exchange system. This is part of the Waste Encapsulation and Storage Facility (WESF). In order to decouple this WESF from B-Plant and to improve recovery from a capsule leak, contaminated pool cell water will be recirculated through a portable ion exchange resin system. digital.library.unt.edu/ark:/67531/metadc677245/
241-SX sludge profile temperature for March 1 to December 29, 1972
Data sheets containing 241-SX sludge profile temperatures. digital.library.unt.edu/ark:/67531/metadc688196/
241-T-107 interim stabilization flammable gas monitor system (safety class 3), acceptance test report
This Acceptance Test Report Provides the acceptance test to be performed at the vendor prior to delivery to Westinghouse Hanford Company. digital.library.unt.edu/ark:/67531/metadc678324/
242-A campaign 95-1 post run document
The 242-A Evaporator Campaign 95-1 was started on June 6, 1995 and finished July 27, 1995. An overall Waste Volume Reduction (WVR) of 8.18 million liters (2.16 mGAL OR 87.6% WVRF) was achieved from 9.35 million liters (2.47 Mgal) of processable waste contained in 108-AP, 107-AP, 106-AW and 102-AW. Slurry generated from Campaign 95-1 consisted of 1.05 million liters (278,000 gal) of dilute double-shell slurry feed (DDSSF) with a SpG of approximately 1.34. Total process condensate discharged to LERF was 10.3 million liters (2.72 Mgal), achieving a condensate/WVR efficiency ratio of 1.26. Total throughout for Campaign 95-1 was 18.1 million liters (4.79 Mgal). B Pond discharges from steam condensate and cooling water were 15.8 and 583 million liters (4.17 and 154 Mgal) respectively. Based on 145 hours of unplanned downtime, the 242-A Evaporator maintained an operating efficiency of 86% during the 49 day campaign. digital.library.unt.edu/ark:/67531/metadc678183/
300 Area dangerous waste tank management system: Compliance plan approach. Final report
In its Dec. 5, 1989 letter to DOE-Richland (DOE-RL) Operations, the Washington State Dept. of Ecology requested that DOE-RL prepare ``a plant evaluating alternatives for storage and/or treatment of hazardous waste in the 300 Area...``. This document, prepared in response to that letter, presents the proposed approach to compliance of the 300 Area with the federal Resource Conservation and Recovery Act and Washington State`s Chapter 173-303 WAC, Dangerous Waste Regulations. It also contains 10 appendices which were developed as bases for preparing the compliance plan approach. It refers to the Radioactive Liquid Waste System facilities and to the radioactive mixed waste. digital.library.unt.edu/ark:/67531/metadc664638/
300 Area waste acid treatment system closure plan. Revision 1
This section provides a description of the Hanford Site, identifies the proposed method of 300 Area Waste Acid Treatment System (WATS) closure, and briefly summarizes the contents of each chapter of this plan. digital.library.unt.edu/ark:/67531/metadc668016/
309 Facility deactivation and decommisioning Criteria Completion Check Lists
To facilitate and track completion of the 309 Facility turnover criteria completion an Applicability Matrix and Criteria Completion Check Lists were prepared. The applicability matrix documents the required turnover criteria for a given area in the facility or scope of work. The applicable criteria is selected for 16 different areas. For each area a completion checklist is provided to document completion of a requirement by WHC and the Environmental Restoration Contractor. digital.library.unt.edu/ark:/67531/metadc681311/
313 building fire alarm system
Acceptance for test for RFAR installation for facility fire alarm and suppression system. digital.library.unt.edu/ark:/67531/metadc687565/
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. digital.library.unt.edu/ark:/67531/metadc683765/
340 Waste handling facility deactivation plan
This document provides an overview of both the present status of the 340 Complex (within Hanford`s 300 Area), and of tasks associated with the deactivation of segments associated with radioactive, mixed liquid waste receipt, storage, and shipping. The plan also describes activities that will allow portions of the 340 Complex to remain in service. digital.library.unt.edu/ark:/67531/metadc687608/
340 Waste handling facility interim safety basis
This document presents an interim safety basis for the 340 Waste Handling Facility classifying the 340 Facility as a Hazard Category 3 facility. The hazard analysis quantifies the operating safety envelop for this facility and demonstrates that the facility can be operated without a significant threat to onsite or offsite people. digital.library.unt.edu/ark:/67531/metadc684701/
400 area secondary cooling water sampling and analysis plan
This is a total rewrite of the Sampling and Analysis Plan in response to, and to ensure compliance with, the State Waste Discharge Permit ST 4501 issued on July 31, 1996. This revision describes changes in facility status and implements requirements of the permit. digital.library.unt.edu/ark:/67531/metadc682613/
500 MW demonstration of advanced wall-fired combustion techniques for the reduction of nitrogen oxide (NOx) emissions from coal-fired boilers. Public design report (preliminary and final)
This Public Design Report presents the design criteria of a DOE Innovative Clean Coal Technology (ICCT) project demonstrating advanced wall-fired combustion techniques for the reduction of NO{sub x} emissions from coal-fired boilers. The project is being conducted at Georgia Power Company`s Plant Hammond Unit 4 (500 MW) near Rome, Georgia. The technologies being demonstrated at this site include Foster Wheeler Energy Corporation`s advanced overfire air system and Controlled Flow/Split Flame low NO{sub x} burner. This report provides documentation on the design criteria used in the performance of this project as it pertains to the scope involved with the low NO{sub x} burners, advanced overfire systems, and digital control system. digital.library.unt.edu/ark:/67531/metadc672735/
An 800-MeV proton beam spill calculation
Using LAHET, the Los Alamos High-Energy Transport code, the authors calculated the radiation hazard from an 800-MeV proton beam spill at the bending magnet. Neutron doses were calculated at an area above the 84.0-cm-thick concrete roof, where there existed a gap with only 30.48-cm concrete shielding. The authors also studied the effect of the gap and proposed a corrective action. digital.library.unt.edu/ark:/67531/metadc686347/
100KE/KW fuel storage basin surface volumetric factors
This Supporting Document presents calculations of surface Volumetric factors for the 100KE and 100KW Fuel Storage Basins. These factors relate water level changes to basin loss or additions of water, or the equivalent water displacement volumes of objects added to or removed from the basin. digital.library.unt.edu/ark:/67531/metadc686510/
11th Topical conference high-temperature plasma diagnostics. Book of abstracts
This report contains abstracts from the 11th topical conference on high-temperature plasma diagnostics. digital.library.unt.edu/ark:/67531/metadc668631/
1300-nm gain obtained with dysprosium-doped chloride crystals
Dy{sup 3+} - doped chloride crystals have high 1300-nm emission quantum yields. Pump - probe experiments on La Cl{sub 3}:Dy{sup 3+} demonstrate optical gain consistent with predictions based on spectroscopic cross sections and lifetimes. digital.library.unt.edu/ark:/67531/metadc665716/
137Cs(90Sr) and Pu isotopes in the Pacific Ocean sources & trends
The main source of artificial radioactivity in the world`s oceans can be attributed to worldwide fallout from atmospheric nuclear weapons testing. Measurements of selected artificial radionuclides in the Pacific Ocean were first conducted in the 1960`s where it was observed that fallout radioactivity had penetrated the deep ocean. Extensive studies carried out during the 1973-74 GEOSECS provided the first comprehensive data on the lateral and vertical distributions of {sup 9O}Sr, {sup 137}Cs and Pu isotopes in the Pacific on a basin wide scale. Estimates of radionuclide inventories in excess of amounts predicted to be delivered by global fallout alone were attributed to close-in fallout and tropospheric inputs from early U.S. tests conducted on Bikini and Enewetak Atolls in the Equatorial Pacific. In general, levels of fallout radionuclides (including {sup 9O}Sr, {sup 137}Cs and Pu isotopes) in the surface waters of the Pacific Ocean have decreased considerably over the past 4 decades and are now much more homogeneously distributed. Resuspension and the subsequent deposition of fallout radionuclides from previously deposited debris on land has become an important source term for the surface ocean. This can be clearly seen in measurements of fallout radionuclides in mineral aerosols over the Korean Peninsula (Yellow dust events). Radionuclides may also be transported from land to sea in river runoff-these transport mechanisms are more important in the Pacific Ocean where large quantities of river water and suspended sands/fluvial sediments reach the coastal zone. Another unique source of artificial radionuclides in the Pacific Ocean is derived from the slow resolubilization and transport of radionuclides deposited in contaminated lagoon and slope sediments near U.S. and French test sites. Although there is a small but significant flux of artificial radionuclides depositing on the sea floor, > 80% of the total 239, {sup 240}Pu inventory and > 95% of the total {sup 137}Cs inventory remains in the water column. Studies conducted through the 1980`s appear to be consistent with earlier findings and indicate that radionuclide inventories in mid-northern latitudes are at least a factor of two above those expected from global fallout alone. The long term persistence of close-in and/or stratospheric fallout from nuclear weapons testing in the Marshall Islands still appears to be the only plausible explanation for this anomaly. digital.library.unt.edu/ark:/67531/metadc690481/
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