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Argonne National Laboratory Reports
30
Fiscal Year 1994
28
Texas Motor Vehicle Traffic Accident Summaries
27
Winter Fuels Report
20
United States Geological Survey Reports
16
Background paper
13
Fiscal Year 1993
13
Summary of All Reported Accidents in Rural Areas of Texas
13
Summary of All Reported Accidents in the State of Texas
13
Construction Report
12
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1/12-Scale scoping experiments to characterize double-shell tank slurry uniformity: Test plan
Million gallon double-shell tanks (DSTs) at Hanford are used to store transuranic, high-level, and low-level wastes. These wastes generally consist of a large volume of salt-laden solution covering a smaller volume of settled sludge primarily containing metal hydroxides. These wastes will be retrieved and processed into immobile waste forms suitable for permanent disposal. The current retrieval concept is to use submerged dual-nozzle pumps to mobilize the settled solids by creating jets of fluid that are directed at the tank solids. The pumps oscillate, creating arcs of high-velocity fluid jets that sweep the floor of the tank. After the solids are mobilized, the pumps will continue to operate at a reduced flow rate sufficient to maintain the particles in a uniform suspension. The objectives of these 1/12-scale scoping experiments are to determine how Reynolds number, Froude number, and gravitational settling parameter affect the degree of uniformity achieved during jet mixer pump operation in the full-scale double-shell tanks; develop linear models to predict the degree of uniformity achieved by jet mixer pumps operating in the full-scale double-shell tanks; apply linear models to predict the degree of uniformity that will be achieved in tank 241-AZ-101 and determine whether contents of that tank will …
Date:
October 1994
Creator:
Bamberger, J. A. & Liljegren, L. M.
System:
The UNT Digital Library
1-Dimensional simulation of thermal annealing in a commercial nuclear power plant reactor pressure vessel wall section
The objective of this work was to provide experimental heat transfer boundary condition and reactor pressure vessel (RPV) section thermal response data that can be used to benchmark computer codes that simulate thermal annealing of RPVS. This specific protect was designed to provide the Electric Power Research Institute (EPRI) with experimental data that could be used to support the development of a thermal annealing model. A secondary benefit is to provide additional experimental data (e.g., thermal response of concrete reactor cavity wall) that could be of use in an annealing demonstration project. The setup comprised a heater assembly, a 1.2 in {times} 1.2 m {times} 17.1 cm thick [4 ft {times} 4 ft {times} 6.75 in] section of an RPV (A533B ferritic steel with stainless steel cladding), a mockup of the {open_quotes}mirror{close_quotes} insulation between the RPV and the concrete reactor cavity wall, and a 25.4 cm [10 in] thick concrete wall, 2.1 in {times} 2.1 in [10 ft {times} 10 ft] square. Experiments were performed at temperature heat-up/cooldown rates of 7, 14, and 28{degrees}C/hr [12.5, 25, and 50{degrees}F/hr] as measured on the heated face. A peak temperature of 454{degrees}C [850{degrees}F] was maintained on the heated face until the concrete wall …
Date:
November 1, 1994
Creator:
Nakos, J. T.; Rosinski, S. T. & Acton, R. U.
System:
The UNT Digital Library
3-D TECATE/BREW: Thermal, stress, and birefringent ray-tracing codes for solid-state laser design
This report describes the physics, code formulations, and numerics that are used in the TECATE (totally Eulerian code for anisotropic thermo-elasticity) and BREW (birefringent ray-tracing of electromagnetic waves) codes for laser design. These codes resolve thermal, stress, and birefringent optical effects in 3-D stationary solid-state systems. This suite of three constituent codes is a package referred to as LASRPAK.
Date:
July 20, 1994
Creator:
Gelinas, R. J.; Doss, S. K. & Nelson, R. G.
System:
The UNT Digital Library
3-D Turbulent Particle Dispersion Submodel Development. Quarterly Progress Report No. 3, October 15, 1991--January 15, 1992
Many practical combustion processes which use solid particles, liquid droplets, or slurries as fuels introduce these fuels into turbulent environments. Examples include spray combustion, pulverized coal and coal slurry combustion, fluidized beds, sorbent injection, and hazardous waste incineration. The interactions of the condensed phases with turbulent environments have not been well described. Such a description is complicated by the difficulty of describing turbulence in general, even in the absence of particles or droplets. But the complications in describing the dispersion and reaction of the condensed phases in turbulent environments do not stem entirely or even primarily from the uncertainties in the description of the turbulence. Theoretical descriptions of the turbulent dispersion of particles and droplets are not well established, even when the characteristics of the turbulence are known. Several new theoretical descriptions of the turbulent dispersion of particles an droplets have proposed over the past five years. It is the purpose of this project to explore the potential of two of these theories for coupling with the other aspects of three-dimensional, reacting, turbulent, particle-laden systems to proved computational simulations that could be useful for addressing industrial problems.
Date:
September 1, 1994
Creator:
Smith, P. J.
System:
The UNT Digital Library
3-D turbulent particle dispersion submodel development. Quarterly progress report No. 4, January 15, 1992--April 15, 1992
Many practical combustion processes which use solid particles, liquid droplets, or slurries as fuels introduce these fuels into turbulent environments. Examples include spray combustion, pulverized coal and coal slurry combustion, fluidized beds, sorbent injection, and hazardous waste incineration. The interactions of the condensed phases with turbulent environments have not been well described. Such a description is complicated by the difficulty of describing turbulence in general, even in the absence of particles or droplets. But the complications in describing the dispersion and reaction of the condensed phases in turbulent environments do not stem entirely or even primarily from the uncertainties in the description of the turbulence. Theoretical descriptions of the turbulent dispersion of particles and droplets are not well established, even when the characteristics of the turbulence are known. It is the purpose of this project to develop two different particle dispersion submodels (one each for dilute and dense phases), and couple them with existing fluid-dynamic heat transfer and reaction chemistry models to provide computational simulations capable of addressing industrial problems.
Date:
September 1, 1994
Creator:
Smith, P. J.
System:
The UNT Digital Library
5 MW pulsed spallation neutron source, Preconceptual design study
This report describes a self-consistent base line design for a 5 MW Pulsed Spallation Neutron Source (PSNS). It is intended to establish feasibility of design and as a basis for further expanded and detailed studies. It may also serve as a basis for establishing project cost (30% accuracy) in order to intercompare competing designs for a PSNS not only on the basis of technical feasibility and technical merit but also on the basis of projected total cost. The accelerator design considered here is based on the objective of a pulsed neutron source obtained by means of a pulsed proton beam with average beam power of 5 MW, in {approx} 1 {mu}sec pulses, operating at a repetition rate of 60 Hz. Two target stations are incorporated in the basic facility: one for operation at 10 Hz for long-wavelength instruments, and one operating at 50 Hz for instruments utilizing thermal neutrons. The design approach for the proton accelerator is to use a low energy linear accelerator (at 0.6 GeV), operating at 60 Hz, in tandem with two fast cycling booster synchrotrons (at 3.6 GeV), operating at 30 Hz. It is assumed here that considerations of cost and overall system reliability may favor …
Date:
June 1, 1994
Creator:
unknown
System:
The UNT Digital Library
A 10 um Resolution Secondary Emission Monitor for Fermilab's Targeting Station
Improvement in focusing the proton beam onto the antiproton production target necessitates the development of a higher resolution beam profile monitor. Two designs for the construction of a multiwire profile mointor grid are presented. The first is a conventional strung and tensioned Ti wire design. The second is a photo etched Ti grid of wires bonded to a ceramic substrate. Both have a central wire spacing of 125 {mu}m. The completed beam profile monitors are designed to operate in a 120 GeV beam pulse of 5 x 10{sup 12} protons with a 1.5{mu}s duration and will be installed in late 1993.
Date:
January 1, 1994
Creator:
Hurh, P.; O'Day, S.; Dombrowski, R. & Page, T.
System:
The UNT Digital Library
The 12-GeV/c beam transfer and absorber lines for the Superconducting Super Collider
The beam optics of the 12-GeV/c proton beam transfer line between the Low Energy Booster (LEB) and the Medium Energy Booster (MEB) at the Superconducting Super Collider is presented. The beam is extracted from the LEB vertically and is injected into the MEB through a vertical Lambertson magnet and a horizontal kicker. The beamline has high flexibility for amplitude and dispersion function matching. Effects of various errors in the transfer line are studied, and a beam position correction scheme is proposed. The beam optics of the 12-GeV/c absorber line transporting the beam from the LEB to an absorber during the LEB commissioning is also presented.
Date:
August 1, 1994
Creator:
Mao, N.; McGill, J.; Gerig, R. & Brown, K.
System:
The UNT Digital Library
13. international conference on the application of accelerators in research and industry. Final performance technical report
This report summarizes attendance at the conference, describes its session subjects and other activities, names its sponsoring organizations, and references where the papers published for it may be found (in Nuclear Instruments and Methods in Physics Research Vol. B 99 (1995)).
Date:
1994~
Creator:
unknown
System:
The UNT Digital Library
A 40 GByte/s read-out system for GEM
The preliminary design of the read-out system for the GEM (Gammas, Electrons, Muons) detector at the Superconducting Super Collider is presented. The system reads all digitized data from the detector data sources at a Level 1 trigger rate of up to 100 kHz. A total read-out bandwidth of 40 GBytes/s is available. Data are stored in buffers that are accessible for further event filtering by an on-line, processor farm. Data are transported to the farm only as they are needed by the higher-level trigger algorithms, leading to a reduced bandwidth requirement in the Data Acquisition System.
Date:
April 1994
Creator:
Bowden, M.; Carrel, J.; Dorenbosch, J. & Kapoor, V.
System:
The UNT Digital Library
45-Day deliverable for Tank 241-BX-105 Auger samples, risers 2 and 6
Two auger samples from single-shell tank 241-BX-105 (BX-105) were extruded, broken down, and analyzed for DSC, TGA, and total alpha as prescribed. Analytical results were tracked and reported using the laboratory information management system known as LabCore. This is the final report for the fiscal year 1995 BX-105 auger sample characterization effort. Included are copies of the differential scanning calorimetry (DSC) and thermogravimetric analyses (TGA) scans as requested. Also included is a copy of any immediate notification documentation, chain of custody forms, the hot cell work plan, extruded segment [auger] description sheets, and total alpha data.
Date:
November 16, 1994
Creator:
Bell, K. E.
System:
The UNT Digital Library
45-Day safety screen results for single shell tank 241-AP-106, liquid grab samples, riser 1, 30{degrees} and 150{degrees} in conjunction with evaporator campaign 95-1
This is the 45-Day report for the fiscal year 1995 safety screening characterization of three liquid grab samples from single shell tank 241-AP-106. The required analyses are differential scanning calorimetry (DSC), thermal gravimetric analysis (TGA) and appearance (APPR). No analytes exceeded the notification limits, therefore, secondary analyses (RSST, cyanide, and hot persulfate-total organic carbon) were not required. Summary data tables 2, 3 and 4 present the appearance, DSC and TGA data, respectively. Total alpha analyses are not included in this report, because it is not required for liquid grab samples.
Date:
December 14, 1994
Creator:
Miller, G. L.
System:
The UNT Digital Library
45-Day safety screening for Tank 241-B-102 auger samples, riser 1
This is the 45-Day report for the fiscal year 1994 Tank 241-B-102 auger sampling characterization effort. Only one of the two planned auger samples was received by the 222-S Laboratory, however it was decided to begin the 45-day clock and issue a report based on receipt of the first auger sample. Included are copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans as requested. Also included is a copy of any immediate notification documentation, chain of custody forms, the hot cell work plan, extruded segment [auger] description sheets, and total alpha data. The TGA percent moisture results are below the safety criteria limit of 17% in a subsample taken approximately five minutes after extrusion and a second subsample taken from the lower half of the auger. Verbal and written notifications were made as prescribed. The DSC analysis of all subsamples indicates the presence of fraction exotherms, however the results are a factor of two or more below the notification limit of 523 Joules/gram (J/g). Total alpha results are all below the detection limit. In some cases, the tank characterization plan (TCP) accuracy and precision criteria are not met. If a re-run was not performed when a TCP …
Date:
December 1, 1994
Creator:
Bell, K. E.
System:
The UNT Digital Library
45-Day safety screening for Tank 241-C-103 push mode sample, riser 2
This is the 45-Day report for the Tank 241-C-103 (C-103) push-mode core sampling characterization effort. Problems encountered with the push-mode sampling truck following removal of the first segment from riser 2 resulted in a long delay before resumption of sampling, therefore it was decided to begin the 45-day clock and issue a report based on receipt of this first segment. If subsequent segments are removed from tank C-103, a revision of this report or a new report will be issued to include any new data. Included are copies of the differential scanning calorimetry (DSC) and thermogravimetric analysis (TGA) scans as requested in Reference 1. Also included is a copy of any immediate notification documentation. Other pertinent documentation will be included in the C-103 216-day report.
Date:
December 16, 1994
Creator:
Bell, K. E.
System:
The UNT Digital Library
95-1 Campaign evaporator boildown results
The Process Chemistry Laboratories were requested to support the 242-A Evaporator restart as part of the overall 222-S laboratory effort. The net purpose of these studies is to determine the characteristics of double-shell tank materials as they are processed in the evaporator. The results for the boildown study (which includes pressure and temperature versus % waste volume reduction and density of final boildown residue) supporting the 242-A Evaporator restart are reported below. The boildown was performed in a vacuum distillation apparatus with an adjustable vacuum limiting manometer and an isolatable collection graduated cylinder. The boildown was conducted over a seven hour period. The evaporation was done at 60 torr (to avoid excessive foaming and bumping of solution) for approximately half of the boildown, the pressure then being reduced to 40 torr when the reduction in solution volume allowed this to be done. Percent waste volume reduction was measured by observing the amount of condensate collected in a graduated cylinder. As the graduated cylinder became full, it was isolated from the rest of the system and the condensate removed. Pressure was set using an electronic manometer with a low pressure limiter set at the desired level. Temperature was measured using a …
Date:
October 10, 1994
Creator:
Miller, G. L.
System:
The UNT Digital Library
100 Area electrical distribution fault and coordination report
This report documents three-phase and line-to-ground fault values and time overcurrent coordination curves for the electrical utility distribution system located in the 100 Areas. Activities that may improve the coordination of the distribution system have also been identified. An evaluation of system coordination was performed. The results of this evaluation are listed in Appendix B. There are protective devices within the 100 Area distribution system that do not coordinate with one another throughout the Areas. There is also a mis-application of reclosing relays at the 100B Area. The impact of the mis-coordination and incorrect application of reclosing relays is that system selectivity is reduced. Equipment will still be protected against damaging currents, however more equipment will be de-energized than necessary during fault conditions. It is the opinion of the author of this report that the cases of mis-coordination listed above, and in Appendix B, do not significantly degrade the system protection system nor the reliability of the 100 Area distribution system. Therefore, immediate response to correct these problems is not recommended. However, a planned methodology, outlined in an Activity Plan, to correct these problems should be developed and implemented in the near future.
Date:
September 23, 1994
Creator:
Webber, J. J.
System:
The UNT Digital Library
100 Area excavation treatability study data validation report
This report presents the results of sampling and chemical analyses at Hanford Reservation. The samples were analyzed by Thermo-Analytic Laboratories and Roy F. Weston Laboratories using US Environmental Protection Agency CLP protocols. Sample analyses included: volatile organics; semivolatile organics; inorganics; and general chemical parameters. The data from the chemical analyses were reviewed and validated to verify that reported sample results were of sufficient quality to support decisions regarding remedial actions performed at this site.
Date:
May 19, 1994
Creator:
Frain, J. M.
System:
The UNT Digital Library
100 Area soil washing: Bench scale tests on 116-F-4 pluto crib soil
The Pacific Northwest Laboratory conducted a bench-scale treatability study on a pluto crib soil sample from 100 Area of the Hanford Site. The objective of this study was to evaluate the use of physical separation (wet sieving), treatment processes (attrition scrubbing, and autogenous surface grinding), and chemical extraction methods as a means of separating radioactively-contaminated soil fractions from uncontaminated soil fractions. The soil washing treatability study was conducted on a soil sample from the 116-F-4 Pluto Crib that had been dug up as part of an excavation treatability study. Trace element analyses of this soil showed no elevated concentrations above typically uncontaminated soil background levels. Data on the distribution of radionuclide in various size fractions indicated that the soil-washing tests should be focused on the gravel and sand fractions of the 116-F-4 soil. The radionuclide data also showed that {sup 137}Cs was the only contaminant in this soil that exceeded the test performance goal (TPG). Therefore, the effectiveness of subsequent soil-washing tests for 116-F-4 soil was evaluated on the basis of activity attenuation of {sup 137}Cs in the gravel- and sand-size fractions.
Date:
June 10, 1994
Creator:
Field, J. G.
System:
The UNT Digital Library
100 areas technical activities report - engineering, May, 1948
This report is the May, 1948, progress report from the pile engineering groups in support of the production reactors in the 100 Area of the Hanford Reservation. Included are studies of reactor slug fabrication techniques relative to blistering and corrosion, corrosion of reactor components, studies and design of graphite blocks for reactors, and reactor cover gas changes and studies.
Date:
June 18, 1994
Creator:
Woods, W. K.
System:
The UNT Digital Library
100-B area technical baseline report
This document supports the environmental remediation effort of the 100-B Area by providing remediation planners with key data that characterize the 100-B and 100-C Reactor sites. It provides operational histories of the 100-B and 100-C Reactors and each of their associated liquid and solid waste sites.
Date:
September 1, 1994
Creator:
Carpenter, R. W.
System:
The UNT Digital Library
100-DR-1 radiological surveys
This report summarizes and documents the results of the radiological surveys conducted over the surface of the 100-DR-1 Operable Unit, Hanford Site, Richland, Washington. In addition, this report explains the survey methodology using the Ultrasonic Ranging and Data System (USRADS). The 100-DR-1 radiological survey field task consisted of two activities: characterization of the operable unit-specific background conditions and the radiological survey of the operable unit surface area. The survey methodology was based on utilization of USRADS for automated recording of the gross gamma radiation levels at or near 6 in. and at 3 ft from the surface soil. The purpose of the survey is to identify the location of unidentified subsurface radioactive material areas and any surface contamination associated with these areas. The radiological surveys were conducted using both a digital count rate meter with a NaI detector reporting in counts per minute (CPM) and a dose rate meter reporting micro-Roentgen per hour (uR) connected to a CHEMRAD Tennessee Corp. Series 2000 USRADS. The count rate meter was set for gross counting, i.e., Window ``out``. The window setting allows detection of low, intermediate, and high energy photons. The USRADS equipment is used to record the detector readings verses the location …
Date:
January 28, 1994
Creator:
Naiknimbalkar, N. M.
System:
The UNT Digital Library
100 Hour Test of the Pressurized Woodchip-Fired Gravel Bed Combustor
Combustion of wood chips in a packed bed combustor for a gas turbine cogeneration system is described. A discussion on flue gas emissions and mass balances is included.
Date:
August 1, 1994
Creator:
Ragland, Kenneth W. & Aerts, Danny J.
System:
The UNT Digital Library
101-SY waste sample speed of sound/rheology testing for sonic probe program
One problem faced in the clean-up operation at Hanford is that a number of radioactive waste storage tanks are experiencing a periodic buildup and release of potentially explosive gases. The best known example is Tank 241-SY-101 (commonly referred to as 101-SY) in which hydrogen gas periodically built up within the waste to the point that increased buoyancy caused a roll-over event, in which the gas was suddenly released in potentially explosive concentrations (if an ignition source were present). The sonic probe concept is to generate acoustic vibrations in the 101-SY tank waste at nominally 100 Hz, with sufficient amplitude to cause the controlled release of hydrogen bubbles trapped in the waste. The sonic probe may provide a potentially cost-effective alternative to large mixer pumps now used for hydrogen mitigation purposes. Two important parameters needed to determine sonic probe effectiveness and design are the speed of sound and yield stress of the tank waste. Tests to determine these parameters in a 240 ml sample of 101-SY waste (obtained near the tank bottom) were performed, and the results are reported.
Date:
July 25, 1994
Creator:
Cannon, N. S.
System:
The UNT Digital Library
105-KE Basin isolation barrier leak rate test analytical development
This report provides analytical developments in support of the proposed leak rate test of the 105-KE Basin. The analytical basis upon which the K-basin leak test results will be used ti determine the basin leakage rates is developed in this report. The leakage of the K-Basin isolation barriers under accident conditions will be determined from the test results. There are two fundamental flow regimes that may exist in the postulated K-Basin leakage, viscous laminar and turbulent flow. An analytical development is presented for each flow regime. The basic geometry and nomenclature of the postulated leak paths are denoted.
Date:
December 1, 1994
Creator:
Irwin, J. J.
System:
The UNT Digital Library