Resource Type

HLW Tank Space Management, Final Report (open access)

HLW Tank Space Management, Final Report

The HLW Tank Space Management Team (SM Team) was chartered to select and recommend an HLW Tank Space Management Strategy (Strategy) for the HLW Management Division of Westinghouse Savannah River Co. (WSRC) until an alternative salt disposition process is operational. Because the alternative salt disposition process will not be available to remove soluble radionuclides in HLW until 2009, the selected Strategy must assure that it safely receives and stores HLW at least until 2009 while continuing to supply sludge slurry to the DWPF vitrification process.
Date: September 20, 1999
Creator: Miller, M. S.; Abell, G.; Garrett, R.; D'Entremont, P.; Fowler, J. R.; Mahoney, M. et al.
System: The UNT Digital Library
Effect of single dose x-ray to the nail fold area of human subjects (open access)

Effect of single dose x-ray to the nail fold area of human subjects

In order to further understand the nature of changes which occur in the fingers of persons occupationally exposed to radiation a series of experiments were performed on human subjects generally using x-rays at 130 KV potential, 20 ma and at a distance of 10 cm. Doses ranged from 200-600 r. Fourteen subjects were patients being treated by x-rays or radium for other purposes. The other subject was a staff member who occasionally prepared radium plaques containing 130 mgm of radium. Counts were made of the number of vessels in the terminal row of a measured area of the nail fold. In no case was there any detectable change in the nail fold area within 15 minutes of treatment. Observations were continued for up to 56 days and changes observed included hyperemia, pigmentation, erythemia, and some transitory changes in vascular structure of the affected area. A recommendation for continued studies is made.
Date: June 20, 1947
Creator: Nickson, M.
System: The UNT Digital Library
A study of multistage/multifraction column for fine particle separation. Quarterly technical progress report, second quarter April 1995--July 1995 (open access)

A study of multistage/multifraction column for fine particle separation. Quarterly technical progress report, second quarter April 1995--July 1995

The overall objective of the proposed research program is to explore the potential application of a new invention involving a multistage column equipped with vortex-inducing loop-flow contactors (hereafter referred to as the multistage column) for fine coal cleaning process. The research work will identify the design parameters and their effects on the performance of the separation process. The results of this study will provide an engineering basis for further development of this technology in coal cleaning and in the general areas of fluid/particle separation. In the first year of the project, we completed equipment design, construction of the new column for hydrodynamic tests and gas holdup measurements. Also, we have initiated the determination of bubble size as part of the hydrodynamic measurements.
Date: July 20, 1995
Creator: Chiang, S. H.
System: The UNT Digital Library
Well Installation and Sampling Report for Monitoring Wells TCM6 TCM7, and TNX 28D - 40D and GeoSiphon Cell TGSC-2 (open access)

Well Installation and Sampling Report for Monitoring Wells TCM6 TCM7, and TNX 28D - 40D and GeoSiphon Cell TGSC-2

The shallow groundwater and sediments beneath the TNX Area are contaminated with both dissolved and residual chlorinated volatile organic compounds (CVOCs) such as trichloroethylene (TCE), carbon tetrachloride and perchloroethylene (PCE). The Savannah River Technology Center (SRTC) is studying a new technology for remediating CVOCs known as GeoSiphon.
Date: September 20, 1999
Creator: Nichols, R. L.; Dixon, K. L. & Noonkester, J. V.
System: The UNT Digital Library
Inhomogeneous primordial nucleosynthesis and new abundance constraints on {Omega}{sub b}h{sup 2} (open access)

Inhomogeneous primordial nucleosynthesis and new abundance constraints on {Omega}{sub b}h{sup 2}

We discuss the upper limit to the baryonic contribution to the closure density. We consider effects of new observational and theoretical uncertainties in the primordial light element abundances, and the effects of fluctuation geometry on the inhomogeneous nucleosynthesis yields. We also consider implications of the possible detection of a high D/H abundance in a Lyman-{alpha} absorption cloud at high redshift and the implied chemical evolution effects of a high deuterium abundance. We show that there exists a region of the parameter space for inhomogeneous models in which a somewhat higher baryonic contribution to the closure density is possible than that allowed in standard homogeneous models. This result is contrary to some other recent studies and is due to both geometry and recently revised uncertainties in primordial light-element abundances, particularly {sup 7}Li. We find that the presently adopted abundance constraints are consistent with a contribution of baryons to the closure density as high as {Omega}{sub b}h{sub 50}{sup 2} {le} 0.11 ({eta} {le} 7 {times} 10{sup {minus}10}). This corresponds to a 20% increase over the limit from standard homogeneous models ({Omega}{sub b}h{sub 50}{sup 2} {le} 0.08, {eta} {le} 5.8 {times} 10{sup {minus}10}). With a high deuterium abundance the upper limits for the …
Date: July 20, 1995
Creator: Mathews, G. J.; Kajino, T. & Orito, M.
System: The UNT Digital Library
Long-term Operational Experience with the Barrel CRID at SLD (open access)

Long-term Operational Experience with the Barrel CRID at SLD

The Barrel CRID detector has been operating successfully at SLD for the past seven years. It is an important tool for SLD physics analyses. The long-term operational experience with this device is described.
Date: May 20, 1999
Creator: Va'Vra, Jaroslav
System: The UNT Digital Library
Preoperational test report, cross-site transfer water flush system (POTP-001) (open access)

Preoperational test report, cross-site transfer water flush system (POTP-001)

This report documents the results of the testing performed per POTP-001, for the Cross-Site Transfer Water Flush System. (HNF-1552, Rev. 0) The Flush System consists of a 47,000 gallon tank (302C), a 20 hp pump, two 498kW heaters, a caustic addition pump, various valves, instruments, and piping. The purpose of this system is to provide flush water at 140 F, 140gpm, and pH 11-12 for the Cross-Site Transfer System operation.
Date: February 20, 1998
Creator: Parsons, G.L.
System: The UNT Digital Library
Analysis for Materials Test Reactor (MTR Fuel Assemblies in Dry Storage) (open access)

Analysis for Materials Test Reactor (MTR Fuel Assemblies in Dry Storage)

This report documents a creep analysis to estimate the maximum acceptable temperature for spent aluminum clad nuclear fuels in dry storage.
Date: October 20, 1999
Creator: Miller, R.F.
System: The UNT Digital Library
A Thermal Conduction Analysis of Proposed Lateral and Downstream Row 1 Module Plate Designs (open access)

A Thermal Conduction Analysis of Proposed Lateral and Downstream Row 1 Module Plate Designs

The cavity flood system is designed to be the primary safeguard for the integrity of the blanket modules during loss of coolant accidents (LOCAs). In the unlikely event that the internal flow passages in a module dryout, decay heat in the metal structures will be dissipated to the cavity flood system through the module walls. There is a design proposal under consideration to utilize a single 7.5 inch plate design in the APT blanket lateral modules. Currently, the lateral and downstream row 1 modules are designed with 4.0 inch plates, and longer plates are utilized in the lower power outer row modules. There are many benefits (e.g., fabrication costs, assemblage error reductions) to having a single plate design. The purpose of this study is to determine if the longer plate design meets the safety criterion that, when a module is internally dry, it can be adequately cooled by the cavity flood system.
Date: September 20, 1999
Creator: Shadday, M.A.
System: The UNT Digital Library
Graphite Isotope Ratio Method Development Report: Irradiation Test Demonstration of Uranium as a Low Fluence Indicator (open access)

Graphite Isotope Ratio Method Development Report: Irradiation Test Demonstration of Uranium as a Low Fluence Indicator

This report describes an irradiation test designed to investigate the suitability of uranium as a graphite isotope ratio method (GIRM) low fluence indicator. GIRM is a demonstrated concept that gives a graphite-moderated reactor's lifetime production based on measuring changes in the isotopic ratio of elements known to exist in trace quantities within reactor-grade graphite. Appendix I of this report provides a tutorial on the GIRM concept.
Date: October 20, 1999
Creator: Reid, B. D.; Gerlach, D. C.; Love, E. F.; McNeece, J. P.; Livingston, J. V.; Greenwood, L. R. et al.
System: The UNT Digital Library
General and localized corrosion of the drip shield (open access)

General and localized corrosion of the drip shield

Ti Gr 7 is an extremely corrosion resistant material, with a very stable passive film. Based upon exposures in the LTCTF, it has been determined that the general corrosion and oxidation rates of Ti Gr 7 are essentially below the level of detection. In any event, over the 10,000 year life of the repository, general corrosion and oxidation should not be life limiting. The large separation between measured corrosion and threshold potentials indicate that localized breakdown of the passive film is unlikely under plausible conditions, even in SSW at 120 C. In the future, the pH and current in crevices formed from Ti Gr 7 should be determined experimentally. With exposures of two years, no significant evidence of crevice corrosion has been observed with Ti Gr 16 in SDW, SCW, and SAW at temperatures up to 9O C, though many of the samples have a beautiful green patina. An abstracted model has been presented, with parameters determined experimentally, that should enable performance assessment to account for the general and localized corrosion of this material. A feature of this model is the use of the materials specification to limit the range of corrosion and threshold potentials, thereby making sure that substandard …
Date: August 20, 1999
Creator: Estill, J. C.; Farmer, J. C. & McCright, R. D.
System: The UNT Digital Library
Independent Panel Evaluation of Dry Sludge PISA Program (open access)

Independent Panel Evaluation of Dry Sludge PISA Program

Dr. Kirk Yeager and Mr. Marvin Banks from Energetic Material Research and Technology Center (EMRTC) evaluated the Savannah River Site (SRS) efforts in the Dry Sludge program. They evaluated four program areas: energetic material formation, stability, initiation, and propagation. The panel evaluation included a site visit (July 13, 1999 and July 14, 1999) as well as a review of various reports and presentations by researchers involved in the program.
Date: October 20, 1999
Creator: Fondeur, F. F.
System: The UNT Digital Library
Effects of Crust Ingestion on Mixer Pump Performance in Tank 241-SY-101: Workshop Results (open access)

Effects of Crust Ingestion on Mixer Pump Performance in Tank 241-SY-101: Workshop Results

In August 1999, a workshop was held at Pacific Northwest National Laboratory to discuss the effects of crust ingestion on mixer pump performance in Hanford Waste Tank 241-SY-101. The main purpose of the workshop was to evaluate the potential for crust ingestion to degrade mixing and/or damage the mixer pump. The need for a previously determined 12-inch separation between the top of the mixer pump inlet and the crust base was evaluated. Participants included a representative from the pump manufacturer, an internationally known expert in centrifugal pump theory, Hanford scientists and engineers, and operational specialists representing relevant fields of expertise. The workshop focused on developing an understanding of the pump design, addressing the physics of entrainment of solids and gases into the pump, and assessing the effects of solids and gases on pump performance. The major conclusions are summarized as follows: (1) Entrainment of a moderate amount of solids or gas from the crust should not damage the pump or reduce its lifetime, though mixing effectiveness will be somewhat reduced. (2) Air binding should not damage the pump. Vibrations due to ingestion of gas, solids, and objects potentially could cause radial loads that might reduce the lifetime of bearings and …
Date: October 20, 1999
Creator: Brennen, C.E.; Stewart, C.W. & Meyer, P.A.
System: The UNT Digital Library
Fast Drift CRID with GEM (open access)

Fast Drift CRID with GEM

The only available technique at the present time, to perform particle identification up to 40-50 GeV/c in a 4{pi} solenoidal geometry using the Cherenkov ring imaging method is the use of gaseous detectors tilled with either TMAE or TEA photocathodes, and a combination of the gaseous, and solid or liquid radiators. If one would consider building such a device, one may want to investigate alternative methods of building a single-electron detector. This paper investigates the feasibility of using the GEM together with a simple MWPC detector employing 33 {micro}m diameter carbon wires to obtain a second coordinate. The results are compared to the CRID single-electron detector.
Date: May 20, 1999
Creator: Va'Vra, Jaroslav
System: The UNT Digital Library
SSPX simulation model (open access)

SSPX simulation model

An analytical approximation to an R-L-C circuit representing SSPX is shown to reproduce the observed capacitor bank efficiency and gun optimization data. As in the SPICE code, the spheromak gun is represented by a fixed resistance chosen to balance energy transfer to the gun. A revised estimate of the magnetic decay time in SSPX Shot 1822 then brings our estimate of the gun efficiency itself in line with the observed spheromak magnetic field for this shot. Prompted by these successes, we present a turbulence-based theoretical model for the spheromak resistance that can be implemented in the SPICE code, of the form: R{sub s} = {kappa}I (1-I{sub 0}/I){sup 2} where I is the gun current, I{sub 0} = ({Lambda}{sub 0}/{mu}{sub 0}){Phi} with bias flux and Taylor eigenvalue {lambda}{sub 0}, and {kappa} is a coefficient based on the magnetic turbulence model employed in Dan Hua's spheromak simulation code. The value of {kappa} giving a good energy balance (around 0.1 m{Omega}/KA) implies substantial turbulence levels. Implementing our model in SPICE would provide a calibration for theoretical calculations of the turbulence. Our analytic approximation to the SPICE code provides guidance to optimize future performance in SSPX, the greatest benefit appearing to come from reducing …
Date: September 20, 1999
Creator: Fowler, T K
System: The UNT Digital Library
ICF Quarterly Report April-June 1998, volume 8, number 3 (open access)

ICF Quarterly Report April-June 1998, volume 8, number 3

None
Date: December 20, 1998
Creator: Key, M
System: The UNT Digital Library
APT Blanket Thermal Analyses of Top Horizontal Row 1 Modules (open access)

APT Blanket Thermal Analyses of Top Horizontal Row 1 Modules

The Accelerator Production of Tritium (APT) cavity flood system (CFS) is designed to be the primary safeguard for the integrity of the blanket modules during loss of coolant accidents (LOCAs). For certain large break LOCAs the CFS also provides backup for the residual heat removal systems (RHRs) in cooling the target assemblies. In the unlikely event that the internal flow passages in a blanket module or target assembly dryout, decay heat in the metal structures will be dissipated to the CFS through the module or assembly walls (i.e., rung outer walls). The target assemblies consist of tungsten targets encased in steel conduits, and they can safely sustain high metal temperatures. Under internally dry conditions, the cavity flood fluid will cool the target assemblies with vigorous nucleate boiling on the external surfaces. However, the metal structures in the blanket modules consist of lead cladded in aluminum, and they have a long-term exposure temperature limit currently set to 150 degrees C. Simultaneous LOCAs in both the target and blanket heat removal systems (HRS) could result in dryout of the target ladders, as well as the horizontal blanket modules above the target. The cavity flood coolant would boil on the outside surfaces of …
Date: September 20, 1999
Creator: Shadday, M.A.
System: The UNT Digital Library
Removal of mixing pump in tank 102-AP -- pump drop onto central pit (open access)

Removal of mixing pump in tank 102-AP -- pump drop onto central pit

The mixing pump, if dropped in the pump pit following its removal from the tank, is incapable of compromising the tank structure either locally or in a structural displacement mode to an extent which might allow dispersion of the contents. A drop from 10 ft above the pit floor (considered the maximum credible height) of a pump which is considered perfectly rigid does not approach the required perforation velocity. The velocity required to perforate requires a drop height which is physically impossible to attain with existing cranes. An analysis of the location of the deposition of the strain energy required to match the pump`s impact kinetic energy, the results of which are shown in Table 2, verifies that there is no credible chance for compromise of the tank roof by such a drop.
Date: June 20, 1995
Creator: Jimenez, R. F.
System: The UNT Digital Library
Sampling and analysis plan for sludge located on the floor and in the pits of the 105-K basins (open access)

Sampling and analysis plan for sludge located on the floor and in the pits of the 105-K basins

This Sampling and Analysis Plan (SAP) provides direction for the sampling of the sludge found on the floor and in the remote pits of the 105-K Basins to provide: (1) basic data for the sludges that have not been characterized to-date and (2) representative Sludge material for process tests to be made by the SNF Project/K Basins sludge treatment process subproject. The sampling equipment developed will remove representative samples of the radioactive sludge from underwater at the K Basins, depositing them in shielded containers for transport to the Hanford Site laboratories. Included in the present document is the basic background logic for selection of the samples to meet the requirements established in the Data Quality Objectives (DQO), HNF-2033, for this sampling activity. The present document also includes the laboratory analyses, methods, procedures, and reporting that will be required to meet the DQO.
Date: November 20, 1998
Creator: BAKER, R.B.
System: The UNT Digital Library
TTP SR1-6-WT-31, Milestone C.3-2 Annual Report on Clemson/INEEL Melter Work (open access)

TTP SR1-6-WT-31, Milestone C.3-2 Annual Report on Clemson/INEEL Melter Work

This work is performed in collaboration with RL37WT31-C and ID77WT31-B. During the first two years of radioactive operation of the DWPF process, several areas for improvement in melter design have been identified. The continuing scope of this task is to address performance limitations and deficiencies identified by the user. SRS will design and test several configurations of the melter pour spout and associated equipment to improve consistency of performance and recommend design improvements.
Date: October 20, 1999
Creator: Bickford, D.F.
System: The UNT Digital Library
Property Data for Simulated Americium/Curium Glasses (open access)

Property Data for Simulated Americium/Curium Glasses

The authors studied the properties of mixed lanthanide-alumino-borosilicate glasses. Fifty-five glasses were designed to augment a previous, Phase I, study by systematically varying the composition of Ln{sub 2}O{sub 3} and the concentrations of Ln{sub 2}O{sub 3}, SiO{sub 2}, B{sub 2}O{sub 3}, Al{sub 2}O{sub 3}, and SrO in glass. These glasses were designed and fabricated at the Savannah River Technology Center and tested at the Pacific Northwest National Laboratory. The properties measured include the high-temperature viscosity ({eta}) as a function of temperature (T) and the liquidus temperature (T{sub L}) of Phase II test glasses.
Date: October 20, 1999
Creator: Riley, B. J.; Smith, D. E.; Peeler, D. K.; Reamer, I. A.; Vienna, J. D. & Schweiger, M. J.
System: The UNT Digital Library
Formulation of Molding Materials From Recycled Printed Wiring Boards (open access)

Formulation of Molding Materials From Recycled Printed Wiring Boards

The objective of this project was to formulate the pulverized electronic waste (PEW) stream derived from grinding obsolete electronic assemblies and combine this material with thermoplastic or thermosetting polymers into useful, high-value commercial products materials. PEW consists primarily of various thermoset plastic materials and glass fibers from the printed wiring boards, along with ceramic pieces from chip carriers and other electronic components. Typically, the thermosetting materials have the same desirable properties as in the original electronic assembly, including relatively high temperature resistance, excellent chemical resistance, and flame retardancy. These properties combine to make PEW an inherently good inert filler material for plastic composites.
Date: April 20, 1998
Creator: Lula, J.W. & Bohnert, G.W.
System: The UNT Digital Library
Compton Scattering at the NLC and Large Extra Dimensions (open access)

Compton Scattering at the NLC and Large Extra Dimensions

We study Compton scattering, {gamma}e {yields} {gamma}e, in the context of the recent proposal for Weak Scale Quantum Gravity (WSQG) with large extra dimensions. It is shown that, with an ultraviolet cutoff M{sub S} {approx} 1 TeV for the effective gravity theory, the cross section for this process at the Next Linear Collider (NLC) deviates from the prediction of the Standard Model significantly. Our results suggest that, for typical proposed NLC energies and luminosities, WSQG can be tested in the range 4 TeV {approx}< M{sub S} {approx}< 16 TeV, making {gamma}e {yields} {gamma}e an important test channel.
Date: July 20, 1999
Creator: Davoudiasl, Hooman
System: The UNT Digital Library
Reactivation of an Idle Lease to Increase Heavy Oil Recovery Through Application of Conventional Steam Drive Technology in a Low Dip Slope and Basin Reservoir in the Midway-Sunset Field, San Jaoquin Basin, California (open access)

Reactivation of an Idle Lease to Increase Heavy Oil Recovery Through Application of Conventional Steam Drive Technology in a Low Dip Slope and Basin Reservoir in the Midway-Sunset Field, San Jaoquin Basin, California

A previously idle portion of the Midway-Sunset field, the ARCO Western Energy Pru Fee property, is being brought back into commercial production through tight integration of geologic characterization, geostatistical modeling, reservoir simulation, and petroleum engineering. This property, shut-in over a decade ago as economically marginal using conventional cyclic steaming methods, has a 200-300 foot thick oil column in the Monarch Sand. However, the sand lacks effective steam barriers and has a thick water-saturation zone above the oil-water contact. These factors require an innovative approach to steam flood production design that will balance optimal total oil production against economically viable steam-oil ratios and production rates. The methods used in the Class III demonstration are accessible to most operators in the Midway-Sunset field and could be used to revitalize properties with declining production of heavy oils throughout the region.
Date: March 20, 1998
Creator: Schamel, Steven
System: The UNT Digital Library