Valuing the salmon resource: Columbia River stocks under climate change and fishery enhancement (open access)

Valuing the salmon resource: Columbia River stocks under climate change and fishery enhancement

This paper represents an update to ongoing multidisciplinary research in the area of climate change and associated regional impacts to fisheries and economies. This work particularly deals with the total value of Columbia River salmon and the idea that fish have capital value, articulated here as spawning value. Earlier work dealt solely with the Yakima River spring chinook fishery`s response to climate change and fishery enhancement programs and the associated direct economic effects (Anderson et al. 1992). We have expanded our modeling attempts to examine similar impacts in the Grande Ronde River subbasin of the Columbia River basin, and added the summer steelhead stock to the analysis. Relatively recent developments and improvements in climate change modeling and fishery modeling enabled us to attempt such an endeavor.
Date: April 1, 1993
Creator: Anderson, D. M. & Scott, M. J.
Object Type: Article
System: The UNT Digital Library
Waste glass melting stages (open access)

Waste glass melting stages

Three different simulated nuclear waste glass feeds, consisting of dried waste and glass frit, were heat treated for 1 hour in a gradient furnace at temperatures ranging from approximately 600[degrees]C--1000[degrees]C. Simulated melter feeds from the Hanford Waste Vitrification Plant (HWVP), the Defense Waste Processing Facility (DWPF), and Kernforschungszentrum Karlsruhe (KfK) in Germany were used. The samples were thin-sectioned and examined by optical microscopy to investigate the stages of the conversion from feed to glass. Various phenomena were seen, such as frit softening, bubble formation, foaming, bubble motion and removal, convective mixing, and homogenization. Behavior of different feeds was similar, although the degree of gas generation and melt homogenization varied.
Date: April 1, 1993
Creator: Anderson, L. D.; Dennis, T.; Elliott, M. L. & Hrma, P.
Object Type: Article
System: The UNT Digital Library
Waste glass melting stages (open access)

Waste glass melting stages

Three different simulated nuclear waste glass feeds, consisting of dried waste and glass frit, were heat treated for 1 hour in a gradient furnace at temperatures ranging from approximately 600{degrees}C--1000{degrees}C. Simulated melter feeds from the Hanford Waste Vitrification Plant (HWVP), the Defense Waste Processing Facility (DWPF), and Kernforschungszentrum Karlsruhe (KfK) in Germany were used. The samples were thin-sectioned and examined by optical microscopy to investigate the stages of the conversion from feed to glass. Various phenomena were seen, such as frit softening, bubble formation, foaming, bubble motion and removal, convective mixing, and homogenization. Behavior of different feeds was similar, although the degree of gas generation and melt homogenization varied.
Date: April 1, 1993
Creator: Anderson, L. D.; Dennis, T.; Elliott, M. L. & Hrma, P.
Object Type: Article
System: The UNT Digital Library
Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot (open access)

Waste Isolation Pilot Plant simulated RH TRU waste experiments: Data and interpretation pilot

The simulated, i.e., nonradioactive remote-handled transuranic waste (RH TRU) experiments being conducted underground in the Waste Isolation Pilot Plant (WIPP) were emplaced in mid-1986 and have been in heated test operation since 9/23/86. These experiments involve the in situ, waste package performance testing of eight full-size, reference RH TRU containers emplaced in horizontal, unlined test holes in the rock salt ribs (walls) of WIPP Room T. All of the test containers have internal electrical heaters; four of the test emplacements were filled with bentonite and silica sand backfill materials. We designed test conditions to be ``near-reference`` with respect to anticipated thermal outputs of RH TRU canisters and their geometrical spacing or layout in WIPP repository rooms, with RH TRU waste reference conditions current as of the start date of this test program. We also conducted some thermal overtest evaluations. This paper provides a: detailed test overview; comprehensive data update for the first 5 years of test operations; summary of experiment observations; initial data interpretations; and, several status; experimental objectives -- how these tests support WIPP TRU waste acceptance, performance assessment studies, underground operations, and the overall WIPP mission; and, in situ performance evaluations of RH TRU waste package materials plus …
Date: April 1, 1993
Creator: Molecke, M. A.; Argueello, G. J. & Beraun, R.
Object Type: Report
System: The UNT Digital Library
Waste separations and pretreatment technology development in the Underground Storage Tank--Integrated Demonstration Program (open access)

Waste separations and pretreatment technology development in the Underground Storage Tank--Integrated Demonstration Program

The principal objective of the Underground Storage Tank Integrated Demonstration (UST-ID) Program is the demonstration and continued development of technologies suitable for the remediation of USTs. The most promising new technologies are selected for demonstration, testing, and evaluation. The objective is the eventual transfer of new technologies as a system to full-scale remediation at US Department of Energy (DOE) complexes and sites in the private sector. Technologies under development in the UST-ID Program are targeted toward use in remediation actions at the following five DOE participant sites: Hanford, Fernald, Idaho, Oak Ridge, and Savannah River. Combined, these participant sites have more than 300 USTs containing more than 100 m gal of high-level and low-level radioactive liquid waste. This paper focuses on the Waste Separations and Pretreatment area of the UST-ID, summarizing the currently funded technology development projects. In this area, several ``compact processing units`` (CPUs) are being developed to effect near-term demonstration and deployment of promising processes in actual tank environments. The CPU design and development approach is summarized. A number of programmatic issues are discussed, including onsite and offsite transportation of potentially contaminated processing systems, containment design criteria, including applicable codes and standards, and operation and maintenance of such …
Date: April 1, 1993
Creator: Cruse, J. M.
Object Type: Article
System: The UNT Digital Library
Water level measurements for modeling hydraulic properties in the 300-FF-5 and 100 Aggregate Area Operable units (open access)

Water level measurements for modeling hydraulic properties in the 300-FF-5 and 100 Aggregate Area Operable units

Pressure transducers connected to dataloggers were used to measure ground water and Columbia River water elevations simultaneously and hourly at 35 locations in the 300-FF-5 Operable Unit and 16 locations in the 100 Aggregate Area Operable Unit on the Hanford Site. Water temperatures were also measured at 12 of these locations. This report details the findings of these studies.
Date: April 1, 1993
Creator: Campbell, M. D.; McMahon, W. J. & Simpson, K. R.
Object Type: Report
System: The UNT Digital Library
Welding tritium aged stainless steel (open access)

Welding tritium aged stainless steel

Stainless steels exposed to tritium become unweldable by conventional methods due to He buildup within the metal matrix. With longer service lives expected for new weapon systems, and service life extensions of older systems, methods for welding/repair on tritium-exposed material will become important. Results are reported that indicate that both solid-state resistance welding and low-heat gas metal arc overlay welding are promising methods for repair or modification of tritium-aged stainless steel.
Date: April 1, 1993
Creator: Kanne, W. R., Jr.
Object Type: Article
System: The UNT Digital Library
What can be learned from epidemiologic studies of persons exposed to low doses of radiation? (open access)

What can be learned from epidemiologic studies of persons exposed to low doses of radiation?

The main objective of radiation risk assessment is to determine the risk of various adverse health effects associated with exposure to low doses and low dose rates. Extrapolation of risks from studies of persons exposed at high doses (generally exceeding 1 Sv) and dose rates has been the primary approach used to achieve this objective. The study of Japanese atomic bomb survivors in Hiroshima and Nagasaki has played an especially important role in risk assessment efforts. A direct assessment of the dose-response function based on studies of persons exposed at low doses and dose rates is obviously desirable. This paper focuses on the potential of both current and future nuclear workers studies for investigating the dose-response functions at low doses, and also discusses analyses making use of the low dose portion of the atomic bomb survivor data. Difficulties in using these data are the statistical imprecision of estimated dose-response parameters, and potential bias resulting from confounding factors and from uncertainties in dose estimates.
Date: April 1, 1993
Creator: Gilbert, E. S.
Object Type: Article
System: The UNT Digital Library
Whole-arm obstacle avoidance system conceptual design (open access)

Whole-arm obstacle avoidance system conceptual design

Whole-arm obstacle avoidance is needed for a variety of robotic applications in the Environmental Restoration and Waste Management (ER WM) Program. Typical industrial applications of robotics involve well-defined workspaces, allowing a predetermined knowledge of collision-free paths for manipulator motion. In the unstructured or poorly defined hazardous environments of the ER WM Program, the potential for significant problems resulting from collisions between manipulators and the environment in which they are utilized is great. The conceptual design for a sensing system that will provide protection against such collisions is described herein. The whole-arm obstacle avoidance system consists of a set of sensor bracelets,'' which cover the surface area of the manipulator links to the maximum extent practical, and a host processor. The host processor accepts commands from the robot control system, controls the operation of the sensors, manipulates data received from the bracelets, and makes the data available to the manipulator control system. The bracelets consist of a subset of the sensors, associated sensor interface electronics, and a bracelet interface. Redundant communications links between the host processor and the bracelets are provided, allowing single-point failure protection. The system allows reporting of 8-bit data from up to 1000 sensors at a minimum of …
Date: April 1, 1993
Creator: Wintenberg, A. L.; Butler, P. L.; Babcock, S. M.; Ericson, M. N. & Britton, C. L., Jr.
Object Type: Report
System: The UNT Digital Library
Whole-arm obstacle avoidance system conceptual design (open access)

Whole-arm obstacle avoidance system conceptual design

Whole-arm obstacle avoidance is needed for a variety of robotic applications in the Environmental Restoration and Waste Management (ER&WM) Program. Typical industrial applications of robotics involve well-defined workspaces, allowing a predetermined knowledge of collision-free paths for manipulator motion. In the unstructured or poorly defined hazardous environments of the ER&WM Program, the potential for significant problems resulting from collisions between manipulators and the environment in which they are utilized is great. The conceptual design for a sensing system that will provide protection against such collisions is described herein. The whole-arm obstacle avoidance system consists of a set of sensor ``bracelets,`` which cover the surface area of the manipulator links to the maximum extent practical, and a host processor. The host processor accepts commands from the robot control system, controls the operation of the sensors, manipulates data received from the bracelets, and makes the data available to the manipulator control system. The bracelets consist of a subset of the sensors, associated sensor interface electronics, and a bracelet interface. Redundant communications links between the host processor and the bracelets are provided, allowing single-point failure protection. The system allows reporting of 8-bit data from up to 1000 sensors at a minimum of 50 Hz. …
Date: April 1, 1993
Creator: Wintenberg, A. L.; Butler, P. L.; Babcock, S. M.; Ericson, M. N. & Britton, C. L., Jr.
Object Type: Report
System: The UNT Digital Library
Wildlife Mitigation and Restoration for Grand Coulee Dam: Blue Creek Project, Phase 1. (open access)

Wildlife Mitigation and Restoration for Grand Coulee Dam: Blue Creek Project, Phase 1.

This report is a recommendation from the Spokane Tribe to the Northwest Power Planning Council (NPPC) for partial mitigation for the extensive wildlife and wildlife habitat losses on the Spokane Indian Reservation caused by the construction of Grand Coulee Dam. NPPC`s interim wildlife goal over the next 7 years for the Columbia hydropower system, is to protect, mitigate and enhance approximately 35% basin wide of the lost habitat units. Grand Coulee Dam had the greatest habitat losses of any Dams of the Wildlife Rule.
Date: April 1, 1993
Creator: Merker, Christopher
Object Type: Report
System: The UNT Digital Library
X- and {gamma}-ray computed tomography applications at LLNL (open access)

X- and {gamma}-ray computed tomography applications at LLNL

Members of the Nondestructive Evaluation (NDE) Section at the Lawrence Livermore National Laboratory (LLNL) have implemented the advanced three-dimensional imaging technique of x and {gamma}-ray computed tomography (CAT or CT) for industrial and scientific nondestructive evaluation. This technique provides internal and external views of materials, components, and assemblies nonintrusively. Our research and development includes building CT scanners as well as data preprocessing, image reconstruction, display and analysis algorithms. These capabilities have been applied for a variety of industrial and scientific NDE applications where objects can range in size from 1 mm{sup 3} to 1 m{sup 3}. Here we discuss the usefulness of Cr to evaluate: Ballistic target materials, high-explosives shape charges, missile nosetips, and reactor-fuel tubes.
Date: April 1, 1993
Creator: Roberson, G. P.; Martz, H. E.; Schneberk, D. J. & Azevedo, S. G.
Object Type: Article
System: The UNT Digital Library
X-ray and neutron scattering studies of magnetic critical fluctuations in holmium (open access)

X-ray and neutron scattering studies of magnetic critical fluctuations in holmium

We describe measurements of the magnetic critical fluctuations of holmium by x-ray scattering techniques. The x-ray results are compared to those obtained in neutron scattering experiments performed on the same sample.
Date: April 1, 1993
Creator: Thurston, T. R.; Helgesen, G.; Gibbs, D.; Shirane, G.; Hill, J. P. & Gaulin, B. D.
Object Type: Article
System: The UNT Digital Library
X-ray beam lines and beam line components for the SLAC Linac Coherent Light Source (LCLS) (open access)

X-ray beam lines and beam line components for the SLAC Linac Coherent Light Source (LCLS)

The LCLS is a novel high-brightness x-ray source designed to operate in the 300--400 eV range. In contrast to conventional synchrotron radiation sources, its output pulses will be characterized by unprecedented levels of brevity and peak power. In this paper we present recently-developed beam line layouts and design features intended to optimize the delivery of the LCLS photons to various experimental stations.
Date: April 1, 1993
Creator: Tatchyn, R. & Pianetta, P.
Object Type: Article
System: The UNT Digital Library
X-ray diagnostics of tokamak plasmas (open access)

X-ray diagnostics of tokamak plasmas

This paper discusses the influence that salinity has on the bioavailability of the two largest classes of contaminants, trace metals and organic compounds will be discussed. Although data on contaminant toxicity will be used to draw inferences about chemical availability, this discussion will focus on the properties that contaminants are likely to exhibit in waters of varying salinities. In addition, information on physiological changes that are affected by salinity will be used to illustrate how biological effects can alter the apparent availability of contaminants.
Date: April 1, 1993
Creator: Bitter, M.; Hsuan, H.; Hill, K.W. & Zarnstorff, M.
Object Type: Article
System: The UNT Digital Library
X-ray diagnostics of tokamak plasmas (open access)

X-ray diagnostics of tokamak plasmas

This paper discusses the influence that salinity has on the bioavailability of the two largest classes of contaminants, trace metals and organic compounds will be discussed. Although data on contaminant toxicity will be used to draw inferences about chemical availability, this discussion will focus on the properties that contaminants are likely to exhibit in waters of varying salinities. In addition, information on physiological changes that are affected by salinity will be used to illustrate how biological effects can alter the apparent availability of contaminants.
Date: April 1, 1993
Creator: Bitter, M.; Hsuan, H.; Hill, K. W. & Zarnstorff, M.
Object Type: Article
System: The UNT Digital Library
Zinc(II) oxide stability in alkaline sodium phosphate solutions at elevated temperatures (open access)

Zinc(II) oxide stability in alkaline sodium phosphate solutions at elevated temperatures

Zinc oxide (ZnO) is shown to transform into either of two phosphate-containing compounds in relatively dilute alkaline sodium phosphate solutions at elevated temperatures via ZnO(s) + Na{sup +} + H{sub 2}PO{sub 4}{sup {minus}} {r_reversible} NaZnPO{sub 4}(s) + H{sub 2}O or 2 ZnO(s) + H{sub 3}PO{sub 4}(aq) {r_reversible} Zn{sub 2}(OH)PO{sub 4}(s) + H{sub 2}O. X-ray diffraction analyses indicate that NaZnPO{sub 4} possesses an orthorhombic unit cell having lattice parameters a = 8.710 {+-} 0.013, b = 15.175 {+-} 0.010, and c = 8.027 {+-} 0.004 {angstrom}. The thermodynamic equilibria for these reactions were defined in the system ZnO-Na{sub 2}O-P{sub 2}O{sub 5}-H{sub 2}O for Na/P molar ratios between 2.1 and 3. Based on observed reaction threshold values for sodium phosphate concentration and temperature, the standard entropy (S{degrees}) and free energy of formation ({Delta}G{sub f}{degrees}) for NaZnPO{sub 4} were calculated to be 169.0 J/mol-K and {minus}1510.6 kJ/mol, respectively; similar values for Zn{sub 2}(OH)PO{sub 4} (tarbuttite) were 235.9 J/mol-K and {minus}1604.6 kJ/mol. Additions of sodium sulfite and sulfate did not alter the above reactions.
Date: April 1, 1993
Creator: Ziemniak, S. E. & Opalka, E. P.
Object Type: Report
System: The UNT Digital Library