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  Partner: UNT Libraries Government Documents Department
 Decade: 1980-1989
 Language: English
Acute Toxicity and Bioaccumulation of Chloroform to Four Species of Freshwater Fish

Acute Toxicity and Bioaccumulation of Chloroform to Four Species of Freshwater Fish

Date: August 1, 1980
Creator: ,
Description: Acute toxicity of chloroform to four species of freshwater fish was studied in flow-through 96-hr toxicity tests. Chloroform is toxic to fish in the tens of parts per million, a concentration well above that which would be expected to be produced under normal power plant chlorination conditions. Investigations of acute toxicity of chloroform and the bioaccumulation of chlorinated compounds in tissues of fish revealed differences in tolerance levels and tissue accumulations. Mean 96-hr LC{sub 50}s for chloroform were 18 ppm for rainbow trout and bluegill, 51 ppm for largemouth bass and 75 ppm for channel catfish. Mortalities of bluegill and largemouth bass occurred during the first 4 hr of exposure while rainbow trout and channel catfish showed initial tolerance and mortalities occurred during the latter half of the 96-hr exposure. Rainbow trout had the highest level of chloroform tissue accumulation, 7 {micro}g/g tissue, catfish the second highest, 4 {micro}g/g tissue, followed by bluegill and largemouth bass which each accumulated about 3 {micro}g/g tissue. Accumulation of chloroform was less than one order of magnitude above water concentrations for all species.
Contributing Partner: UNT Libraries Government Documents Department
Chronic Effects of Chlorination By-Products on Rainbow Trout, Salmo gairdneri

Chronic Effects of Chlorination By-Products on Rainbow Trout, Salmo gairdneri

Date: November 1, 1980
Creator: ,
Description: Rainbow trout were exposed to by-products of low-level water chlorination for several months in two separate experiments. In each test 2400 juvenile rainbow trout (Salmo gairdneri) were reared under chlorination conditions designed to simulate those of a power plant. Objectives were to determine effects of long term exposure to provide samples for tissue analysis of chlorination byroducts. No significant difference in fish condition factors was found between the test groups and controls, neither was there an apparent effect on mortality. Background levels of chloroform were found in all fish, but there was no evidence of an increased amount of chloroform or other chlorination by-products resulting from chronic low level exposure to chlorination by-products.
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Mathematical Simulation of Sediment and Radionuclide Transport in Surface Waters

Mathematical Simulation of Sediment and Radionuclide Transport in Surface Waters

Date: April 1, 1981
Creator: ,
Description: The study objective of "The Mathematical Simulation of Sediment and Radionuclide Transport in Surface Waters" is to synthesize and test radionuclide transport models capable of realistically assessing radionuclide transport in various types of surface water bodies by including the sediment-radionuclide interactions. These interactions include radionuclide adsorption by sediment; desorption from sediment into water; and transport, deposition, and resuspension of sorbed radionuclides controlled by the sediment movements. During FY-1979, the modification of sediment and contaminant (radionuclide) transport model, FETRA, was completed to make it applicable to coastal waters. The model is an unsteady, two-dimensional (longitudinal and lateral) model that consists of three submodels (for sediment, dissolved-contaminant, and particulate-contaminant transport), coupled to include the sediment-contaminant interactions. In estuaries, flow phenomena and consequent sediment and radionuclide migration are often three-dimensional in nature mainly because of nonuniform channel cross-sections, salinity intrusion, and lateral-flow circulation. Thus, an unsteady, three-dimensional radionuclide transport model for estuaries is also being synthesized by combining and modifying a PNL unsteady hydrothermal model and FETRA. These two radionuclide transport models for coastal waters and estuaries will be applied to actual sites to examine the validity of the codes.
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A Measurement Control Program for Nuclear Material Accounting

A Measurement Control Program for Nuclear Material Accounting

Date: June 1, 1980
Creator: ,
Description: A measurement control program for nuclear material accounting monitors and controls the quality of the measurements of special nuclear material that are involved in material balances. The quality is monitored by collecting data from which the current precision and accuracy of measurements can be evaluated. The quality is controlled by evaluations, reviews, and other administrative measures for control of selection or design of facilities. equipment and measurement methods and the training and qualification of personnel who perform SNM measurements. This report describes the most important elements of a program by which management can monitor and control measurement quality.
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Monitoring the Random Errors of Nuclear Material Measurements

Monitoring the Random Errors of Nuclear Material Measurements

Date: June 1, 1980
Creator: ,
Description: Monitoring and controlling random errors is an important function of a measurement control program. This report describes the principal sources of random error in the common nuclear material measurement processes and the most important elements of a program for monitoring, evaluating and controlling the random error standard deviations of these processes.
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Training and Qualifying Personnel for Performing Measurements for the Control and Accounting of Special Nuclear Material

Training and Qualifying Personnel for Performing Measurements for the Control and Accounting of Special Nuclear Material

Date: November 1, 1980
Creator: ,
Description: This report presents general procedures for training and qualifying personnel who perform sampling and measurements used for special nuclear material accounting. Considerations for establishing training and qualifying procedures are discussed.
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A Visual Aesthetic Prediction Method for Use in Benefit-Cost Analysis

A Visual Aesthetic Prediction Method for Use in Benefit-Cost Analysis

Date: August 1, 1980
Creator: ,
Description: This report discusses the development of a method to predict landscape visual aesthetic changes caused by the siting of nuclear power plants. The methodology uses public perceptions as a measure of visual aesthetics. Individuals scored landscape photographs on a 0 to 50 visual aesthetic scale. The visual aesthetic scores were explained statistically by landscape characteristics, percent of the scene in clear, still water, and characteristics of the individuals scoring the photographs. Three visual aesthetic relationships were empirically estimated. The first is the relationship among group mean visual aesthetic scores and landscape characteristics. The second is the relationship among individual visual aesthetic scores, landscape characteristics, and the characteristics of the individuals who ranked the landscapes. These relationships were estimated using data from two regions in the U.S. and a diverse set of landscape photographs. The third relationship is among group mean visual aesthetic scores for landscapes with a visible nuclear power plant, landscape characteristics, and mean individual characteristics of the groups who scored the landscapes. This relationship was estimated using data from six regions in the U.S. and landscapes showing nuclear plants with a closed cycle cooling system. The statistical results are highly significant. Prediction validity test results indicate that the ...
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The Idaho Chemical Processing Plant Product Denitrator Upgrade

The Idaho Chemical Processing Plant Product Denitrator Upgrade

Date: May 1, 1982
Creator: /A, N
Description: The upgrade and redesign of a fluidized-bed denitrator for production of uranium trioxide from uranyl nitrate solution is discussed. The success of the project in improving process efficiency and personnel safety is also addressed based on subsequent operation.
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A Demonstration of the Constructibility of a Precast Concrete Stay-in-Place Forming System for Lock Wall Rehabilitation

A Demonstration of the Constructibility of a Precast Concrete Stay-in-Place Forming System for Lock Wall Rehabilitation

Date: December 1987
Creator: ABAM Engineers Incorporated
Description: Report describing a demonstration to evaluate the feasibility of the stay-in-place forming system to rehabilitate damaged lock walls as an alternative to the risk and investment of undertaking full-scale lock rehabilitiation.
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Design of a Precast Concrete Stay-in-Place Forming System for Lock Wall Rehabilitation

Design of a Precast Concrete Stay-in-Place Forming System for Lock Wall Rehabilitation

Date: July 1987
Creator: ABAM Engineers Incorporated
Description: Report describing the design of forming a system to use pre-cast concrete for rehabilitating damaged walls in locks, as a way to prevent problems with cracking in replacement air-entrained concrete used in standard methods.
Contributing Partner: UNT Libraries Government Documents Department
Conceptual Design of a Rapid-Cycling Synchrotron for the KFA-Juelich Spallation Neutron Source

Conceptual Design of a Rapid-Cycling Synchrotron for the KFA-Juelich Spallation Neutron Source

Date: January 1983
Creator: ANL-KFA Study Group
Description: An accelerator group was established at ANL by the request of KFA-Juelich to carry out a conceptual design study and cost estimate for a rapid-cycling synchrotron as a possible first stage program on spallation neutron sources at KFA-Juelich. This set of notes is the individual notes which form the basis of the final report under this proposal prepared in January 1983. This document contains 37 papers/notes for Advanced Accelerator Development - Neutron Source Series Notes...numbered AAD-N-1 through AAD-N-37. Each note or paper is written by various authors.
Contributing Partner: UNT Libraries Government Documents Department
RESIDUAL RADIONUCLIDE DISTRIBUTION AND INVENTORY AT THE DRESDEN UNIT ONE NUCLEAR GENERATING PLANT

RESIDUAL RADIONUCLIDE DISTRIBUTION AND INVENTORY AT THE DRESDEN UNIT ONE NUCLEAR GENERATING PLANT

Date: April 1, 1984
Creator: Abel, K. H.; Robertson, D. E.; Lepel, E. A. & Leale, M. W.
Description: None
Contributing Partner: UNT Libraries Government Documents Department
Optical simulation for imaging reconnaissance and intelligence sensors OSIRIS: High fidelity sensor simulation test bed; Modified user`s manual

Optical simulation for imaging reconnaissance and intelligence sensors OSIRIS: High fidelity sensor simulation test bed; Modified user`s manual

Date: January 4, 1988
Creator: Abernathy, M.F. & Puccetti, M.G.
Description: The OSIRIS program is an imaging optical simulation program which has been developed to predict the output of space-borne sensor systems. The simulation is radiometrically precise and includes highly realistic laser, atmosphere, and earth background models, as well as detailed models of optical components. This system was developed by Rockwell Power Services for the Los Alamos National Laboratory. It is based upon the LARC (Los Alamos Radiometry Code, also by Rockwell), and uses a similar command structure and 3d coordinate system as LARC. At present OSIRIS runs on the Cray I computer under the CTSS operating s stem, and is stored in the OSIRIS root directory on LANL CTSS mass storage.
Contributing Partner: UNT Libraries Government Documents Department
Stressmeter placement at spent fuel test in climax granite

Stressmeter placement at spent fuel test in climax granite

Date: May 20, 1980
Creator: Abey, A.E. & Washington, H.R.
Description: Vibrating wire stressmeters were installed in the Spent Fuel Facility at the Nevada Test Site. These stressmeters will measure the changes in in situ stress during the five-year spent fuel test. Before installation, laboratory tests were conducted to study reproducibility of placement and to develop a program hopefully to reduce corrosion of the stressmeters while in place at the Spent Fuel Facility. These laboratory tests are discussed along with the installation of the stressmeters at the Spent Fuel Facility.
Contributing Partner: UNT Libraries Government Documents Department
Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments

Stress corrosion cracking tests on high-level-waste container materials in simulated tuff repository environments

Date: June 1, 1986
Creator: Abraham, T.; Jain, H. & Soo, P.
Description: Types 304L, 316L, and 321 austenitic stainless steel and Incoloy 825 are being considered as candidate container materials for emplacing high-level waste in a tuff repository. The stress corrosion cracking susceptibility of these materials under simulated tuff repository conditions was evaluated by using the notched C-ring method. The tests were conducted in boiling synthetic groundwater as well as in the steam/air phase above the boiling solutions. All specimens were in contact with crushed Topopah Spring tuff. The investigation showed that microcracks are frequently observed after testing as a result of stress corrosion cracking or intergranular attack. Results showing changes in water chemistry during test are also presented.
Contributing Partner: UNT Libraries Government Documents Department
Effect of gamma radiation on groundwater chemistry and glass leaching as related to the NNWSI repository site

Effect of gamma radiation on groundwater chemistry and glass leaching as related to the NNWSI repository site

Date: May 1986
Creator: Abrajano, T.; Bates, J.; Ebert, W. & Gerding, T.
Description: To address the effect of ionizing radiation on groundwater chemistry and waste form durability, NNWSI is performing an extensive set of experiments as a function of dose rate (2 x 10{sup 5}, 1 x 10{sup 4}, 1 x 10{sup 3}, and 0 rad/h). The results of the tests done at 2 x 10{sup 5} rad/h have been reported, while the 1 x 10{sup 3} and 0 rad/h tests are in progress. This paper presents an overview of the results of the tests done at 1 x 10{sup 4} rad/h and discusses the relevance of these tests to repository conditions. An interpretation of the results relating to the manner by which the glass waste form corrodes is presented elsewhere. A complete discussion of the effect of gamma radiation on groundwater chemistry and waste form durability will be presented when the series of experiments are complete.
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Transport and reaction kinetics at the glass:solution interface region: Results of repository-oriented leaching experiments

Transport and reaction kinetics at the glass:solution interface region: Results of repository-oriented leaching experiments

Date: December 31, 1986
Creator: Abrajano, T.A. Jr. & Bates, J.K.
Description: Repository-oriented leaching experiments involving Savannah River Laboratory (SRL) 165 type glass under a {gamma}-radiation field (1 = 0.2 x 10{sup 4} R/h) have been performed by the Nevada Nuclear Waste Storage Investigations (NNWSI) project. In this communication, we discuss glass surface analyses obtained by SEM, nuclear resonance profiling, and SIMS together with leachate solution data in relation to a mechanism that couples diffusion, hydrolysis (etching and gelation), and precipitation to qualitatively describe the release of different glass components to the leachant solutions. The release of mobile (e.g., Li) and partly mobile (e.g., B) species is controlled primarily by interdiffusion with water species across the interdiffusion zone. Glass components that are immobile in the interdiffusion zone are released to the solution by etching. For prediction of long-term steady-state concentrations of glass components with low solubility, the relative rates of release from the glass and secondary mineral precipitation must be taken into account.
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The reaction of glass during gamma irradiation in a saturated tuff environment: Part 3, long-term experiments at 1 x 10{sup 4}rad/hour

The reaction of glass during gamma irradiation in a saturated tuff environment: Part 3, long-term experiments at 1 x 10{sup 4}rad/hour

Date: February 1, 1988
Creator: Abrajano, T.A. Jr.; Bates, J.K.; Gerding, T.J. & Ebert, W.L.
Description: Savannah River Laboratory 165 type glass was leached with equilibrated J-13 groundwater at 90{degree}C for times up to 182 days. These experiments were performed as part of an effort by the Nevada Nuclear Waste Storage Investigations Project to assess the importance of radiation effects on repository performance and waste glass corrosion. The gamma radiation field used in this work was 1. 0 +- 0.2 x 10{sup 4} rad/h. Glass dissolution is notably incongruent throughout the entire experimental periods and normalized releases follow the sequence Li {ge} Na {ge} B {approx_equal} U {ge} Si. The normalized leach rates of these elements, as well as the measured growth rates of the reaction layers, decreased with time. The only significant variation observed in the abundance of anions is the systematic decrease in NO{sub 3}/sup {minus}//NO{sub 2}/sup {minus}/ ratio from the starting EJ-13 groundwater to the EJ-13 blank experiments to the tuff- and glass-containing experiments. A leaching model that is consistent with the observed solution data and depth profiles is presented. The applicability and limitation of the present results in predicting the actual interactions that may occur in the NNWSI repository are discussed. 35 refs., 30 figs., 12 tabs.
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Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment, Part 3: Long-Term Experiments at 1x10^4 Rad/Hour

Reaction of Glass During Gamma Irradiation in a Saturated Tuff Environment, Part 3: Long-Term Experiments at 1x10^4 Rad/Hour

Date: February 1988
Creator: Abrajano, Teofilo Aniag; Bates, John K.; Gerding, Thomas J. & Ebert, William L.
Description: Report on experiments to assess the importance of radiation effects on waste glass corrosion. This third part contains a description of the experiments, results, and discussion, with conclusions and related appendices.
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Sodium Waste Technology : a Summary Report

Sodium Waste Technology : a Summary Report

Date: January 1987
Creator: Abrams, C. S. & Witbeck, L. C.
Description: The Sodium Waste Technology (SWT) Program was established to resolve long-standing issues regarding disposal of sodium-bearing waste and equipment. Comprehensive SWT research programs investigated a variety of approaches for either removing sodium from sodium-bearing items, or disposal of items containing sodium residuals. The most successful of these programs was the design, test, and the production operation of the Sodium Process Demonstration Facility at ANL-W. The technology used was a series of melt-drain-evaporate operations to remove nonradioactive sodium from sodium-bearing items and then converting the sodium to storable compounds.
Contributing Partner: UNT Libraries Government Documents Department
MEASUREMENTS OF THE PROPERTIES OF D MESON DECAYS

MEASUREMENTS OF THE PROPERTIES OF D MESON DECAYS

Date: May 1, 1980
Creator: Abrams, G.; Blocker, C.A.; Blondel, A.; Carithers, W.C.; Chinowsky, W.; Coles, M.W. et al.
Description: We present a study of the decay properties of charmed D mesons produced near the peak of the {psi}" (3770) resonance in e{sup +}e{sup -} annihilation. Branching fractions for nine Cabibbo-favored and three Cabibbo-suppressed decay modes are presented along with upper limits on one additional Cabibbo-favored and four additional Cabibbo-suppressed decay modes. A study of K{pi}{pi} decay mode Dalitz plots reveals a large quasi-two-body pseudoscalar-vector component for the D{sup 0} decays and an apparent nonuniform population an the Dalitz plot for the D{sup +} decay into K{sup -}{pi}{sup +}{pi}{sup +}. Using tagged events, we measure the charged particle multiplicity and strange particle content of D decays. A measurement of the D{sup +} and D{sup 0} semileptonic decay fractions indicates that the D{sup +} has a significantly longer lifetime than the D{sup 0}.
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PERFORMANCE OF THE LEAD/LIQUID ARGON SHOWER COUNTER SYSTEM OF THE MARK II DETECTOR AT SPEAR

PERFORMANCE OF THE LEAD/LIQUID ARGON SHOWER COUNTER SYSTEM OF THE MARK II DETECTOR AT SPEAR

Date: May 1, 1980
Creator: Abrams, G.S.; Blocker, C.A.; Briggs, D.D.; Carithers, W.C.; Dieterle, W.E.; Eaton, M.W. et al.
Description: The shower counter system of the SLAC-LBL Mark II detector is a large lead/liquid argon system of the type pioneered by Willis and Radekal; however, it differs in most details and is much larger than other such detectors currently in operation, It contains, for example, 8000 liters of liquid argon and 3000 channels of low noise electronics, which is about eight times the size of the system of Willis et al. in the CERN ISR. This paper reports, with little reference to design, on the operation and performance of the Mark II system during approximately a year and a half of operation at the Stanford Linear Accelerator Center's e{sup +}-e{sup -} facility, SPEAR. The design and construction of the system have previously been described and a detailed discussion of all aspects -- design, construction, operation, and performance -- is in preparation.
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Tritium distribution in the MHTGR

Tritium distribution in the MHTGR

Date: May 1, 1988
Creator: Acharya, R.
Description: The {sup 3}H production, transport and environmental release from the 350 MW(t) Modular High Temperature Gas Cooled Reactor was analyzed. The analysis was performed using a modified TRITGO computer code, plant data base from the Preliminary Safety Information Document and materials property data from the Fuel Design Data Manual, Issue F. The analysis indicates that most of the {sup 3}H produced in the reactor is retained by the fuel particles and the structural graphite elements. The single largest source of {sup 3}H is ternary fission in the fuel particles, of which 95% is retained by the particles. The {sup 3}H released from the core and the {sup 3}H produced by {sup 3}He activation are largely removed by the Helium Purification System. Assuming zero leakage of water from the secondary system, the average predicted {sup 3}H activity in the secondary water of 0.35 {mu}Ci/g is much greater than the allowable activity of 5 pCi/g for direct discharge into the environment. If any of the secondary water has to be discharged, it must be diluted prior to discharge. 10 refs., 9 figs.
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Fission product plateout/liftoff/washoff test plan. Revision 1

Fission product plateout/liftoff/washoff test plan. Revision 1

Date: May 1, 1988
Creator: Acharya, R. & Hanson, D.
Description: A test program is planned in the COMEDIE loop of the Commissariat a l`Energy Atomique (CEA), Grenoble, France, to generate integral test data for the validation of computer codes used to predict fission product transport and core corrosion in the Modular High Temperature Gas-Cooled Reactor (MHTGR). The inpile testing will be performed by the CEA under contract from the US Department of Energy (DOE); the contract will be administered by Oak Ridge National Laboratory (ORNL). The primary purpose of this test plan is to provide an overview of the proposed program in terms of the overall scope and schedule. 8 refs, 3 figs.
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