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Thermochemical Investigations of Nearly Ideal Binary Solvents. 6. Solubilities of Iodine and Benzil in Systems of Nonspecific Interactions (open access)

Thermochemical Investigations of Nearly Ideal Binary Solvents. 6. Solubilities of Iodine and Benzil in Systems of Nonspecific Interactions

Article on thermochemical investigations of nearly ideal binary solvents and the solubilities of iodine and benzil in systems of nonspecific interactions.
Date: February 1, 1983
Creator: Acree, William E. (William Eugene) & Bertrand, Gary L.
Object Type: Article
System: The UNT Digital Library
Pawhuska Daily Journal-Capital (Pawhuska, Okla.), Vol. 74, No. 22, Ed. 1 Tuesday, February 1, 1983 (open access)

Pawhuska Daily Journal-Capital (Pawhuska, Okla.), Vol. 74, No. 22, Ed. 1 Tuesday, February 1, 1983

Daily newspaper from Pawhuska, Oklahoma that includes local, state, and national news along with advertising.
Date: February 1, 1983
Creator: Adams, Bill
Object Type: Newspaper
System: The Gateway to Oklahoma History

[Photograph 2012.201.B1182.0699]

Photograph used for a story in the Oklahoma Times newspaper. Caption: "A basket quickly takes form in the hands of fourth grader Crag L. Smith."
Date: February 1, 1983
Creator: Albright, Bob
Object Type: Photograph
System: The Gateway to Oklahoma History
Microwave energy storage in resonant cavities (open access)

Microwave energy storage in resonant cavities

One method of generating short, high-power microwave pulses is to store rf energy in a resonant cavity over a relatively long fill time and extract is rapidly. A power gain roughly equal to the ratio of fill time to extraction time can be obtained. During the filling of a resonant cavity some of the energy is lost in heating the cavity walls, and some will generally be reflected at the input coupling of the cavity. In this paper we discuss the time dependence of the stored energy and related quantities and the way in which it depends on the coupling of the source to the cavity.
Date: February 1, 1983
Creator: Alvarez, Raymond A.
Object Type: Report
System: The UNT Digital Library
Guidelines for nuclear-power-plant safety-issue-prioritization information development (open access)

Guidelines for nuclear-power-plant safety-issue-prioritization information development

Pacific Northwest Laboratory has developed a methodology, with examples, to calculate - to an approximation serviceable for prioritization purposes - the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report is an applications guide to issue-specific calculations. A description of the approach, mathematical models, worksheets and step-by-step examples are provided. Analysis using this method is intended to provide comparable results for many issues at a cost of two staff-weeks per issue. Results will be used by the NRC to support decisions related to issue priorities in allocation of resources to complete safety issue resolutions.
Date: February 1, 1983
Creator: Andrews, W.B.; Gallucci, R.H.V.; Heaberlin, S.W.; Bickford, W.E.; Konzek, G.J.; Strenge, D.L. et al.
Object Type: Report
System: The UNT Digital Library

[Photograph 2012.201.B1030.0445]

Photograph used for a story in the Oklahoma Times newspaper. Caption: "Kay Precure, left, and Shirley Harris check out local fashions."
Date: February 1, 1983
Creator: Argo, Jim
Object Type: Photograph
System: The Gateway to Oklahoma History
Pacific Northwest Laboratory annual report for 1982 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. Part 5. Environmental and occupational protection, assessment, and engineering (open access)

Pacific Northwest Laboratory annual report for 1982 to the DOE Office of the Assistant Secretary for Environmental Protection, Safety and Emergency Preparedness. Part 5. Environmental and occupational protection, assessment, and engineering

Part 5 of the 1982 Annual Report to the Department of Energy's Office of Environmental Protection, Safety and Emergency Preparedness presents Pacific Northwest Laboratory's progress on work performed for the Office of Environmental Programs, Office of Operational Safety, and the Office of Nuclear Safety. The report is in three sections, introduced by blue divider pages, corresponding to the program elements: Technology Impacts, Environmental and Safety Engineering, Operational and Environmental Safety. In each section, articles describe progress made during FY 1982 on individual projects, as identified by the Field Task Proposal/Agreement. Authors of these articles represent a broad spectrum of capabilities derived from various segments of the Laboratory, reflecting the interdisciplinary nature of the work.
Date: February 1, 1983
Creator: Bair, W.J.
Object Type: Report
System: The UNT Digital Library
Magnetoresistance, electrical conductivity, and Hall effect of glassy carbon (open access)

Magnetoresistance, electrical conductivity, and Hall effect of glassy carbon

These properties of glassy carbon heat treated for three hours between 1200 and 2700/sup 0/C were measured from 3 to 300/sup 0/K in magnetic fields up to 5 tesla. The magnetoresistance was generally negative and saturated with reciprocal temperature, but still increased as a function of magnetic field. The maximum negative magnetoresistance measured was 2.2% for 2700/sup 0/C material. Several models based on the negative magnetoresistance being proportional to the square of the magnetic moment were attempted; the best fit was obtained for the simplest model combining Curie and Pauli paramagnetism for heat treatments above 1600/sup 0/C. Positive magnetoresistance was found only in less than 1600/sup 0/C treated glassy carbon. The electrical conductivity, of the order of 200 (ohm-cm)/sup -1/ at room temperature, can be empirically written as sigma = A + Bexp(-CT/sup -1/4) - DT/sup -1/2. The Hall coefficient was independent of magnetic field, insensitive to temperature, but was a strong function of heat treatment temperature, crossing over from negative to positive at about 1700/sup 0/C and ranging from -0.048 to 0.126 cm/sup 3//coul. The idea of one-dimensional filaments in glassy carbon suggested by the electrical conductivity is compatible with the present consensus view of the microstructure.
Date: February 1, 1983
Creator: Baker, D.F.
Object Type: Report
System: The UNT Digital Library
Handling encapsulated spent fuel in a geologic repository environment (open access)

Handling encapsulated spent fuel in a geologic repository environment

In support of the Spent Fuel Test-Climate at the U.S. Department of Energy`s Nevada Test Site, a spent-fuel canister handling system has been designed, deployed, and operated successfully during the past five years. This system transports encapsulated commercial spent-fuel assemblies between the packaging facility and the test site ({similar_to}100 km), transfers the canisters 420 m vertically to and from a geologic storage drift, and emplaces or retrieves the canisters from the storage holes in the floor of the drift. The spent-fuel canisters are maintained in a fully shielded configuration at all times during the handling cycle, permitting manned access at any time for response to any abnormal conditions. All normal operations are conducted by remote control, thus assuring as low as reasonably achievable exposures to operators; specifically, we have had no measurable exposure during 30 canister transfer operations. While not intended to be prototypical of repository handling operations, the system embodies a number of concepts, now demonstrated to be safe, reliable, and economical, which may be very useful in evaluating full-scale repository handling alternatives in the future. Among the potentially significant concepts are: Use of an integral shielding plug to minimize radiation streaming at all transfer interfaces. Hydraulically actuated transfer …
Date: February 1, 1983
Creator: Ballou, L. B.
Object Type: Article
System: The UNT Digital Library
Reduction in airborne contamination levels at the 9201-5 Arc Melt sawing operation. A Y-12 Plant 1982 ALARA goal (open access)

Reduction in airborne contamination levels at the 9201-5 Arc Melt sawing operation. A Y-12 Plant 1982 ALARA goal

Lowering the uranium airborne contamination level at the two saws in the 9201-5 Arc Melt Area was chosen as a Y-12 Plant As-Low-As-Reasonably-Achievable (ALARA) goal for 1982. This priority was convincingly communicated to those involving by giving specific instructions to suspend saw operations any time there was evidence of a problem until that problem could be corrected. Using control charts on air flow rates into the saw enclosures and pressure drops across filters in the saw ventilation (Delta Phase I) exhaust system, it was possible to decide when filter changes or other adjustments were necessary to maintain the exhaust flow rates needed for improved airborne contamination control. The keeping of these charts, along with the actions taken on the basis of the data gathered, made it possible to meet the goal of reducing airborne contamination levels in 1982, as compared with 1981, although production in the Arc Melt Area increased significantly. These data also showed that use of one brand of filter in the prefilter system resulted in the need to change filters more frequently than when another brand was used. This fact triggered an investigation which revealed the cause for the shorter useful life of that filter and a …
Date: February 1, 1983
Creator: Beck, D.E. & West, C.M.
Object Type: Report
System: The UNT Digital Library

[Photograph 2012.201.B1215.1045]

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "A lone car passes a road plow on the snowy U.S. 60 just west of Tonkawa Tuesday."
Date: February 1, 1983
Creator: Beckel, Jim
Object Type: Photograph
System: The Gateway to Oklahoma History
Analysis and Thermal-Design Improvements of Downhole Tools for Use in Hot-Dry Wells (open access)

Analysis and Thermal-Design Improvements of Downhole Tools for Use in Hot-Dry Wells

Design improvements made for downhole thermal protection of systems based on results obtained from the analysis of the electronics, heat sink, and dewar packaged in a steel tubular body are described. Results include heat flux at the tool surface, temperature-time histories of each subsystem and isotherm contour plots during the simulation. The analysis showed that the thermal potential between the electronics and the heat sink was in the wrong direction and also was too small to remove heat entering the electronics section. Also, the conductance of the available heat transfer paths from electronics to heat sink was too small to remove that heat efficiently. Significant improvements in survival at high temperatures were achieved by increasing the available thermal capacity of the heat sink, increasing the thermal potential between the heat sink and electronics, and vastly increasing the conductance of the heat transfer paths.
Date: February 1, 1983
Creator: Bennett, G. A. & Sherman, G. R.
Object Type: Report
System: The UNT Digital Library
SERI biomass program annual technical report: 1982 (open access)

SERI biomass program annual technical report: 1982

The biomass with which this report is concerned includes aquatic plants, which can be converted into liquid fuels and chemicals; organic wastes (crop residues as well as animal and municipal wastes), from which biogas can be produced via anerobic digestion; and organic or inorganic waste streams, from which hydrogen can be produced by photobiological processes. The Biomass Program Office supports research in three areas which, although distinct, all use living organisms to create the desired products. The Aquatic Species Program (ASP) supports research on organisms that are themselves processed into the final products, while the Anaerobic Digestion (ADP) and Photo/Biological Hydrogen Program (P/BHP) deals with organisms that transform waste streams into energy products. The P/BHP is also investigating systems using water as a feedstock and cell-free systems which do not utilize living organisms. This report summarizes the progress and research accomplishments of the SERI Biomass Program during FY 1982.
Date: February 1, 1983
Creator: Bergeron, P.W.; Corder, R.E.; Hill, A.M.; Lindsey, H. & Lowenstein, M.Z.
Object Type: Report
System: The UNT Digital Library
Existing experimental criticality data applicable to nuclear-fuel-transportation systems (open access)

Existing experimental criticality data applicable to nuclear-fuel-transportation systems

Analytical techniques are generally relied upon in making criticality evaluations involving nuclear material outside reactors. For these evaluations to be accepted the calculations must be validated by comparison with experimental data for a known set of conditions having physical and neutronic characteristics similar to those conditions being evaluated analytically. The purpose of this report is to identify those existing experimental data that are suitable for use in verifying criticality calculations on nuclear fuel transportation systems. In addition, near term needs for additional data in this area are identified. Of the considerable amount of criticality data currently existing, that are applicable to non-reactor systems, those particularly suitable for use in support of nuclear material transportation systems have been identified and catalogued into the following groups: (1) critical assemblies of fuel rods in water; (2) critical assemblies of fuel rods in water containing soluble neutron absorbers; (3) critical assemblies containing solid neutron absorber; (4) critical assemblies of fuel rods in water with heavy metal reflectors; and (5) critical assemblies of fuel rods in water with irregular features. A listing of the current near term needs for additional data in each of the groups has been developed for future use in planning criticality …
Date: February 1, 1983
Creator: Bierman, S.R.
Object Type: Report
System: The UNT Digital Library
SURE: a system of computer codes for performing sensitivity/uncertainty analyses with the RELAP code. [PWR] (open access)

SURE: a system of computer codes for performing sensitivity/uncertainty analyses with the RELAP code. [PWR]

A package of computer codes has been developed to perform a nonlinear uncertainty analysis on transient thermal-hydraulic systems which are modeled with the RELAP computer code. Using an uncertainty around the analyses of experiments in the PWR-BDHT Separate Effects Program at Oak Ridge National Laboratory. The use of FORTRAN programs running interactively on the PDP-10 computer has made the system very easy to use and provided great flexibility in the choice of processing paths. Several experiments simulating a loss-of-coolant accident in a nuclear reactor have been successfully analyzed. It has been shown that the system can be automated easily to further simplify its use and that the conversion of the entire system to a base code other than RELAP is possible.
Date: February 1, 1983
Creator: Bjerke, M.A.
Object Type: Report
System: The UNT Digital Library
HEAVY-ION RADIOBIOLOGY: CELLULAR STUDIES (open access)

HEAVY-ION RADIOBIOLOGY: CELLULAR STUDIES

The effects of accelerated heavy charged particles on cellular systems in vitro are reviewed and physical characteristics and beam monitoring and dosimetry are briefly described.
Date: February 1, 1983
Creator: Blakely, Eleanor A.; Ngo, Frank Q.H.; Curtis, Stanley B. & Tobias, Cornelius A.
Object Type: Article
System: The UNT Digital Library
Three-Dimensional Stellarator Equilibria by Iteration (open access)

Three-Dimensional Stellarator Equilibria by Iteration

The iterative method of evaluating plasma equilibria is especially simple in a magnetic coordinate representation. This method is particularly useful for clarifying the subtle constraints of three-dimensional equilibria and studying magnetic surface breakup at high plasma beta.
Date: February 1, 1983
Creator: Boozer, Allen H.
Object Type: Report
System: The UNT Digital Library
Flight-systems safety program, September 1982. Progress report (open access)

Flight-systems safety program, September 1982. Progress report

This technical monthly report covers studies related to the use of /sup 238/PuO/sub 2/ in radioisotope power systems carried out for the Office of Space Nuclear Projects of the US Department of Energy by Los Alamos National Laboratory. Most of the studies discussed here are ongoing. Results and conclusions described may change as the work continues.
Date: February 1, 1983
Creator: Bronisz, S. E.
Object Type: Report
System: The UNT Digital Library
The Baytown Sun (Baytown, Tex.), Vol. 61, No. 079, Ed. 1 Tuesday, February 1, 1983 (open access)

The Baytown Sun (Baytown, Tex.), Vol. 61, No. 079, Ed. 1 Tuesday, February 1, 1983

Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.
Date: February 1, 1983
Creator: Brown, Leon
Object Type: Newspaper
System: The Portal to Texas History
FFTF reactor-characterization program: gamma-ray measurements and shield characterization (open access)

FFTF reactor-characterization program: gamma-ray measurements and shield characterization

A series of experiments is to be made during the acceptance test program of the Fast Flux Test Facility (FFTF) to measure the gamma ray characteristics of the Fast Test Reactor (FTR) and to establish the performance characteristics of the reactor shield. These measurements are a part of the FFTF Reactor Characterization Program (RCP). Detailed plans have been developed for these experiments. During the initial phase of the Characteristics Program, which will be carried out in the In-Reactor Thimble (IRT), both active and passive measurement methods will be employed to obtain as much information concerning the gamma ray environment as is practical. More limited active gamma ray measurements also will be made in the Vibration Open Test Assembly (VOTA).
Date: February 1, 1983
Creator: Bunch, W. L. & Moore, Jr., F. S.
Object Type: Report
System: The UNT Digital Library
Decays of /sup 22/Al and /sup 26/P: discovery of beta-delayed two-proton radioactivity (open access)

Decays of /sup 22/Al and /sup 26/P: discovery of beta-delayed two-proton radioactivity

A helium-jet system and the /sup 24/Mg(/sup 3/He,p4n)/sup 22/Al and /sup 28/Si(/sup 3/He,p4n)/sup 26/P reactions have been used to discover the only known odd-odd, T/sub Z/ = -2 nuclides, /sup 22/Al(t/sub 1/2/ approx. 70ms) and /sup 26/P(t/sub 1/2/ approx. 20 ms). Observations of beta-delayed protons from each isotope (laboratory energies 7.839 +- 0.015 MeV and 8.149 +- 0.021 MeV for /sup 22/Al and 7.269 +- 0.015 MeV and 6.827 +- 0.050 MeV for /sup 26/P) established the existence of these nuclides and provided a measurement of the mass excesses of the lowest T = 2 states in their beta decay daughters, /sup 22/Mg and /sup 26/Si (13.650 +- 0.015 MeV and 5.936 +- 0.015 MeV, respectively). Measurement of these masses confirmed that these T = 2 states were unbound to two-proton emission as had been predicted theoretically.
Date: February 1, 1983
Creator: Cable, M.D.
Object Type: Report
System: The UNT Digital Library
Representative well models for eight geothermal-resource areas (open access)

Representative well models for eight geothermal-resource areas

Representative well models have been constructed for eight major geothermal-resource areas. The models define representative times and costs associated with the individual operations that can be expected during drilling and completion of geothermal wells. The models were made for and have been used to evaluate the impacts of potential new technologies. The nature, construction, and validation of the models are presented.
Date: February 1, 1983
Creator: Carson, C. C.; Lin, Y. T. & Livesay, B. J.
Object Type: Report
System: The UNT Digital Library
Reduction of recycling by pumping at the PDX limiter (open access)

Reduction of recycling by pumping at the PDX limiter

We have installed two arrays of Zr-Al getters adjacent to the PDX limiter to affect the pumping of neutrals formed in this region. The projected area of the getters is approximately 0.4% of the plasma area, and the measured H/sub 2/ pumping speed is 16,000 l/sec. During ohmic discharges, the getters reduced the electron density decay time from 340 to 180 msec. This result, combined with H/sub ..cap alpha..'/ data indicates that the recycling coefficient decreases by 10% or more.
Date: February 1, 1983
Creator: Cecchi, J. L.; Knize, R. J.; Dylla, H. F.; Fonck, R. J.; Owens, D. K. & Sredniawski, J. J.
Object Type: Report
System: The UNT Digital Library
Beam-shape distortion caused by transverse wake fields (open access)

Beam-shape distortion caused by transverse wake fields

As a particle bunch in a storage ring passes through a region with a transverse impedance, it generates a transverse wake electromagnetic field that is proportional to the transverse displacement of the bunch in the region. The field acts back on the bunch, causing various effects (such as instabilities) in the motion of the bunch. We study one such effect in which a transverse impedance causes the beam to be distorted in its shape. Observed at a fixed location in the storage ring, this distortion does not change from turn to turn; rather, the distortion is static in time. To describe the distortion, the bunch is considered to be divided longitudinally into many slices and the centers of change of the slices are connected into a curve. In the absence of transverse impedance, this curve is a straight line parallel to the direction of motion of the bunch. Perturbed by the transverse wake field, the curve becomes distorted. What we find in this paper is the shape of such a curve. The results obtained are applied to the PEP storage ring. The impedance is assumed to come solely from the rf cavities. We find that the beam shape is sufficiently …
Date: February 1, 1983
Creator: Chao, A.W. & Kheifets, S.
Object Type: Article
System: The UNT Digital Library