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Estimates of the number of large amplitude gusts (open access)

Estimates of the number of large amplitude gusts

Preliminary estimates are presented of the number of occurrences of large amplitude gusts for use in the design of wind energy conversion systems. Existing turbulence information has been combined with an assumed wind speed distribution to arrive at the estimates. The number of large amplitude gusts per year is treated as a function of the annual mean wind speed and terrain roughness. This treatment is based upon the assumptions that the atmosphere has neutral stability during high winds and that the gustiness is induced by flow over surface roughness elements. Large gusts during thunderstorms and other severe weather phenomena are not treated. The results of the study are presented in tabular form as a function of gust amplitude and hourly average wind speed.
Date: March 1, 1978
Creator: Ramsdell, J.V.
Object Type: Report
System: The UNT Digital Library
Preliminary study of the favorability for uranium in the Madera Limestone, and Cutler and Chinle Formations of the Sierra Nacimiento-Jemez Mountains area, New Mexico (open access)

Preliminary study of the favorability for uranium in the Madera Limestone, and Cutler and Chinle Formations of the Sierra Nacimiento-Jemez Mountains area, New Mexico

Small, surficial, secondary uranium deposits are present in several formations in the Sierra Nacimiento-Jemez Mountains region, but none of significant size are known. Field surveys indicate that the deposits are laterally discontinuous and are, in most cases, associated with carbonaceous debris. Mineral contents of as much as 0.18 percent U/sub 3/O/sub 8/ are recorded. There are 2 known deposits in the Pennsylvanian Madera Limestone, 18 in the Permian Cutler Formation, and 3 in the Triassic Chinle Formation. The Madera Limestone consists of a lower and an upper member. The lower member is predominantly a dense limestone and is lithologically unfavorable. The upper member, which consists of several arkosic units interbedded with cherty limestone, is not a favorable host rock because of its thin arkosic units, the paucity of carbonaceous debris, and its lithologically unfavorable limestone. The Cutler Formation consists mostly of interfingering siltstones and fine- to coarse-grained feldspathic and arkosic sandstones of fluvial origin. The sandstones are generally lenticular, average about 40 ft in thickness, and are favorable. Cutler equivalents south of lat 36/sup 0/ N. (Abo and Yeso Formations) were not included in this study. The Chinle Formation in the project area consists of five members. The Agua Zarca …
Date: January 1, 1978
Creator: Vizcaino, H. P.; O'Neill, A. J. & Dotterer, F. E.
Object Type: Report
System: The UNT Digital Library
Only source of energy (open access)

Only source of energy

Various plants that might play a role in the energy mix of the future are discussed and illustrated. Included among them are the Euphorbias and Guayule. (JGB)
Date: March 22, 1978
Creator: Calvin, G. J. & Calvin, M.
Object Type: Report
System: The UNT Digital Library
Elastic and Plastic Strains and the Stress Corrosion Cracking of Austenitic Stainless Steels. Progress Report, April 30, 1977--December 30, 1977 (open access)

Elastic and Plastic Strains and the Stress Corrosion Cracking of Austenitic Stainless Steels. Progress Report, April 30, 1977--December 30, 1977

A newly developed test environment based on NaCl, Na/sub 2/SO/sub 4/, and HCl has provided some insight to several aspects of SCC in a transformable austenitic stainless steel. Current vs. time curves indicated the presence of the formation of a ''protective'' film which drastically reduced the anodic current leading to failure. This film, not indicated by the polarization curves, is subject to highly localized damage such as pitting. Thus, although it allows only very small corrosion currents, it is not truly protective. Hence, it is pseudo-passive. The critical cracking potential did not exhibit any difference between the annealed and the maximum (25%) deformation examined. The corrosion or open circuit potential for both annealed and deformed material behaved in a similar manner, becoming more noble with time until it reached the critical cracking potential and SCC ensured. The failure time for the deformed specimens was substantially shorter than for the annealed ones, but the incubation time was essentially the same. Within the range of experimental conditions examined thus far, it appears that the critical parameters leading to SCC in a chloride environment are primarily dependent on surface-environment interactions and not dependent on the bulk properties.
Date: January 1, 1978
Creator: Troiano, A. R.
Object Type: Report
System: The UNT Digital Library
D/sup -/ production by multiple charge-transfer collisions of low-energy D ions and atoms in cesium vapor (open access)

D/sup -/ production by multiple charge-transfer collisions of low-energy D ions and atoms in cesium vapor

The production of D/sup -/ by multiple charge-transfer collisions of a D/sup +/ beam in a cesium-vapor target is considered for D/sup +/ energies above 300 eV. The cross sections relevant to D/sup -/ formation are obtained by a least-squares fit of three-charge-state differential equations to experimental yield curves. Implications for production of intense negative-ion beams are discussed, and speculations are made about extrapolation to lower engeries.
Date: January 22, 1978
Creator: Hooper, E. B. Jr.; Willmann, P. A. & Schlachter, A. S.
Object Type: Report
System: The UNT Digital Library
Resonant decay of finite extent cold electron plasma waves (open access)

Resonant decay of finite extent cold electron plasma waves

The parametric decay of a finite extent cold electron plasma wave (slow wave) was studied experimentally. Using a frequency of ..omega../sub 0/ approximately greater than 10..omega../sub pi/, it was found that the decay waves propagated along the pump wave rather than in the Vector E/sub 0/ x Vector B direction. This is in agreement with the recent theoretical predictions of finite length stabilization.
Date: February 1, 1978
Creator: Wong, K. L.; Bellan, P. & Porkolab, M.
Object Type: Report
System: The UNT Digital Library
LOFT system structural response during subcooled blowdown (open access)

LOFT system structural response during subcooled blowdown

The Loss-of-Fluid Test (LOFT) facility is a highly instrumented, pressurized water reactor test system designed to be representative of large pressurized water reactors (LPWRs) for the simulation of loss-of-coolant accidents (LOCAs). Detailed structural analysis and appropriate instrumentation (accelerometers and strain gages) on the LOFT system provided information for evaluation of the structural response of the LOFT facility for loss-of-coolant experiment (LOCE) induced loads. In general, the response of the system during subcooled blowdown was small with typical structural accelerations below 2.0 G's and dynamic strains less than 150 x 10/sup -/6 m/m. The accelerations measured at the steam generator and simulated steam generator flange exceeded LOCE design values; however, integration of the accelerometer data at these locations yielded displacements which were less than one half of the design values associated with a safe shutdown earthquake (SSE), which assures structural integrity for LOCE loads. The existing measurement system was adequate for evaluation of the LOFT system response during the LOCEs. The conditions affecting blowdown loads during nuclear LOCEs will be nearly the same as those experienced during the nonnuclear LOCEs, and the characteristics of the structural response data in both types of experiments are expected to be the same. The LOFT …
Date: January 1, 1978
Creator: Martinell, J. S.
Object Type: Report
System: The UNT Digital Library
Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR] (open access)

Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR]

The behavior of the fission metal cesium and the fission gases krypton and xenon in the Saclay Spitfire Loop SSL-1 test has been compared to that predicted using General Atomic reference data and computer code models. This is the first in a series of analyses planned in order to provide quantitative validation of HTGR fission product design methods. In this analysis, the first attempt to rigorously verify fission product design methods, the FIPERQ code was used to model the diffusion of cesium graphite and release to the coolant stream. The comparisons showed that the cesium profile shape in the graphite web and the partition coefficient between fuel rod matrix material and fuel element graphite were correctly modeled, although the overall release was significantly underpredicted. Uncertainties in the source term (fissile particle failure fraction) and total release to the coolant precluded an accurate appraisal of the validity of FIPERQ. However, several recommendations are presented to improve the applicability of future in-pile test data for the validation of fission metal release codes. The half-life dependence of fission gas release during irradiation was found to be in good agreement with the model used in the reference design materials, providing assurance that this aspect …
Date: February 1, 1978
Creator: Jensen, D. D.; Haire, M. J. & Ballagny, A.
Object Type: Report
System: The UNT Digital Library
Nuclear magnetic resonance study of metallic scandium chlorides (open access)

Nuclear magnetic resonance study of metallic scandium chlorides

The /sup 45/Sc nuclear magnetic resonance was studied in samples having the general composition CsSc/sub x/Cl/sub 3/ (0.67 less than or equal to x less than or equal to 1.0) in the CsCl-ScCl/sub 3/-Sc system. In particular the structure of CsScCl/sub 3/ suggests that it may be a one-dimensional conductor, and an attempt was therefore made to detect the occurrence of a metal-insulator transition of the type characteristic of one-dimensional conductors. Conventional crossed-coil (nuclear induction) techniques were employed. The /sup 45/Sc resonance was studied over a wide frequency range (4 to 24 MHz) at 300K, these measurements yielding the Knight shift and nuclear electric quadrupole coupling parameters. No significant variation in the spectra occurred from 4.2K to 450K, indicating the absence of a metal-insulator transition in this temperature range.
Date: April 1, 1978
Creator: McMullen, T.P.
Object Type: Report
System: The UNT Digital Library
Western Gas Sands Project. Quarterly basin activities report (open access)

Western Gas Sands Project. Quarterly basin activities report

A summation of information is presented on geology and drilling activity in the four primary study areas of the Western Gas Sands Project. The areas of interest are the Greater Green River Basin, the Piceance Basin, the Uinta Basin, and the Northern Great Plains Province. Drilling activity is discussed for the months of October, November, and December, 1977, with the major emphasis on wells located in low permeability sandstone areas, having significant gas production and utilizing hydraulic fracturing treatments. The drilling information was obtained primarily from ''The Rocky Mountain Region Report'' published by Petroleum Information Corporation on a daily basis. Another source of information was the ''Montana Oil and Gas Journal'' which is released weekly.
Date: January 1, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Thermo-chemical energy conversion and storage. Final report (open access)

Thermo-chemical energy conversion and storage. Final report

Research support for the cyclohexane/benzene heat pipe development program at Sandia Laboratories is reported. The apparent kinetics of the gas-phase catalytic dehydrogenation of cyclohexane to benzene in an internally recirculated (gradientless) reactor over the temperature range from 500 to 800/sup 0/F at 1 atm at various space velocities was studied. A kinetic model was developed based on a reversible mass-action rate expression and a catalyst effectiveness factor which is able to correlate both the conversion and reaction rate data very well over the temperature range 500 to 750/sup 0/F. The data taken at 800/sup 0/F appear to be qualitatively and quantitatively different than the data taken at the lower temperatures. It is not as yet clear, whether this can be attributed to a change in kinetic mechanism or some reversible alteration of the catalyst surface at the higher temperature. The formation of side products in this system over the same temperature range was also studied. Both the number and amount of side product(s) formed increases with increasing temperature and residence time. Over the temperature range from 500 to 600/sup 0/F the side products produced appear to be strongly related to the presence of low molecular weight unsaturated hydrocarbon impurities in …
Date: September 1, 1978
Creator: Ritter, A.B.; DeLancey, G.B.; Schneider, J. & Silla, H.
Object Type: Report
System: The UNT Digital Library
Operating manual for the de Phanger precision long counter (PLC) (open access)

Operating manual for the de Phanger precision long counter (PLC)

The setting up, calibration operation, characteristics, and problems of the precision long counter for neutron intensity measurements are discussed. (WHK)
Date: February 6, 1978
Creator: Slaughter, D.
Object Type: Report
System: The UNT Digital Library
Studies of nuclear-waste migration in geologic media. Annual report, November 1976--October 1977 (open access)

Studies of nuclear-waste migration in geologic media. Annual report, November 1976--October 1977

The confinement of nuclear wastes in geologic formations is being considered as a method of permanently disposing of the waste. Laboratory experiments (column infiltration, static absorption, and batch partitioning experiments) were performed with nuclides of Cs, Pu, Np, and Am to examine the migratory characteristics of long-lived radionuclides that could be mobilized by groundwaters infiltrating a nuclear waste repository and the surrounding geologic body. In column infiltration experiments, the positions of peak concentrations of Cs in chalk or shale columns; Pu in limestone; Am in limestone, sandstone, or tuff; and Np in a limestone column did not move when the columns were infiltrated with water. However, fractions of each of the nuclides were seen downstream from the peaks, indicating that there was a large dispersion in the relative migration rates of each of the trace elements in the lithic materials studied. The results of static absorption experiments indicate that Pu and Am are strongly absorbed from solution by the common rocks studied and that their migration relative to ground-water flow is thereby retarded. In addition, the reaction rates of dissolved nuclides with rocks were found to vary considerably in different rock-element systems. Batch partitioning experiments were performed to test whether …
Date: March 1, 1978
Creator: Seitz, M.G.; Rickert, P.G.; Fried, S.M.; Friedman, A.M. & Steindler, M.J.
Object Type: Report
System: The UNT Digital Library
Sensitivity of primary knock-on atom spectra and displacement per atom cross sections to different secondary neutron energy and angular distributions and ''in-group'' weighting schemes (open access)

Sensitivity of primary knock-on atom spectra and displacement per atom cross sections to different secondary neutron energy and angular distributions and ''in-group'' weighting schemes

The sensitivity of primary knock-on atom (PKA) spectra and displacement per atom (DPA) cross sections to different secondary neutron energy and angular distributions and ''in-group'' weighting schemes is investigated. It is shown that the sensitivity of the PKA spectra and DPA cross sections for the (n,n' unresolved) and (n,2n) reactions in Fe to different angular distributions and the same secondary neutron spectrum is reasonably large (approximately 15%), whereas the sensitivity of these quantities to grossly different secondary neutron spectra and the same angular distribution is unexpectedly small. It is also shown that for Al the sensitivity of damage energy cross sections to different ''in-group'' weighting schemes is, for the most part, small.
Date: January 1, 1978
Creator: Gabriel, T. A. & Bishop, B. L.
Object Type: Report
System: The UNT Digital Library
Radiation instrumentation (open access)

Radiation instrumentation

Separate abstracts have been prepared for items within the scope of the energy data base.
Date: January 1, 1978
Creator: Wadman, W.W. III (ed.)
Object Type: Article
System: The UNT Digital Library
Mirror hybrid reactor studies (open access)

Mirror hybrid reactor studies

The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed. (MHR)
Date: January 19, 1978
Creator: Bender, D.J.
Object Type: Article
System: The UNT Digital Library
''Sensing'' the elliptical torus (open access)

''Sensing'' the elliptical torus

A method is given for testing the location of an arbitrary point P=(x,y,z) relative to the toroidal surface generated by rotation of an ellipse (y - y-bar)/sup 2//b/sup 2/ + (z - z-bar)/sup 2//c/sup 2/ = 1, b,c,z-bar > o, about the Y axis. This includes the orientation of P with respect to both the outer and inner surfaces fo the degenerate torus generated by an ellipse with c > z-bar. 2 figures.
Date: March 1, 1978
Creator: Cashwell, E.D. & Everett, C.J.
Object Type: Report
System: The UNT Digital Library
Kilowatt Isotope Power System: component report for the Ground Demonstration System Accumulator (open access)

Kilowatt Isotope Power System: component report for the Ground Demonstration System Accumulator

The Model Number ORC1A3A01 System Accumulator for the Kilowatt Isotope Power System was expulsion tested and demonstrated to be in compliance with the requirements of Sundstrand Explusion Test Procedure, TP 400. Test requirements of TP 400 were extracted from the Kilowatt Isotope Power System, Ground Demonstration System Test Plan.
Date: January 31, 1978
Creator: Brainard, E.L.
Object Type: Report
System: The UNT Digital Library
Bibliography of reports on research sponsored by the NRC office of nuclear regulatory research, July--December 1977 (open access)

Bibliography of reports on research sponsored by the NRC office of nuclear regulatory research, July--December 1977

A bibliography of 198 reports published by contractors of the NRC Office of Nuclear Regulatory Research during the period July through December 1977 is presented along with abstracts from the Nuclear Safety Information Center computer file. The bibliography has been sorted into the subject categories used by NRC to organize the research program. Within the subject categories, the reports are arranged first by contractor organization and then chronologically. A brief description of the NRC research program precedes the bibliography.
Date: April 1, 1978
Creator: Buchanan, J.R.
Object Type: Report
System: The UNT Digital Library
Radially resolved measurements of ''q'' on the ATC tokamak (open access)

Radially resolved measurements of ''q'' on the ATC tokamak

This paper describes a new technique for directly measuring the safety factor, or q, profile in a tokamak. A tightly collimated neutral beam capable of injecting approximately 100 mA of 30 keV deuterium atoms was mounted on the ATC tokamak. By proper tangential aiming of the beam a strong concentration of circulating fast ions was created at a chosen plasma minor radius. By examining the orbits of these ions with a multi-sight-line charge exchange detector, it was possible to measure the shifts of the orbits off of magnetic surfaces, and thereby to make local measurements of q. This experiment showed that when q on axis reached unity, strong internal turbulence began, and further lowering of q at the outer edge of the plasma did not lower q(0). A second result was that the measured q(0) was approximately 1.8 times larger than the q(0) deduced from the T/sub e/(r) profile, assuming z/sub eff/ to be independent of minor radius. This suggests a significant peaking of z/sub eff/ on axis in ATC.
Date: April 1, 1978
Creator: Goldston, R.J.
Object Type: Report
System: The UNT Digital Library
Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures (open access)

Low strain diameter expansion of internally pressurized Zircaloy-4 tubing at high temperatures

Tests of closed-end, internally pressurized, Zircaloy-4 tubing specimens were utilized to develop low strain creep characteristics as a function of time at temperatures in the range of 1475/sup 0/F to 2000/sup 0/F (802/sup 0/C to 1093/sup 0/C) and hoop stresses in the range of 250 to 2500 psi for use in loss-of-coolant accident (LOCA) analyses. The strain rate above the start of the alpha to beta phase transformation region, approximately 1490/sup 0/F (810/sup 0/C), was found to be sensitive to the test procedure (stress-temperature history). This is believed to result from variations in the metallurgical structure. A prediction model is presented which provides a conservative upper bound to the low strain test data provided in this report and reported in the literature.
Date: March 1978
Creator: White, L.S. & Busby, C.C.
Object Type: Report
System: The UNT Digital Library
Neutron induced current pulses in fission chambers. [LMFBR] (open access)

Neutron induced current pulses in fission chambers. [LMFBR]

The mechanism of neutron induced current pulse generation in fission chambers is discussed. By application of the calculated detector transfer function to proposed detector current pulse shapes, and by comparison with actually observed detector output voltage pulses, a credible, semi-empirical, trapezoidal pulse shape of chamber current is obtained.
Date: January 1, 1978
Creator: Taboas, A.L. & Buck, W.L.
Object Type: Report
System: The UNT Digital Library
Analysis of LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step transient (open access)

Analysis of LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step transient

This report presents the analysis of the LOFT pressurizer spray and surge nozzles to include a 450/sup 0/F step thermal transient. Previous analysis performed under subcontract by Basic Technology Incorporated was utilized where applicable. The SAASIII finite element computer program was used to determine stress distributions in the nozzles due to the step transient. Computer results were then incorporated in the necessary additional calculations to ascertain that stress limitations were not exceeded. The results of the analysis indicate that both the spray and surge nozzles will be within stress allowables prescribed by subsubarticle NB-3220 of the 1974 edition of the ASME Boiler and Pressure Vessel Code when subjected to currently known design, normal operating, upset, emergency, and faulted condition loads.
Date: January 18, 1978
Creator: Nitzel, M.E.
Object Type: Report
System: The UNT Digital Library
Kilowatt Isotope Power System: component test report for the ground demonstration system pump. 77-KIPS-99 (open access)

Kilowatt Isotope Power System: component test report for the ground demonstration system pump. 77-KIPS-99

The purpose of this test was to demonstrate that the pump utilized for the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) fulfilled the requirements of Test Procedure 398A, Component Test Procedure for the Ground Demonstration System Pump. The results of the tests are reported. From these results it was concluded that the pump for the Kilowatt Isotope Power System has satisfactorily completed the requirements of Sundstrand Pump Test Procedure, TP 398A.
Date: February 8, 1978
Creator: Brainard, E.L.
Object Type: Report
System: The UNT Digital Library