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3,579 Matching Results
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Analysis of equivalent capacitances between mutually coupled windings
The interwinding capacitance between mutually coupled windings may play a significant role in the transient analysis of these windings. Neglecting this capacitance or dividing it equally among the interwinding node pairs would then result in considerable inaccuracy in the analysis. A method is proposed to calculate equivalent interwinding capacitances which will reduce this inaccuracy. It is illustrated by simple winding models.
Date:
January 1, 1986
Creator:
Chowdhuri, P.
Object Type:
Article
System:
The UNT Digital Library
Analysis of FEL optical systems with grazing incidence mirrors
The use of grazing incidence optics in resonators alleviates the problem of damage to the optical elements and permits higher powers in cavities of reasonable dimensions for a free electron laser (FEL). The design and manufacture of a grazing incidence beam expander for the Los Alamos FEL mock-up has been completed. In this paper, we describe the analysis of a bare cavity, grazing incidence optical beam expander for an FEL system. Since the existing geometrical and physical optics codes were inadequate for such an analysis, the GLAD code was modified to include global coordinates, exact conic representation, raytracing, and exact aberration features to determine the alignment sensitivities of laser resonators. A resonator cavity has been manufactured and experimentally setup in the Optical Evaluation Laboratory at Los Alamos. Calculated performance is compared with the laboratory measurements obtained so far.
Date:
January 1, 1986
Creator:
Knapp, C. E.; Viswanathan, V. K.; Bender, S. C.; Appert, Q. D.; Lawrence, G. & Barnard, C.
Object Type:
Article
System:
The UNT Digital Library
Analysis of fissionable material using delayed gamma rays from photofission
The energetic gamma-ray spectra from the fission products of photofission have been investigated to determine whether photofission can identify heavily shielded fissionable material. Target samples of natural thorium, 93% enriched /sup 235/U, natural uranium, and 93% enriched /sup 239/Pu were irradiated with bremsstrahlung gamma rays produced by 10-MeV electrons from a small linear accelerator. The gamma-ray spectra for each of the four isotopes studied reveals a distinctive intensity distribution. For example, the intensity ratio of the pair of gamma rays at 1436 keV (/sup 138/Cs) and 1428 keV (/sup 94/Sr) is 1.9 for /sup 235/U, 2.4 for /sup 238/U, 1.7 for /sup 232/Th and 1.4 for /sup 239/Pu. 6 refs., 2 figs., 1 tab.
Date:
September 1, 1986
Creator:
Hollas, C. L.; Close, D. A. & Moss, C. E.
Object Type:
Article
System:
The UNT Digital Library
Analysis of fuel shares in the industrial sector
These studies describe how fuel shares have changed over time; determine what factors are important in promoting fuel share changes; and project fuel shares to the year 1995 in the industrial sector. A general characterization of changes in fuel shares of four fuel types - coal, natural gas, oil and electricity - for the industrial sector is as follows. Coal as a major fuel source declined rapidly from 1958 to the early 1970s, with oil and natural gas substituting for coal. Coal's share of total fuels stabilized after the oil price shock of 1972-1973, and increased after the 1979 price shock. In the period since 1973, most industries and the industrial sector as a whole appear to freely substitute natural gas for oil, and vice versa. Throughout the period 1958-1981, the share of electricity as a fuel increased. These observations are derived from analyzing the fuel share patterns of more than 20 industries over the 24-year period 1958 to 1981.
Date:
June 1, 1986
Creator:
Roop, J.M. & Belzer, D.B.
Object Type:
Report
System:
The UNT Digital Library
Analysis of fuel shares in the residential sector: 1960 to 1995
Historical and future energy use by fuel type in the residential sector of the United States are examined. Of interest is the likely relative demand for fuels as they affect national policy issues such as the potential shortfall of electric generating capacity in the mid to late 1990's and the ability of the residential sector to switch rapdily among fuels in response to fuel shortages, price increases and other factors. Factors affecting the share of a fuel used rather than the aggregate level of energy use are studied. However, the share of a fuel used is not independent of the level of energy consumption. In the analysis, the level of consumption of each fuel is computed as an intermediate result and is reported for completeness.
Date:
August 1, 1986
Creator:
Reilly, J.M.; Shankle, S.A. & Pomykala, J.S.
Object Type:
Report
System:
The UNT Digital Library
An analysis of groundwater contamination from the operation of a 6-GeV continuous electron beam accelerator
The potential contamination groundwater in the vicinity of a beam dump associated with a 6-GeV continuous electron beam accelerator has been analyzed considering the site hydrology. The potential contamination arising from photoneutron activation of soil and the subsequent leaching, transport, and decay of tritium are examined. The analysis accounts for dilution from groundwater transport and infiltration of precipitation. The results demonstrate that dilution reduces the concentration of tritium in the groundwter by one order of magnitude from a simple production and transport model that does not consider the effects of dilution. 5 refs., 2 figs., 2 tabs.
Date:
January 1, 1986
Creator:
Lee, D. W.
Object Type:
Article
System:
The UNT Digital Library
Analysis of high pressure boil-off situation during MSIV closure ATWS in a typical BWR/4
The objective of this paper is to provide a best-estimate analysis of the MSIV Closure ATWS in the Browns Ferry Unit 1 BWR with Mark 1 containment. The calculations have been performed using the RAMONA-3B code which has a three-dimensional neutron kinetics model coupled with one-dimensional (multi-channel core representation), four-equation, nonhomogeneous, nonequilibrium thermal hydraulics. The code also allows for one-dimensional neutronic core representation. The 1-D capability of the code has been employed in this calculation since a thorough sensitivity study showed that for a full ATWS, a one-dimensional (axial) neutron kinetics adequately describes the core behavior. (Note that the core steady-state symmetry in this case was preserved throughout the transient so that radial effects could be neglected.) The calculation described in the paper was started from a steady-state fuel condition corresponding to the end of Cycle 5 of the Browns Ferry reactor.
Date:
January 1, 1986
Creator:
Neymotin, L. Y.; Slovik, G. C. & Saha, P.
Object Type:
Article
System:
The UNT Digital Library
Analysis of hydrogen production during a BWR6 core heatup transient
An extensive study was performed for the prediction of hydrogen production during a BWR6 core heatup transient. Hydrogen production was found to be strongly affected by the transient core heat transfer and vessel hydrodynamics. Various sources important for steam generation and hydrogen production were identified. The results of the study were used by the NRC staff in their evaluation of the adequacy of the H/sub 2/ release histories suggested by the Hydrogen Control Owner's Group (HCOG). The owners group are sponsoring a 1/4 scale test program to investigate the adequacy of H/sub 2/ control during a degraded event. 1 ref., 2 figs.
Date:
January 1, 1986
Creator:
Yang, J. W. & Pratt, W. T.
Object Type:
Article
System:
The UNT Digital Library
Analysis of inelastic neutron scattering spectra from a time-of-flight spectrometer with filter detector
Inelastic neutron scattering spectra obtained from time-of-flight spectrometers with filter detector suffer in energy resolution from a long time-of-flight tail in the filter response function. A mathematical method is described which removes this tail in measured spectra. The energy resolution can thereby be adapted for each part of the spectrum. Applications of the method to data taken at the LANSCE pulsed spallation source are presented.
Date:
January 1, 1986
Creator:
Vorderwisch, P.; Mezei, F.; Eckert, J. & Goldstone, J.A.
Object Type:
Article
System:
The UNT Digital Library
Analysis of Magnetic Refrigerators With External Regeneration
The central idea of the magnetic refrigeration systems analyzed in this paper is that of a MR having a regenerator composed of an integral number of separate stages but having only a single magnetic stage. In principle, each stage is thermally isolated from the others, but the stages are accessed by a manifold and valve system which allows gas to flow between the MM and the individual stages. The concept therefore is distinctly unlike that of the unusual continuous regenerator of gas refrigerators. Although a small amount of gas in the manifold is responsible for the actual transfer of heat between elements of the REGMR, it is clear from the cycle description in the caption of Fig. 1 that the fixed mass of the MM is analogous to a fixed mass of a working fluid in a gas refrigerator or engine. Both, in effect, are carried thermally through all parts of their respective systems.
Date:
January 1, 1986
Creator:
Overton, W. C. Jr. & Barclay, J. A.
Object Type:
Article
System:
The UNT Digital Library
Analysis of MSIV-ATWS events with the BNL plant analyzer
There are automatic safety features and operator-initiated emergency procedures which influence the sequence of events until the time when the standby liquid control system (SLCS), or other attempts to get control rods inserted, can effect shutdown of the core. One emergency procedure for a BWR/4 would require the operator to reduce the flow of high pressure coolant injection (HPCI) into the reactor. The core inlet flow rate at this time would be due to natural circulation and the reduced flow would lower the water level in the downcomer thereby reducing the natural circulation flow rate. This effect, and the reduction in core inlet subcooling due to mixing of the emergency feedwater with steam in the downcomer when the level was lowered, cause a sufficient increase in core void fraction so that the power would be reduced. A reduction in pressure might also be called for during this event in order to comply with the PSP heat capacity temperature limit (or possibly to prevent cycling of relief valves). In the past few years there have been several studies of this problem with the emphasis on calculating the power level in the core. In the present study we consider the power level …
Date:
June 1, 1986
Creator:
Diamond, D. J.
Object Type:
Article
System:
The UNT Digital Library
Analysis of nuclear power plant construction costs
The objective of this report is to present the results of a statistical analysis of nuclear power plant construction costs and lead-times (where lead-time is defined as the duration of the construction period), using a sample of units that entered construction during the 1966-1977 period. For more than a decade, analysts have been attempting to understand the reasons for the divergence between predicted and actual construction costs and lead-times. More importantly, it is rapidly being recognized that the future of the nuclear power industry rests precariously on an improvement in the cost and lead-time situation. Thus, it is important to study the historical information on completed plants, not only to understand what has occurred to also to improve the ability to evaluate the economics of future plants. This requires an examination of the factors that have affected both the realized costs and lead-times and the expectations about these factors that have been formed during the construction process. 5 figs., 22 tabs.
Date:
January 1, 1986
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Analysis of organizational options for the uranium enrichment enterprise in relation to asset divesture. [BPA; TVA; SYNFUELS; CONRAIL; British TELECOM; COMSTAT]
This report presents a comparison of the characteristics of some prominent examples of independent government corporations and agencies with respect to the Department of Energy's (DOE) uranium enrichment enterprise. The six examples studied were: the Bonneville Power Administration (BPA); the Tennessee Valley Authority (TVA); the Synthetic Fuels Corporation (SYNFUELS); the Consolidated Rail Corporation (CONRAIL); the British Telecommunications Corporation (British TELECOM); and the Communications Satellite Organization (COMSAT), in order of decreasing levels of government ownership and control. They range from BPA, which is organized as an agency within DOE, to COMSAT, which is privately owned and free from almost all regulations common to government agencies. Differences in the degree of government involvement in these corporations and in many other characteristics serve to illustrate that there are no accepted standards for defining the characteristics of government corporations. Thus, historical precedent indicates considerable flexibility would be available in the development of enabling legislation to reorganize the enrichment enterprise as a government corporation or independent government agency.
Date:
August 1, 1986
Creator:
Harrer, B. J.; Hattrup, M. P.; Dase, J. E. & Nicholls, A. K.
Object Type:
Report
System:
The UNT Digital Library
Analysis of picosecond pulsed laser melted graphite
A Raman microprobe and high resolution TEM have been used to analyze the resolidified region of liquid carbon generated by picosecond pulse laser radiation. From the relative intensities of the zone center Raman-allowed mode for graphite at 1582 cm/sup -1/ and the disorder-induced mode at 1360 cm/sup -1/, the average graphite crystallite size in the resolidified region is determined as a function of position. By comparison with Rutherford backscattering spectra and Raman spectra from nonosecond pulsed laser melting experiments, the disorder depth for picosecond pulsed laser melted graphite is determined as a function of irradiating energy density. Comparisons of TEM micrographs for nanosecond and picosecond pulsed laser melting experiments show that the structure of the laser disordered regions in graphite are similar and exhibit similar behavior with increasing laser pulse fluence.
Date:
January 1, 1986
Creator:
Steinbeck, J.; Braunstein, G.; Speck, J.; Dresselhaus, M. S.; Huang, C. Y.; Malvezzi, A. M. et al.
Object Type:
Article
System:
The UNT Digital Library
Analysis of residential, industrial and commercial sector responses to potential electricity supply constraints in the 1990s
There is considerable debate over the ability of electric generation capacity to meet the growing needs of the US economy in the 1990s. This study provides new perspective on that debate and examines the possibility of power outages resulting from electricity supply constraints. Previous studies have focused on electricity supply growth, demand growth, and on the linkages between electricity and economic growth. This study assumes the occurrence of electricity supply shortfalls in the 1990s and examines the steps that homeowners, businesses, manufacturers, and other electricity users might take in response to electricity outages.
Date:
September 1, 1986
Creator:
Fisher, Z. J.; Fang, J. M.; Lyke, A. J. & Krudener, J. R.
Object Type:
Report
System:
The UNT Digital Library
Analysis of steam-generator tube-rupture events combined with auxiliary-feedwater control-system failure for Three Mile Island-Unit 1 and Zion-Unit 1 pressurized water reactors
A steam-generator tube-rupture (SGTR) event combined with loss of all offsite alternating-current power and failure of the auxiliary-feedwater (AFW) control system has been investigated for the Three Mile Island-Unit 1 (TMI-1) and Zion-Unit 1 (Zion-1) pressurized water reactors. The Transient Reactor Analysis Code was used to simulate the accident sequence for each plant. The objectives of the study were to predict the plant transient response with respect to tube-rupture flow termination, extent of steam generator overfill, and thermal-hydraulic conditions in the steam lines. Two transient cases were calculated: (1) a TMI-1 SGTR and runaway-AFW transient, and (2) a Zion-1 SGTR and runaway-AFW transient. Operator actions terminated the tube-rupture flow by 1342 s (22.4 min) and 1440 s (24.0 min) for TMI-1 and Zion-1, respectively, but AFW injection was continued. The damaged steam generator (DSG) overfilled by 1273 s (21.2 min) for the TMI-1 calculation and by 1604 s (26.7 min) for the Zion-1 calculation. The DSG steam lines were completely filled by 1500 s (25 min) and 2000 s (33.3 min) for TMI-1 and Zion-1, respectively. The maximum subcooling in the steam lines was approx.63 K (approx.113/sup 0/F) for TMI-1 and approx.44 K (approx.80/sup 0/F) for Zion-1.
Date:
January 1, 1986
Creator:
Nassersharif, B.
Object Type:
Article
System:
The UNT Digital Library
Analysis of surface contaminants on beryllium windows
It is known that various crystalline and liquid compounds form on the downstream surfaces of beryllium windows exposed to air. It is also known that the integrity of such windows may be compromised resulting in leaks through the window. The purpose of this report is to document the occurrences described as they pertain to the NSLS and to analyze, where possible, the various substances formed.
Date:
December 1, 1986
Creator:
Gmur, N. F.
Object Type:
Report
System:
The UNT Digital Library
Analysis of temperature-time data from 3 m drillholes at Crystal Hot Springs, Utah
A method for determining the background geothermal gradient values through the analysis of temperature measurements at multiple depths to 3 m and recorded over a time span of several days is presented. The analysis is based on the amplitude decay and phase shift of temperature waves with depth. Diurnal and other high frequency temperature variations are used to compute thermal diffusivities which in turn are used to model and remove the effect of the annual temperature wave. The analysis considers both a homogeneous half space and a two layer medium consisting of an overburden of finite thickness overlying a semi-infinite substratum. The method was tested in three holes in the Crystal Hot Springs geothermal field. Temperatures in each hole were recorded once a minute over a period of three days with a probe containing thermistors at eight different depths. Five of the thermistors were positioned at shallow depths (less than or equal to 0.5 m) to monitor diurnal and other high frequency waves and three at greater depths (greater than or equal to 1 m) to measure lower frequency variations. Since measurements were recorded at only three sites, the accuracy and reliability of the method is not fully evaluated. Potential …
Date:
January 1, 1986
Creator:
Howell, Jack & Chapman, David S.
Object Type:
Report
System:
The UNT Digital Library
Analysis of the April 18, 1986 UF[sub 6] release test
On April 18 1986 a controlled uranium hexafluoride (UF[sub 6])release test was conducted at a CESTA (a French government agency) test site near Bordeaux, France. During the test, 45.8 kg of UF[sub 6] vapor a time interval of 605 s from a 3.15-m high, 0.05-m diameter pipe at a rate of 75.7 kg/s. The exit velocity was 3.46 m/s, and the average exit temperature was 108[degree]C. Information collected during the release test included: meteorological data, measurements of uranium and fluorine concentrations deposition data, and particle size distribution data. Data collected was evaluated and compared to the UF[sub 6] dispersion model.
Date:
October 1, 1986
Creator:
Just, R. A.
Object Type:
Report
System:
The UNT Digital Library
Analysis of the April 18, 1986 UF{sub 6} release test. Draft
On April 18 1986 a controlled uranium hexafluoride (UF{sub 6})release test was conducted at a CESTA (a French government agency) test site near Bordeaux, France. During the test, 45.8 kg of UF{sub 6} vapor a time interval of 605 s from a 3.15-m high, 0.05-m diameter pipe at a rate of 75.7 kg/s. The exit velocity was 3.46 m/s, and the average exit temperature was 108{degree}C. Information collected during the release test included: meteorological data, measurements of uranium and fluorine concentrations deposition data, and particle size distribution data. Data collected was evaluated and compared to the UF{sub 6} dispersion model.
Date:
October 1, 1986
Creator:
Just, R. A.
Object Type:
Report
System:
The UNT Digital Library
Analysis of the burping behavior of the cold solid methane moderator at IPNS (Intense Pulsed Neutron Source)
Examination of the cold solid methane moderator at IPNS (Model II) revealed that a circumferential weld failed due to high internal pressure, such as would be caused by thermal expansion of solid methane or the release of Hydrogen gas upon spontaneous heating. This weld is the main object of current attention for a design of a replacement. The present paper deals with the processes which lead to the burping behavior and outlines the analysis of some of the consequences. The purpose is to determine conditions under which the system can operate at the lowest possible temperature, avoiding the problems experienced to data.
Date:
January 1, 1986
Creator:
Carpenter, J.M. & Walter, U.
Object Type:
Article
System:
The UNT Digital Library
Analysis of the FELIX experiments with cantilevered beams and hollow cylinders
Experiments have been performed with the FELIX facility at Argonne National Laboratory to study the coupling between eddy currents and deflections and to provide data for validating eddy current computer programs. Experiments with cantilevered beams in crossed steady and decaying magnetic fields verify that coupling effects act to alleviate the large currents, deflections, and stresses predicted by uncoupled analyses. Measurements of magnetic fields induced in conducting hollow cylinders are analyzed by exponential fitting and by transfer functions. Spatial variation in the parameters of the exponential fit and in those of the one- and two-pole transfer functions suggests that several eddy current modes are acting in the cylinder test pieces.
Date:
January 1, 1986
Creator:
Turner, L. R.; Hua, T. Q. & Lee, S. Y.
Object Type:
Article
System:
The UNT Digital Library
Analysis of the requirements for economic magnetic fusion
A generic reactor model is used to examine the economic viability of electricity generation by magnetic fusion. The simple model uses components which are representative of those used in previous reactor studies of deuterium-tritium burning tokamaks, stellarators, bumpy tori, reverse field pinches and tandem mirrors. Conservative costing assumptions are made. The generic reactor is not a tokamak but rather it is intended to emphasize what is common to all magnetic fusion reactors. The reactor uses a superconducting toroidal coil set to produce the dominant magnetic field. To this extent it is a less good approximation to systems, such as the reversed field pinch in which the main field is produced by a plasma current. The main output of the study is the cost of electricity as a function of the weight and size of the fusion core - blanket, shield, structure and coils. The model shows that a 1200 MW/sub e/ power plant with a fusion core weight of about 10,000 tonnes should be competitive in the future with fission and fossil plants. Sensitivity studies of varying the assumptions show that this result is not sensitively dependent on any given assumption. Of particular importance is the result that this scale …
Date:
January 1, 1986
Creator:
Sheffield, J.
Object Type:
Article
System:
The UNT Digital Library
Analysis of the results of the Midland PRA
This paper presents the results of a limited review of the Midland PRA (MPRA), aimed at facilitating regulatory analyses and at providing insights into safety related plant failures. In particular, stress was laid on the root causes of accident sequences, particularly their failure modes, viz., hardware, human, maintenance, test, and repair. Because this information was difficult to extract in this detailed and sophisticated PRA (and in certain others) a special algorithm was developed to display the leading sequences contributing to core damage and/or to public risk in terms of the above generic failure modes. This was done in a hierarchical fashion to allow tracing the important accident sequences to the systems failures. The weighted core damage frequency (CDF) values of the sequences considered then provided a (quantitative) ranked importance listing of these failure modes, led by hardware failures (in 78%) and human factors (in 37%), etc. Multiple maintenance situations (reflecting on test and maintenance specifications) were also evaluated, but played only a small role (less than or equal to3%). Similar tabulations were also made of the (weighted) importance of the support systems (such as the electric power system, the component cooling water systems, etc.) and of the role of the …
Date:
January 1, 1986
Creator:
Bozoki, G. & Teichmann, T.
Object Type:
Article
System:
The UNT Digital Library