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Transport of solid commodities via freight pipeline: demand analysis methodology. Volume IV. First year final report (open access)

Transport of solid commodities via freight pipeline: demand analysis methodology. Volume IV. First year final report

In order to determine the feasibility of intercity freight pipelines, it was necessary to determine whether sufficient traffic flows currently exist between various origins and destinations to justify consideration of a mode whose operating characteristics became competitive under conditions of high-traffic volume. An intercity origin/destination freight-flow matrix was developed for a large range of commodities from published sources. A high-freight traffic-density corridor between Chicago and New York and another between St. Louis and New York were studied. These corridors, which represented 18 cities, had single-direction flows of 16 million tons/year. If trans-shipment were allowed at each of the 18 cities, flows of up to 38 million tons/year were found in each direction. These figures did not include mineral or agricultural products. After determining that such pipeline-eligible freight-traffic volumes existed, the next step was to determine the ability of freight pipeline to penetrate such markets. Modal-split models were run on aggregate data from the 1967 Census of Transportation. Modal-split models were also run on disaggregate data specially collected for this study. The freight pipeline service characteristics were then substituted into both the aggregate and disaggregate models (truck vs. pipeline and then rail vs. pipeline) and estimates of pipeline penetration into particular …
Date: July 1, 1976
Creator: Allen, W.B. & Plaut, T.
System: The UNT Digital Library
Direct time-domain techniques for transient radiation and scattering. [Introduction to transient electromagnetics] (open access)

Direct time-domain techniques for transient radiation and scattering. [Introduction to transient electromagnetics]

A tutorial introduction to transient electromagnetics, focusing on direct time-domain techniques, is presented. Physical, mathematical, numerical, and experimental aspects of time-domain methods, with emphasis on wire objects excited as antennas or scatters are examined. Numerous computed examples illustrate the characteristics of direct time-domain procedures, especially where they may offer advantages over procedures in the more familiar frequency domain. These advantages include greater solution efficiency for many types of problems, the ability to handle nonlinearities, improved physical insight and interpretability, availability of wide-band information from a single calculation, and the possibility of isolating interactions among various parts of an object using time-range gating.
Date: July 1, 1976
Creator: Miller, E. K. & Landt, J. A.
System: The UNT Digital Library
Transport of solid commodities via freight pipeline: impact assessment. Volume V. First year final report (open access)

Transport of solid commodities via freight pipeline: impact assessment. Volume V. First year final report

The application of freight pipeline for the movement of solid goods offers a new option in the field of transportation. This volume examines impacts and their assessments. This study has only identified the areas where truck and/or rail substitution by pipeline may have impacts. It only can be said that pipeline, if it can substitute for surface traffic without correspondingly increasing it at another location, is inherently a more environmentally compatible mode of transport. Based on data presented in this report, it can be stated that, to the extent that a freight pipeline reduces the truck traffic, it helps to reduce street congestion, noise, energy consumption, accidents, and air pollution. As compared to rail, however, accident and noise reduction are certain, but the impact on energy consumption and air pollution depends on local conditions. (MCW)
Date: July 1, 1976
Creator: Zandi, I. & Gimm, K.K.
System: The UNT Digital Library
Geochemistry and hydrothermal alteration at selected Utah hot springs. Final report: Volume 3 (revised) (open access)

Geochemistry and hydrothermal alteration at selected Utah hot springs. Final report: Volume 3 (revised)

Application of Na-K-Ca geothermometry to warm springs in Utah indicates several areas with sufficiently high apparent temperatures to be of interest as geothermal exploration targets. A zone of warm springs in the Bonneville Basin show Na-K-Ca temperatures from 150/sup 0/C to 233/sup 0/C. Examination of Great Salt Lake, Bonneville sediment pore water, and Jordan Valley well-water chemistry indicates that mixing a small percent of these fluids with warm spring water can cause substantial errors in Na-K-Ca temperature estimates. Other saline deposits which may influence Na-K-Ca temperature estimates are the Paradox formation in southeastern Utah, the Muddy Creek formation in southwestern Utah, the Arapien shale in central Utah, the Preuss formation in northeastern Utah, and Playa salts in much of western Utah. The Roosevelt KGRA is the most attractive target identified by Na-K-Ca geothermometry. Hydrothermal alteration, heavy metal distribution, and water chemistry provide additional characterization of the Roosevelt system. Chemistry of a cool water seep (25/sup 0/C) shows Na-K-Ca temperature of 241/sup 0/C and SiO/sub 2/ temperature of 125/sup 0/C. A Phillips well flowing from below 1500' (457m) shows Na-K-Ca temperature of 262/sup 0/C, SiO/sub 2/ temperature of 262/sup 0/C, and K of 1.5 times the surface spring value. The near …
Date: July 1, 1976
Creator: Parry, W. T.; Benson, N. L. & Miller, C. D.
System: The UNT Digital Library
Transport of solid commodities via freight pipeline: cost estimating methodology. Volume III, parts A and B. First year final report (open access)

Transport of solid commodities via freight pipeline: cost estimating methodology. Volume III, parts A and B. First year final report

In order to examine the feasibility of an intercity freight pipeline, it was necessary to develop cost equations for various competing transportation modes. This volume presents cost-estimating equations for rail carload, trailer-on-flatcar, truck, and freight pipeline. Section A presents mathematical equations that approximate the fully allocated and variable costs contained in the ICC cost tables for rail carload, trailer-on-flatcar (TOFC) and truck common-carrier intercity freight movements. These equations were developed to enable the user to approximate the ICC costs quickly and easily. They should find use in initial studies of costs where exact values are not needed, such as in consideration of rate changes, studies of profitability, and in general inter-modal comparisons. Section B discusses the development of a set of engineering cost equations for pneumo-capsule pipelines. The development was based on an analysis of system components and can readily be extended to other types of pipeline. The model was developed for the purpose of a feasibility study. It employs a limited number of generalized parameters and its use is recommended when sufficient detailed and specific engineering information is lacking. These models were used in the comparison of modes presented in Volume I and hence no conclusions regarding relative costs …
Date: July 1, 1976
Creator: Warner, J.A.; Morlok, E.K.; Gimm, K.K. & Zandi, I.
System: The UNT Digital Library
Compilation of current high energy physics experiments - July 1976 (open access)

Compilation of current high energy physics experiments - July 1976

A compilation of current high energy physics experiments is presented, including in the tables the various experimental parameters as well as the spokesmen and institutions. (JFP)
Date: July 1, 1976
Creator: Kelly, R.L.; Armstrong, F.E.; Horne, C.P.; Hutchinson, M.S.; Richards, D.R.; Rittenberg, A. et al.
System: The UNT Digital Library
MHD diffuser model test program (open access)

MHD diffuser model test program

Experimental results of the aerodynamic performance of seven candidate diffusers are presented to assist in determining their suitability for joining an MHD channel to a steam generator at minimum spacing. The three dimensional diffusers varied in area ratio from 2 to 3.8 and wall half angle from 2 to 5 degrees. The program consisted of five phases: (1) tailoring a diffuser inlet nozzle to a 15 percent blockage; (2) comparison of isolated diffusers at enthalpy ratios 0.5 to 1.0 with respect to separation characteristics and pressure recovery coefficients; (3) recording the optimum diffuser exit flow distribution; (4) recording the internal flow distribution within the steam generator when attached to the diffuser; and (5) observing isolated diffuser exhaust dynamic characteristics. The 2 and 2-1/3 degree half angle rectangular diffusers showed recovery coefficients equal to 0.48 with no evidence of flow separation or instability. Diffusion at angles greater than these produced flow instabilities and with angles greater than 3 degrees random flow separation and reattachment.
Date: July 1, 1976
Creator: Idzorek, J J
System: The UNT Digital Library
Evaluation of the Solar Building, Albuquerque, New Mexico: instrumentation of building and system (open access)

Evaluation of the Solar Building, Albuquerque, New Mexico: instrumentation of building and system

The instrumentation used to obtain data on the Solar Building, Albuquerque, New Mexico during the period November, 1974, through April, 1976 is described. Attention is focused on the types of instrumentation used: their principles of operation, sensitivity, range and where pertinent, installation. Locations of sensors are identified, so far as this pertains to obtaining accurate and adequate data. A list of sensors monitored in the third period is presented, as an example in appendix A. For convenience, the physical quantities measured and the type of instrument used to measure each are presented. The nature of the output from the instrument and the normal method of recording that output are also given.
Date: July 1, 1976
Creator: Wildin, M.W.; McLaughlin, E.R. & Gilman, S.F.
System: The UNT Digital Library
Large scale breeder reactor plant prototype mechanical pump conceptual design study (open access)

Large scale breeder reactor plant prototype mechanical pump conceptual design study

This report includes engineering memorandums, drawings, key feature descriptions, and other data. Some of the reports, such as manufacturability and some stress analysis, were done by consultants for Byron Jackson. Review of this report indicates that the design is feasible. The pump can be manufactured to system and specification requirements. The overall length and weight of some pieces will require special consideration, but is within the scope of equipment and technology available today. The fabricated parts are large and heavy, but can be manufactured and machined. Only the high temperature is unique to this size, since previous sodium pumps were smaller. Nondestructive tests as required by the Code are described and are feasible. The performance test of the prototype has been studied thoroughly. It is feasible for a cold water test. There are some problem areas. However, all of them can be solved. Development needs include building and testing a small scale model.
Date: July 1, 1976
Creator: unknown
System: The UNT Digital Library
Large scale breeder reactor plant prototype mechanical pump conceptual design study (open access)

Large scale breeder reactor plant prototype mechanical pump conceptual design study

This final report is a complete conceptual design study of a mechanical pump for a large scale breeder reactor plant. The pumps are located in the cold leg side of the loops. This makes the net positive suction head available - NPSHA - low, and is, in fact, a major influencing factor in the design. Where possible, experience gained from the Clinch River Project and the FFTF is used in this study. Experience gained in the design, manufacturer, and testing of pumps in general and sodium pumps in particular is reflected in this report. The report includes estimated cost and time schedule for design, manufacture, and testing. It also includes a recommendation for development needs.
Date: July 1, 1976
Creator: unknown
System: The UNT Digital Library
Residual gravity analysis of selected cross sections of the Hanford reservation (open access)

Residual gravity analysis of selected cross sections of the Hanford reservation

Gravity data were collected along selected sites on the Hanford reservation. Residual gravity profiles were calculated. These data were then modeled using the Talwani two-dimensional gravity model. Analysis of these models suggests the location of several buried stream channels. The northern channel is believed to represent the ancestral Columbia when it flowed through a synclinal trough between Gable Mountain and Gable Butte, and the southern channel is believed to reflect a previous location of the Yakima River.
Date: July 1, 1976
Creator: Richard, B.H.
System: The UNT Digital Library
Environmental impact directory system: preliminary implementation for geothermal energy (open access)

Environmental impact directory system: preliminary implementation for geothermal energy

An Environmental Impact Directory System (EIDS) was proposed as a method for a computerized search of the widely distributed data files and models pertaining to energy-related environmental effects. To define the scope and content of the system, an example was prepared for the case of geothermal energy. The resulting sub-directory is known as GEIDs (Geothermal Environmental Impact Directory System). In preparing or reviewing an Environmental Impact Statement (EIS), the user may employ GEIDS as an extensive checklist to make sure he has taken into account all predictable impacts at any level of severity.
Date: July 1, 1976
Creator: Hess, F.D.; Hall, R.T. & Fullenwider, E.D.
System: The UNT Digital Library
Sodium--sulfur battery development program. Phase 1. Progress report, June 15, 1975--March 31, 1976 (open access)

Sodium--sulfur battery development program. Phase 1. Progress report, June 15, 1975--March 31, 1976

The pre-pilot facility for the batch production of ..beta..''-alumina tubing was designed and remodeled. Critical items of capital equipment were placed on order. Work began on the construction of the pre-pilot spray dryer and the batch and continuous sintering furnaces. A tentative testing program was arranged to permit evaluation of automatic isostatic pressing equipment. Two cells incorporating high-power-density electrode design and stainless steel containers for sodium and sulfur were designed, constructed, and tested. The first cell delivered an average of 286 W/kg during one discharge cycle at 750 mA/cm/sup 2/. The energy density was 55 Wh/kg at this high current density, whereas at 50 mA/cm/sup 2/ over 80 Wh/kg could be reached. The cell became nonfaradaic after 45 days because of ceramic failure. The second cell was put on test only recently. A cell with separate compartments for charging and discharging and with electrodes optimized for either task was tested successfully. Efforts to develop corrosion-resistant sulfur container materials were inititated. Static sodium tetrasulfide corrosion tests were conducted for 30 to 60 days at 400/sup 0/C on substrates of pure chromium and iron, nickel, cobalt, aluminum, titanium, niobium, tantalum, zirconium, and molybdenum base alloys. These substrates were tested with and without …
Date: July 1, 1976
Creator: Weiner, S. A.
System: The UNT Digital Library
Liquid-metal pumps for large-scale breeder-reactor plant (prototype pump) (open access)

Liquid-metal pumps for large-scale breeder-reactor plant (prototype pump)

This report presents the recommended pump design for use in Large Scale Liquid Metal Fast Breeder Reactor plants. The base design for the pump will circulate 127,000 GPM of liquid sodium at temperatures up to 850/sup 0/F and with a total discharge head at the design point of 500 feet Na with an impeller that is 40 feet below the sodium seal. The pump design is predicated on developing an impeller design which will have a suction specific speed (S/sub n/) of about 20,000 with 20 feet NPSH available, which will result in a pump speed of 530 RPM at design conditions. The design is based on the technology developed in the design and fabrication of FFTF pumps, the design efforts for the Clinch River Breeder Reactor Pump design study and other technology.
Date: July 1, 1976
Creator: Lindsay, M. (comp.)
System: The UNT Digital Library
Oscilloscope Camera Evaluations Quality Division April-June 1976 (open access)

Oscilloscope Camera Evaluations Quality Division April-June 1976

None
Date: July 1, 1976
Creator: Avara, G. R.
System: The UNT Digital Library
Tables of the effective shell-model interaction through second order for the sd shell. [Valence model and unoccupied space] (open access)

Tables of the effective shell-model interaction through second order for the sd shell. [Valence model and unoccupied space]

Numerical tables of the effective shell-model interaction matrix elements for the s-d shell are presented as a function of the valence model space and the unoccupied space.
Date: July 1, 1976
Creator: Vary, J. P.
System: The UNT Digital Library
Influence of pairing on the distribution of independent yield strengths in neutron-induced fission (open access)

Influence of pairing on the distribution of independent yield strengths in neutron-induced fission

This report is a summary of the current status of an ongoing investigation of the influence of the pairing force in the distribution of independent yields. At this time pairing systematics have been obtained for /sup 235/U thermal and fast fission yields by a comparison of experimental data to the normal yield curves predicted by the phenomenological model. A semiempirical formalism has been developed and tested (insofar as the available data permits) by which estimates for the magnitudes of the pairing effects can be easily incorporated into the version of the phenomenological model to be used in the ENDF/B-V Fission Product Evaluated Data File. The formalism is based upon the /sup 235/U thermal and fast fission data analysis and has been extended to other proposed ENDF/B-V fissionable nuclides. Neutron energy dependence has been incorporated (in a simple fashion) in terms of excitation energies of the compound system and measured fission barriers. Again, the energy dependence has been expressed in a manner which is easily assimilated by the ENDF/B-V yield model. The initial efforts in this study have been governed by the need to include some quantitative description of the pairing effects within the framework of the existing phenomenological treatment. The …
Date: July 1, 1976
Creator: Madland, D. G. & England, T. R.
System: The UNT Digital Library
Bayesian Zero-Failure (BAZE) reliability demonstration testing procedure and its application to a Rankine dynamic radioisotope power conversion system (open access)

Bayesian Zero-Failure (BAZE) reliability demonstration testing procedure and its application to a Rankine dynamic radioisotope power conversion system

A Bayesian Zero-Failure (BAZE) reliability demonstration testing procedure is developed. The procedure may be used to verify component failure rates associated with both real-time dependent and cycle-dependent chance failure mechanisms. A constant falure-rate model with a gamma prior distribution is assumed. The procedure is used to obtain sample test plans for components of a proposed Rankine power conversion system.
Date: July 1, 1976
Creator: Martz, H. F. Jr. & Waller, R. A.
System: The UNT Digital Library
Plankton community structure: evaluation of analytical methods using model communities. Final report. [Effects of effluents on plankton] (open access)

Plankton community structure: evaluation of analytical methods using model communities. Final report. [Effects of effluents on plankton]

The general purpose of this project was to provide information that might be of use to biologists who are investigating the effects of effluents on plankton. Although most applicable to non-persistent pollutants, such as thermal effluents, the methodology may be applied in some degree to nondegradable pollutants as well. The purpose of the present study was, therefore, to provide some information about the relative effectiveness of certain representative affinity tests, in circumstances that would be analogous to those encountered in an impact investigation on plankton. In such a study, real data cannot be used, if the purpose is to show the efficiency of a test at detecting groups with known characteristics; artificial data must be employed in which those characteristics are built in. For that reason, a distribution model was to generate the data for computer analysis.
Date: July 1, 1976
Creator: Hayes, W. B.
System: The UNT Digital Library
ETOP 14, a FORTRAN code to process ENDF/B data into the 68-group PHROG library format (open access)

ETOP 14, a FORTRAN code to process ENDF/B data into the 68-group PHROG library format

ETOP 14 processes neutron cross section data from the ENDF/B format to the 68-group PHROG fast spectrum code. Major changes have accompanied modifications in the ENDF/B format and modifications to the PHROG code necessitated by changes in the ENDF/B format. A large number of program changes have been made to increase the program's efficiency and accuracy in treating specific cross sections. The present version of the program will process all Version 4 ENDF/B formats except the Adler-Adler multilevel resonance formula. ETOP 14 calculates infinitely dilute capture and fission cross sections and an infinitely dilute elastic scattering matrix for these materials over the resonance range. This limitation will be corrected in the near future. Some reaction cross sections which are only prominent above 10 MeV are ignored by ETOP 14. The code in its present form can be easily extended above 10 MeV. The maximum number of multigroups permitted is 99 even though the PHROG library is presently limited to 68 quarter lethargy groups. The present report assumes a complete familiarity with the ENDF/B format.
Date: July 1, 1976
Creator: Grimesey, R. A.; Singer, G. L. & Millsap, D. A.
System: The UNT Digital Library
LWR fuel cycle quarterly report, April 1--June 30, 1976. [Preliminary data on Savannah River Plant area to assess environmental effects of fuel reprocessing plant] (open access)

LWR fuel cycle quarterly report, April 1--June 30, 1976. [Preliminary data on Savannah River Plant area to assess environmental effects of fuel reprocessing plant]

A detailed agricultural data base for the Savannah River Plant and its environs was begun. This data base will contain information and data such as crop production, growing season, soil type, and agricultural practices that are needed to assess foodchain pathways. It will be used in the initial assessment of environmental effects of the LWR Fuel Recycle Complex at the Savannah River site.
Date: July 1, 1976
Creator: Dickerson, M. H. & Ng, Y. C.
System: The UNT Digital Library
DENSJT: statistical shell-model level density computer code description and user's manual. [In FORTRAN for CDC Cyber-70 computer] (open access)

DENSJT: statistical shell-model level density computer code description and user's manual. [In FORTRAN for CDC Cyber-70 computer]

The FORTRAN code DENSJT described here is constructed to calculate the appropriate moments and dimensions needed in describing the Gaussian level density for fixed values of the total angular momentum (J) and isobaric spin (T = T/sub 0/). The input for this code is the same as in the usual shell-model codes, namely, the single-particle orbital properties and the antisymmetric two-body matrix elements. To calculate the moments for fixed values of the angular momentum (J) a method described by Ginocchio is used. All of the ''basic inputs'' needed in the reduction formula were derived without any restrictions on the orbitals. The formulas used in DENSJT are described, and the basic inputs are listed in tables. A block flow chart showing the general structure and the specific function of each subroutine is included. All necessary information for the input and output of this code is described. A calculation involving 3 orbitals in the s--d shell took 1 second on a CDC Cyber-70 computer. (RWR)
Date: July 1, 1976
Creator: Dalton, B.
System: The UNT Digital Library
Geothermal resources: exploration and exploitation. A bibliography (open access)

Geothermal resources: exploration and exploitation. A bibliography

This comprehensive bibliography contains 5476 citations of foreign and domestic research reports, journal articles, patents, conference proceedings, and books concerned with the exploration and exploitation of geothermal resources. The coverage dates back as far as useful references could be obtained and extends through June 1976. References are arranged in broad subject categories and are made up of complete bibliographic citations. These are followed by a listing of subject descriptors used to describe the subject content of each reference. Four indexes are included: Corporate, Personal Author, Subject, and Report Number. Also included is a list of journals from which articles were selected. (LBS)
Date: July 1, 1976
Creator: unknown
System: The UNT Digital Library
Annotated bibliography of safety-related occurrences in pressurized-water nuclear power plants as reported in 1975 (open access)

Annotated bibliography of safety-related occurrences in pressurized-water nuclear power plants as reported in 1975

The bibliography presented contains 100-word abstracts of reports to the U.S. Nuclear Regulatory Commission concerning operational events that occurred at pressurized-water reactor nuclear power plants in 1975. The report includes 1097 abstracts, arranged alphabetically by reactor name and then chronologically for each reactor, that describe incidents, failures, and design or construction deficiencies experienced at the facilities. Key-word and permuted-title indexes are provided to facilitate location of the subjects of interest, and tables summarizing the information contained in the bibliography are presented. The information listed in the tables includes instrument failures, equipment failures, system failures, causes of failures, deficiencies noted, and the time of occurrence (i.e., during refueling, operation, testing, or construction). A few of the unique events that occurred during the year are reviewed in detail.
Date: July 1, 1976
Creator: Scott, R. L. & Gallaher, R. B.
System: The UNT Digital Library