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Coupled Hydrodynamic-Structural Response Analysis of Piping Systems

Description: This report describes in detail the expansion of the ICEPEL code for the coupled hydrodynamic-structural response analysis of pipe-elbow loops to general piping systems. A generalized piping-component model, a branching tce junction, and a surge-tank model are introduced and coupled with the pipe-elbow loop model so that a general piping system under the effect of internally traveling pressure pulses can be analyzed hydrodynamically, as well as structurally.
Date: 1978?
Creator: A-Moneim, M. T.
Partner: UNT Libraries Government Documents Department

ICEPEL Analysis of and Comparison with Simple Elastic-Plastic Piping Experiments

Description: The results of simple elastic-plastic piping experiments for straight pipes and single-elbow loop systems are interpreted and evaluated. The experiments are also analyzed by the ICEPEL piping code, and the analytical results are compared against the experimental data.
Date: December 1978
Creator: A-Moneim, M. T.
Partner: UNT Libraries Government Documents Department

Uranium hydrogeochemical and stream sediment reconnaissance data from the area of the Noatak and portions of the Baird Mountains and Ambler River Quadrangles, Alaska

Description: During August 1976, a total of 876 natural waters and 861 bottom sediments were collected at a nominal density of one location each 23 km/sup 2/ from streams and small lakes throughout the Noatak NTMS quadrangle, the southern two-thirds of the Baird Mountains NTMS quadrangle, and in the southwest corner of the Ambler River NTMS quadrangle. These samples were collected as part of the National Uranium Resource Evaluation program in Alaska being conducted by the Los Alamos Scientific Laboratory (LASL). The field collection and treatment of the samples were performed following strict LASL specifications. Total uranium was measured in the waters by fluorometry and in the sediments by delayed-neutron counting, using stringent quality assurance controls at the LASL. The uranium contents of the waters ranged from below the detection limit of 0.02 parts per billion (ppB) to a high of 8.38 ppB, and the uranium contents of the sediments ranged from a low of 0.3 parts per million (ppM) to a high of 34.0 ppM. In general, the locations of waters containing relatively high uranium contents were found to occur in clusters, and particularly in the headwaters of streams draining the southern slopes of the Baird Mountains. Few sediments contained relatively high uranium contents. These usually occurred singly at isolated locations scattered throughout the area. No obvious association exists between the location of high-uranium waters and sediments anywhere in the study area. The geology, mineralogy, and hydrology of this area is only generally described in the literature; therefore, it is difficult to correlate these data with particular aspects of the physical environment where individual samples were collected. However, the data do indicate that certain areas underlaid by Paleozoic sedimentary rocks and granitic intrusives within the Baird Mountains and a quartz-pebble conglomerate in the Waring Mountains may warrant more detailed field ...
Date: May 1, 1978
Creator: Aamodt, P.L.; Hill, D.E. & Sharp, R.R. Jr.
Partner: UNT Libraries Government Documents Department

Uranium Hydrogeochemical and Stream Sediment Reconnaissance Data Release for the Montana Portion of the Hamilton, Montana/Idaho, NTMS Quadrangle

Description: from Summary: This report describes work done in Hamilton, Montanan/Idaho, National Topographic Map Series (NTMS) quadrangle (1:250 000 scale) by the Los Alamos Scientific Laboratory (LASL) as part of the nationwide Hydrogeochemical and Stream Sediment Reconnaissance (HSSR).
Date: March 1978
Creator: Aamodt, Paul L.
Location Info:
Partner: UNT Libraries Government Documents Department

Uranium Hydrogeochemical and Stream Sediment Reconnaissance Data from the Area of the Noatak and Portions of the Baird Mountains and Ambler River Quadrangles, Alaska

Description: From introduction: This report describes work done in the Noatak and portions of the Baird Mountains and Ambler River, Alaska, National Topographic Map Series (NTMS) quadrangles (1:250 000 scale) by the Los Alamos Scientific Laboratory (LASL) as part of the nationwide Hydrogeochemical and Stream Sediment Reconnaissance (HSSR).
Date: May 1978
Creator: Aamodt, Paul L.; Hill, Dwight E. & Sharp, Robert R., Jr.
Partner: UNT Libraries Government Documents Department

TCT hybrid preconceptual blanket design studies

Description: The conceptual design of a tokamak fusion-fission (hybrid) reactor, which produces electric power and fissile material, has been performed in a cooperative effort between Princeton's Plasma Physics Laboratory (PPPL) and Battelle's Pacific Northwest Laboratories (PNL). PPPL, who had overall project lead responsibility, designed the fusion driver system. Its core consists of a tokamak plasma maintained in the two-component torus (TCT) mode by both D and T beams and having a single null poloidal divertor. The blanket concept selected by PPPL consists of a neutron multiplying converter region, containing natural Uranium Molybdenum (U-Mo) slugs followed by a fuel burning blanket region of molten salt containing PuF/sub 3/. PNL analyzed this concept to determine its structural, thermal and hydraulic performance characteristics. An adequate first wall cooling method was determined, utilizing low pressure water in a double wall design. A conceptual layout of the converter region tubes was performed, providing adequate helium cooling and the desired movement of U-Mo slugs. A thermal hydraulic analysis of the power-producing blanket regions indicated that either more helium coolant tubes are needed or the salt must be circulated to obtain adequate heat removal capability.
Date: January 1, 1978
Creator: Aase, D.T.; Bampton, M.C.C.; Doherty, T.J.; Leonard, B.R.; McCann, R.A.; Newman, D.F. et al.
Partner: UNT Libraries Government Documents Department

Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics

Description: A fuel cycle that employs /sup 233/U denatured with /sup 238/U and mixed with thorium fertile material is examined with respect to its proliferation-resistance characteristics and its technical and economic feasibility. The rationale for considering the denatured /sup 233/U fuel cycle is presented, and the impact of the denatured fuel on the performance of Light-Water Reactors, Spectral-Shift-Controlled Reactors, Gas-Cooled Reactors, Heavy-Water Reactors, and Fast Breeder Reactors is discussed. The scope of the R, D and D programs to commercialize these reactors and their associated fuel cycles is also summarized and the resource requirements and economics of denatured /sup 233/U cycles are compared to those of the conventional Pu/U cycle. In addition, several nuclear power systems that employ denatured /sup 233/U fuel and are based on the energy center concept are evaluated. Under this concept, dispersed power reactors fueled with denatured or low-enriched uranium fuel are supported by secure energy centers in which sensitive activities of the nuclear cycle are performed. These activities include /sup 233/U production by Pu-fueled transmuters (thermal or fast reactors) and reprocessing. A summary chapter presents the most significant conclusions from the study and recommends areas for future work.
Date: December 1, 1978
Creator: Abbott, L.S.; Bartine, D.E. & Burns, T.J. (eds.)
Partner: UNT Libraries Government Documents Department

Quantification of erythroid and granulocytic precursor cells in plateletpheresis residues

Description: Mononuclear cell fractions of human blood and plateletpheresis residues were compared for their content of hemopoietic precursor cells. Erythroid burst-forming units (BFU-E) averaged 560 +- 130 per ml of blood and granulocyte--monocyte colony forming units (CFU-C) averaged 240 +- 90 per ml blood. Estimates based on a blood volume of 7% of body weight indicate that the total blood pools of BFU-E and CFU-C are about 3.5 x 10/sup 6/ and 1.5 x 10/sup 6/ cells respectively. Sequential studies were performed over 3 days following one plateletpheresis in 4 donors. CFU-C and BFU-E approximately doubled between 48 and 72 hours after a plateletpheresis. During this time there was no significant alteration in the percent of null, T or B lymphocytes in blood. Thus, plateletpheresis appears to lead to a mobilization of precursor cells, which results in a transient increase in their concentration in blood. Therefore, pheresis 48 to 72 hours after an initial short-term procedure could harvest much larger numbers of precursor cells. Moreover, such techniques would put blood precursor cell content of plateletpheresis residues within reach of the precursor cell content in the volume of human marrow used for transplantation.
Date: January 1, 1978
Creator: Abboud, C.N.; Brennan, J.K.; Lichtman, M.A. & Nusbacher, J.
Partner: UNT Libraries Government Documents Department

MACK/MACKLIB System for Nuclear Response Functions

Description: The MACK computer program calculates energy pointwise and multigroup nuclear response functions from basic nuclear data in ENDF/B format. The new version of the program MACK-IV, incorporates major developments and improvements aimed at maximizing the utilization of available nuclear data and ensuring energy conservation in nuclear heating calculations. A new library, MACKLIB-IV, of nuclear response functions was generated in the CTR energy group structure of 171 neutron groups and 36 gamma groups. The library was prepared using MACK-IV and ENDF/B-IV and is suitable for fusion, fusion-fission hydrids, and fission applications.
Date: March 15, 1978
Creator: Abdou, M. A. & Gohar, Y. M.
Partner: UNT Libraries Government Documents Department

MACK-IV, a new version of MACK: a program to calculate nuclear response functions from data in ENDF/B format

Description: MACK-IV calculates nuclear response functions important to the neutronics analysis of nuclear and fusion systems. A central part of the code deals with the calculation of the nuclear response function for nuclear heating more commonly known as the kerma factor. Pointwise and multigroup neutron kerma factors, individual reactions, helium, hydrogen, and tritium production response functions are calculated from any basic nuclear data library in ENDF/B format. The program processes all reactions in the energy range of 0 to 20 MeV for fissionable and nonfissionable materials. The program also calculates the gamma production cross sections and the gamma production energy matrix. A built-in computational capability permits the code to calculate the cross sections in the resolved and unresolved resonance regions from resonance parameters in ENDF/B with an option for Doppler broadening. All energy pointwise and multigroup data calculated by the code can be punched, printed and/or written on tape files. Multigroup response functions (e.g., kerma factors, reaction cross sections, gas production, atomic displacements, etc.) can be outputted in the format of MACK-ACTIVITY-Table suitable for direct use with current neutron (and photon) transport codes.
Date: July 1, 1978
Creator: Abdou, M. A.; Gohar, Y. & Wright, R. Q.
Partner: UNT Libraries Government Documents Department

Influence of access hole parameters on neutron moisture probe readings

Description: Computing soil moisture content with a neutron probe requires use of a calibration curve that considers the thermal neutron capture cross section of the hole liner as well as the hole diameter. The influence of steel, polyvinyl chloride, and aluminum casings that fit 0.051 to 0.102-hole diameters was determined by comparison with neutron probe readings in uncased holes of corresponding diameters. Eccentricity of probe location was considered a potentially significant variable. The relationship between hole diameter and count rate also was investigated. The experiment was run in disturbed Bandelier tuff with an average dry density of 1.2 g . cm/sup -3/ and moisture content of 1.3 to 35.5% by volume. The casing material and hole diameter influenced the probe readings significantly, whereas eccentric location of the probe did not. Regression analyses showed an almost perfect inverse linear correlation between hole diameter and count rate.
Date: April 1978
Creator: Abeele, Willy V.
Partner: UNT Libraries Government Documents Department

Chemical maximum humidity indicator update report. Topical report

Description: Raw materials and manufactured parts sometimes must be kept in a controlled-humidity environment. The use of moisture-sensitive systems to indicate the maximum level of humidity exposure is discussed. A chemical indicator made from deliquescent salts and water-soluble dyes provides an irreversible color change at discrete levels of relative humidity. The performance and long-term-stability characteristics of the indicator are described.
Date: November 1, 1978
Creator: Abel, W.B.
Partner: UNT Libraries Government Documents Department

Electrical compensation system for plated-through-hole tester. Milestone report

Description: A microprocessor system has been developed to control the acquisition and interpretation of resistance-measurement data from plated-through holes in printed wiring boards. The system provides a direct digital display of the thickness of the copper plating on the hole walls. The complex calibration for holes having different geometries is stored in the memory of the system, and the geometry factors are input through thumbwheel switches. A special probe system makes possible the determination of an average resistance value for each test hole without moving the probe contacts in relation to the hole.
Date: October 1, 1978
Creator: Abel, W.B.
Partner: UNT Libraries Government Documents Department

Reprocessing flowsheet and material balance for MEU spent fuel

Description: In response to nonproliferation concerns, the high-temperature gas-cooled reactor (HTGR) Fuel Recycle Development Program is investigating the processing requirements for a denatured medium-enriched uranium--thorium (MEU/Th) fuel cycle. Prior work emphasized the processing requirements for a high-enriched uranium--thorium (HEU/Th) fuel cycle. This report presents reprocessing flowsheets for an HTGR/MEU fuel recycle base case. Material balance data have been calculated for reprocessing of spent MEU and recycle fuels in the HTGR Recycle Reference Facility (HRRF). Flowsheet and mass flow effects in MEU-cycle reprocessing are discussed in comparison with prior HEU-cycle flowsheets.
Date: October 1, 1978
Creator: Abraham, L.
Partner: UNT Libraries Government Documents Department

PL/I programming language

Description: PL/I is a large and powerful multipurpose programming language, designed for use in business and in scientific applications as well as in systems programming applications such as writing operating systems. The data types, declarations, expressions, type conversion, and assignment, storage types, procedures, scopes, and environments, on-units and on-statements, other statements affecting flow of control, files and record input--output, and stream input--output are set forth. 9 references. (JFP)
Date: March 1, 1978
Creator: Abrahams, P
Partner: UNT Libraries Government Documents Department

Triggering at Isabelle; the first 200 nanoseconds

Description: At full luminosity of ISABELLE and with an anticipated pp total cross section of 60 mb, there will be, on the average, one interaction every 70 ns. At the other end of the spectrum, it will probably take about 10 ms to store a complete event onto magnetic tape. In between these two extremes comes a triggering scheme which must select the one event out of 14,285,714 that is of interest to the experimenter. In a typical experiment, a certain small number of signals will come into an electronics trailer on cables that are as short as possible and have propagation velocities as high as possible. With these signals a fast decision will be made as to whether the rest of the information coming in on the slower, longer cables should be further processed or not. The typical length of time for this decision is 200 ns. Some of the problems arising during that first 200 ns are considered, and some examples of attempts to solve those problems are given.
Date: July 1, 1978
Creator: Abshire, G.; Kondo, K.; Sculli, J.; Johnson, R.A. & Morris, G.R.
Partner: UNT Libraries Government Documents Department

Optical probe for local void fraction and interface velocity measurements. [BWR; PWR]

Description: In view of the importance of obtaining unsteady local void fraction and interface velocities in liquid-vapor two-phase flows, an optical probe with a controlled tip geometry was developed and is described. In order to minimize the disturbances caused to the flow field by the presence of the probe, its dimensions have been miniaturized. The electronic and hydrodynamic response of the probe were investigated experimentally. The probe was found to be sensitive to both the interface velocities and the phase present at the probe tip. A possible explanation for the behavior of the probe is presented. Within the velocity range checked and with proper calibration, the optical probe developed can be used to determine both local void fractions and interface velocities.
Date: March 1, 1978
Creator: Abuaf, N.; Jones, O.C. Jr. & Zimmer, G.A.
Partner: UNT Libraries Government Documents Department

Advanced Fuel Cell Development Progress Report: October-December 1977

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes work aimed at understanding and improving the performance of fuel cells having molten alkali-carbonate mixtures as electrolytes; the fuel cells operate at temperatures near 925 K.
Date: March 1978
Creator: Ackerman, J. P.; Kinoshita, K.; Finn, P. A.; Sim, J. W. & Nelson, P. A.
Partner: UNT Libraries Government Documents Department

Advanced Fuel Cell Development Progress Report: April-June 1978

Description: Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward understanding and improving the components of molten-carbonate-electrolyte fuel cells operated at temperatures near 925 K.
Date: August 1978
Creator: Ackerman, J. P.; Pierce, Robert Dean; Nelson, P. A.; Arons, R. M.; Kinoshita, K.; Sim, J. W. et al.
Partner: UNT Libraries Government Documents Department

Advanced fuel cell development. Progress report, October--December 1977. [LiAlO/sub 2/ matrix for molten carbonate electrolytes]

Description: Advanced fuel cell research and development activities in Argonne National Laboratory (ANL) during the period October to December 1977 are described. This work has been aimed at understanding and improving the performance of fuel cells having molten alkali-carbonate mixtures as electrolytes; the fuel cells operate at temperatures near 925/sup 0/K. The largest part of this effort has been directed toward development of methods for fabricating and evaluating electrolyte structures for these cells. Cell performance, life, and cost are the criteria of optimization. During this quarter, the desirable physical characteristics of LiAlO/sub 2/ particles, which act to retain the molten carbonates in the electrolyte structure of the cell, have been more clearly defined; a low temperature synthesis of the stable ..gamma..-allotrope of LiAlO/sub 2/ has been devised; an extensive study of LiAlO/sub 2/ stability has begun; and analytical methods have been refined for separating LiAlO/sub 2/, in unaltered form, from carbonates. Testing of various electrolyte structures and other components in 7-cm-dia round cells has provided a means for evaluating new electrolyte developments and verifying a previously developed method for protecting the wet-seal areas of a cell from corrosion.
Date: March 1, 1978
Creator: Ackerman, J.P.; Kinoshita, K.; Finn, P.A.; Sim, J.W. & Nelson, P.A.
Partner: UNT Libraries Government Documents Department

Habitat Development Field Investigations, Windmill Point Marsh Development Site, James River, Virginia: Appendix F, Volume 2

Description: From preface: "This report contains the results of investigations of the chemical and sedimentological characteristics of the James River Artificial Habitat Development Site and a reference marsh near Windmill Point, Virginia. Studies were conducted in the channel before dredging and during site construction as well as at specific time intervals after marsh development."
Date: August 1978
Creator: Adams, Donald D.; Darby, Dennis A. & Young, Randolph J.
Partner: UNT Libraries Government Documents Department