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Comparison of ICEPEL predictions with single elbow flexible piping system experiment
The ICEPEL Code for coupled hydrodynamic-structural response analysis of piping systems is used to analyze an experiment on the response of flexible piping systems to internal pressure pulses. The piping system consisted of two flexible Nickel-200 pipes connected in series through a 90/sup 0/ thick-walled stainless steel elbow. A tailored pressure pulse generated by a calibrated pulse gun is stabilized in a long thick-walled stainless steel pipe leading to the flexible piping system which ended with a heavy blind flange. The analytical results of pressure and circumferential strain histories are discussed and compared against the experimental data obtained by Stanford Research Institute.
Date:
January 1, 1978
Creator:
A-Moneim, M.T. & Chang, Y.W.
Object Type:
Article
System:
The UNT Digital Library
Uranium hydrogeochemical and stream sediment reconnaissance data from the area of the Noatak and portions of the Baird Mountains and Ambler River Quadrangles, Alaska
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 …
Date:
May 1, 1978
Creator:
Aamodt, Paul L.; Hill, Dwight E. & Sharp, Robert R., Jr.
Object Type:
Report
System:
The UNT Digital Library
Anomalous fracture-extension pressure in granitic rocks
Fracture-extension pressures appreciably higher than the least principal earth-stress were observed in hydraulic fractures formed in a pair of 3 km (9600 ft) deep boreholes drilled near the Valles Caldera in northern New Mexico. Pressurization of open wellbores in rock containing preexisting fractures may open these fractures, instead of creating new fractures at right angles to the least principal stress. The pressure necessary to flow into these fractures may be appreciably higher than the least principal stress. Upon sand-propping one such pre-existing fracture, a lower fracture extension pressure was observed. A second fracture in a parallel well-bore 92 m (300 ft) away, at the same depth of 2 km (6500 ft) exhibited the lower fracture extension pressure without propping, but with about 90/sup 0/ difference in fracture direction. Fractures created through perforations at a depth of 3 km (9600 ft) not only exhibited breakdown pressures upon initial pressurization, but sometimes even higher ''breakdown'' pressures upon repressurization. These phenomena may be of interest in the interpretation of earth stress measurements made by hydraulic fracturing.
Date:
January 1, 1978
Creator:
Aamodt, R. L. & Potter, R. M.
Object Type:
Article
System:
The UNT Digital Library
Cermets for high level waste containment
Cermet materials are currently under investigation as an alternate for the primary containment of high level wastes. The cermet in this study is an iron--nickel base metal matrix containing uniformly dispersed, micron-size fission product oxides, aluminosilicates, and titanates. Cermets possess high thermal conductivity, and typical waste loading of 70 wt % with volume reduction factors of 2 to 200 and low processing volatility losses have been realized. Preliminary leach studies indicate a leach resistance comparable to other candidate waste forms; however, more quantitative data are required. Actual waste studies have begun on NFS Acid Thorex, SRP dried sludge and fresh, unneutralized SRP process wastes.
Date:
January 1, 1978
Creator:
Aaron, W. S.; Quinby, T. C. & Kobisk, E. H.
Object Type:
Article
System:
The UNT Digital Library
TCT hybrid preconceptual blanket design studies
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.
Object Type:
Report
System:
The UNT Digital Library
Using field theory in hadron physics
Topics are covered on the connection of field theory and hadron physics. The renormalization group and infrared and ultraviolet limits of field theory, in particular quantum chromodynamics, spontaneous mass generation, color confinement, instantons, and the vacuum state in quantum chromodynamics are treated. 21 references. (JFP)
Date:
March 1, 1978
Creator:
Abarbanel, H.D.I.
Object Type:
Article
System:
The UNT Digital Library
Interim assessment of the denatured /sup 233/U fuel cycle: feasibility and nonproliferation characteristics
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.)
Object Type:
Report
System:
The UNT Digital Library
Quantification of erythroid and granulocytic precursor cells in plateletpheresis residues
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.
Object Type:
Report
System:
The UNT Digital Library
MACK-IV, a new version of MACK: a program to calculate nuclear response functions from data in ENDF/B format
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.
Object Type:
Report
System:
The UNT Digital Library
Chemical maximum humidity indicator update report. Topical report
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.
Object Type:
Report
System:
The UNT Digital Library
Electrical compensation system for plated-through-hole tester. Milestone report
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.
Object Type:
Report
System:
The UNT Digital Library
Simplified inelastic analysis methods applied to fast breeder reactor core design
The paper starts with a review of some currently available simplified inelastic analysis methods used in elevated temperature design for evaluating plastic and thermal creep strains. The primary purpose of the paper is to investigate how these simplified methods may be applied to fast breeder reactor core design where neutron irradiation effects are significant. One of the problems discussed is irradiation-induced creep and its effect on shakedown, ratcheting, and plastic cycling. Another problem is the development of swelling-induced stress which is an additional loading mechanism and must be taken into account. In this respect an expression for swelling-induced stress in the presence of irradiation creep is derived and a model for simplifying the stress analysis under these conditions is proposed. As an example, the effects of irradiation creep and swelling induced stress on the analysis of a thin walled tube under constant internal pressure and intermittent heat fluxes, simulating a fuel pin, is presented.
Date:
January 1, 1978
Creator:
Abo-El-Ata, M. M.
Object Type:
Article
System:
The UNT Digital Library
Reprocessing flowsheet and material balance for MEU spent fuel
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.
Object Type:
Report
System:
The UNT Digital Library
PL/I programming language
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
Object Type:
Report
System:
The UNT Digital Library
Triggering at Isabelle; the first 200 nanoseconds
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.
Object Type:
Report
System:
The UNT Digital Library
Optical probe for local void fraction and interface velocity measurements. [BWR; PWR]
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.
Object Type:
Report
System:
The UNT Digital Library
Advanced fuel cell development. Progress report, October--December 1977. [LiAlO/sub 2/ matrix for molten carbonate electrolytes]
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.
Object Type:
Report
System:
The UNT Digital Library
Preparation and characterization of radioactive samples for various areas of research
Over the past few years, many techniques have been applied by IRML to prepare radioisotope targets and related research materials from actinide and other radioisotopes. Many of these samples were prepared by ceramic technology--an R and D program extending over the past three years. Standard vapor deposition methods have been used to prepare hundreds of fission chamber and other planar samples used in determining cross sections. Refined methods of characterization of all samples have been applied to assure definition of contents to as low as +-0.5% in some cases. Tritium-containing target preparation in support of high yield neutron generators (10/sup 12/ to 10/sup 13/ n/s) has been a continuing development effort both in manufacturing technology and in measurement of tritium content. Of all, however, the largest effort has been development and characterization of neutron dosimetry materials and samples useful for measurement of energy and fluence in reactor core and reflector regions. These dosimeter samples are available for monitoring LWR, CTR, and fast reactor systems.
Date:
January 1, 1978
Creator:
Adair, H.L.
Object Type:
Article
System:
The UNT Digital Library
Methodologies for assessment of power plant ecological effects in the marine environment
Various types of models or methodologies relevant to the assessment of entrainment, thermal, and impingement impacts of power plant operation in the marine environment are presented. The majority of methodologies available for assessing power plant effects are focused at the organism or population level. The most widely applied approaches for estimating entrainment effects on fish populations are the equivalent adult and trophic-conversion methodologies. Current methods to predict the number of fish and distribution of species impinged consider physical factors of the environment but not the biological or behavorial characteristics of fish. With proper validation, ecosystem-level models that consider aggregate responses of biological components to stress may prove to be a viable approach for investigating power plant ecological effects.
Date:
January 1, 1978
Creator:
Adams, S.M.
Object Type:
Article
System:
The UNT Digital Library
Light curves for ''bump Cepheids'' computed with a dynamically zoned pulsation code
The dynamically zoned pulsation code developed by Castor, Davis, and Davison has been used to recalculate the Goddard model and to calculate three other Cepheid models with the same period (9.8 days). This family of models shows how the bumps and other features of the light and velocity curves change as the mass is varied at constant period. This study, with a code that is capable of producing reliable light curves, shows again that the light and velocity curves for 9.8-day Cepheid models with standard homogeneous compositions do not show bumps like those that are observed unless the mass is significantly lower than the ''evolutionary mass.'' The light and velocity curves for the Goddard model presented here are similar to those computed independently by Fischel, Sparks, and Karp. They should be useful as standards for future investigators.
Date:
January 1, 1978
Creator:
Adams, T. F.; Castor, J. E. & Davis, C. G.
Object Type:
Article
System:
The UNT Digital Library
Theoretical light and velocity curves for Cepheid variables. [Nonlinear models]
New Research Initiatives Program W-318 was successfully completed with the calculation of a series of nonlinear Cepheid models with the new DYN code. The dynamical zoning feature of the DYN code makes it unique in that it allows reliable light curves, as well as velocity curves, to be calculated. The models are used to extend to light curves Christy's conclusion, based on velocity curves, that the observations of Cepheids cannot be matched unless the mass is significantly reduced (assuming a homogeneous composition). An examination of results also leads to the conclusion that observed light curves are considerably more complex than has previously been thought. The light and velocity curves we have calculated should be useful guides for interpreting the observations. 36 references.
Date:
December 1, 1978
Creator:
Adams, T. F.; Davis, C. G. & Keller, C. F.
Object Type:
Report
System:
The UNT Digital Library
Harvard--MIT research program in short-lived radiopharmaceuticals. Progress report, September 1, 1977--April 30, 1978. [/sup 99m/Tc, positron-emitting radionuclides]
Progress is reported on the following studies: chemistry studies designed to achieve a more complete understanding of the fundamental chemistry of technetium in order to facilitate the design of future radiopharmaceuticals incorporating the radionuclide /sup 99m/Tc; the development of new radiopharmaceuticals intended to improve image quality and lower radiation doses by the use of short-lived radionuclides and disease-specific agents; the development of short-lived positron-emitting radionuclides which offer advantages in transverse section imaging of regional physiological processes; and studies of the toxic effects of particulate radiation.
Date:
May 1, 1978
Creator:
Adelstein, S. J. & Brownell, G. L.
Object Type:
Report
System:
The UNT Digital Library
Model for magnetic reconnection
A forced reconnection problem was modeled by two infinite wires that are embedded in a plasma which carry parallel currents. They are brought together at a specified rate. The distance between the wires is taken as 2a(1-e/sup ..omega..t/). For small displacements, the hydromagnetic equations can be linearized and solved asymptotically. For larger displacements, the plasma behavior can be estimated by use of scaling arguments. We determine a local velocity of magnetic reconnection and show that it is essentially equal to the maximum possible reconnection velocity (that of the corresponding vacuum case) up to the time when this velocity approaches the local Alfven speed. We compare the details of our solution with the Sweet-Parker and Petschek reconnection theories.
Date:
March 1, 1978
Creator:
Adler, E. A. & Kulsrud, R. M.
Object Type:
Report
System:
The UNT Digital Library
Flaw location and characterization in anisotropic materials by ultrasonic spectral analysis
A method of quantitatively determining size and location of flaws in anisotropic materials such as stainless steel welds is described. In previous work, it was shown that spectral analysis of a broad band ultrasonic pulse scattered from a defect can be used to determine size and orientation in isotropic materials if the velocity of sound in the material is known. In an anisotropic structural material (stainless steel weld, centrifugal cast pipe), the velocity (both shear and longitudinal) is direction-dependent. When anisotropy is not taken into account, defect location and defect size estimation is misjudged. It will be shown that the effect of this structural variation in materials must be considered to obtain the correct size and location of defects by frequency analysis. A theoretical calculation, including anisotropy, of the scattered field from defects will also be presented.
Date:
January 1, 1978
Creator:
Adler, L.; Cook, K. V.; Simpson, W. A. & Lewis, D. K.
Object Type:
Article
System:
The UNT Digital Library