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Note on the cryostatic stability of superconducting composites
A careful discussion is given of the ''equal area condition'' developed by Maddock et al. In order to make the essential points as clear as possible, analytical solutions are derived under simplifying assumptions (simple model for heat transfer by nucleate and film boiling liquid helium; constant heat conduction and specific heat) instead of using more realistic but less controllable computer calculations. A quantitative definition of the concept of a long wire is given. Numerical examples for the Maddock transition characterized by the equal area condition are given for a long superconducting composite with linear cooling and for a liquid helium-cooled resistance wire of finite length. In addition, cases are shown where instead of applying the equal area stability condition, time-dependent solutions should be considered.
Date:
February 1, 1978
Creator:
Gauster, W. F.
Object Type:
Report
System:
The UNT Digital Library
Pacific Northwest Laboratory, annual report for 1983 to the DOE Office of Energy Research. Part 4. Physical sciences
Part 4 of the Pacific Northwest Laboratory Annual Report for 1983 to the Office of Energy Research, includes those programs funded under the title Physical and Technological Research. The Field Task Program Studies reports in this document are grouped under the subheadings and each section is introduced by a divider page that indicates the Field Task Agreement reported in that section. These reports only briefly indicate progress made during 1983. The reader should contact the principal investigators named or examine the publications cited for more details.
Date:
February 1, 1984
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
NRC plan for cleanup operations at Three Mile Island Unit 2
This NRC Plan, which defines NRC's functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC's regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC's review and approval process with regard to cleanup operations as well as NRC's interface with the Department of Energy's involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC's role in ongoing and future cleanup activities.
Date:
February 1, 1982
Creator:
Lo, R. & Snyder, B.
Object Type:
Report
System:
The UNT Digital Library
First wall/blanket/shield design and optimization system
First wall/blanket/shield design and optimization system (BSDOS) has been developed to provide a state-of-the-art design tool for fast accurate analysis. In addition, it has been designed to perform several other functions: (1) allowing comparison and evaluation studies for different concepts using the same data bases and ground rules, (2) permitting the use of any figure of merit in the evaluation studies, (3) optimizing the first wall/blanket/shield design parameters for any figure of merit under several design constraints, (4) permitting the use of different reactor parameters in the evaluation and optimization analyses, (5) allowing the use of improved eingineering data bases to study the impact on the design performance for planning future research and development, and (6) evaluating the effect of the data base uncertainties on the design performance. BSDOS is the first design and optimization system to couple the highly interacting neutronics, heat transfer, thermal hydraulics, stress analysis, radioactivity and decay-heat analyses, tritium balance, and capital cost. A brief description of the main features of BSDOS is given in this paper. Also, results from using BSDOS to perform design analysis for several reactor components are presented. 17 refs., 1 fig., 2 tabs.
Date:
February 1, 1988
Creator:
Gohar, Y.; Baker, C.; Attaya, H.; Cha, Y.; Majumdar, S. & Scandora, T.
Object Type:
Article
System:
The UNT Digital Library
Safety rod latch inspection
During an attempt to raise control rods from the 100 K reactor in December, one rod could not be withdrawn. Subsequent investigation revealed that a small button'' in the latch mechanism had broken off of the lock plunger'' and was wedged in a position that prevented rod withdrawal. Concern that this failure may have resulted from corrosion or some other metallurgical problem resulted in a request that SRL examine six typical latch mechanisms from the 100 L reactor by use of radiography and metallography. During the examination of the L-Area latches, a failed latch mechanism from the 100 K reactor was added to the investigation. Fourteen latches that had a history of problems were removed from K-Area and sent to SRL for inclusion in this study the week after the original seven assemblies were examined, bringing the total of latch assemblies discussed in this report to twenty one. Results of the examination of the K-Area latch that initiated this study is not included in this report.
Date:
February 1, 1992
Creator:
Leader, D.R.
Object Type:
Report
System:
The UNT Digital Library
DOE role in nuclear policies and programs: official transcript of public briefing. Addendum December 13, 1977, Washington, D. C
A total of 24 questions were read into the official record at the public briefing on nuclear policies and programs. The answers published were researched and written by personnel of DOE's Office of Energy Research, Office of Energy Technology, and the Secretary's Office. A few questions were sent to the Nuclear Regulatory Commission for review and for preparation of answers.
Date:
February 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Boundary element formulation for planar time-dependent inelastic deformation of plates with cutouts
A boundary element formulation for planar, time-dependent, inelastic deformation problems for bodies with cutouts is presented in this paper. A stress function description for these nonlinear problems leads to a nonhomogeneous biharmonic equation for the stress function rate. An integral representation of the solution uses modified kernels which guarantee that the cutout boundary is traction free for all time. This incorporation of the effect of the cutout on the stress field into the kernels leads to an accurate determination of stresses in the near field of the cutout. Illustrative analytical examples for circular plates with circular cutouts are presented in this paper. In a companion paper, numerical solutions are presented for problems of finite plates with very narrow elliptic cutouts. These problems are of considerable importance in inelastic fracture.
Date:
February 1, 1980
Creator:
Mukherjee, S. & Morjaria, M.
Object Type:
Report
System:
The UNT Digital Library
Extracted current densities from surface conversion sources of negative ions
The condition for extracting a maximum negative ion current density is found when the product of the radius of the negative ion conversion electrode, the cross-section for negative and positive ion recombination, and the density of positive ions in the ion source equals one. The optimum output is obtained at the highest positive ion density and the smallest electrode radius.
Date:
February 10, 1982
Creator:
Fink, J.H.
Object Type:
Report
System:
The UNT Digital Library
SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR]
The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-dimensional steady state solution scheme to initialize the flow field, (b) steady state and transient fuel rod conduction models, and (c) comprehensive correlation packages to describe fluid-to-fuel rod interfacial energy and momentum exchange. Velocity and pressure boundary conditions can be specified as a function of time and space to model reactor transient conditions such as a hypothesized loss-of-coolant accident (LOCA) or flow blockage.
Date:
February 1, 1978
Creator:
Benedetti, R. L.; Lords, L. V. & Kiser, D. M.
Object Type:
Report
System:
The UNT Digital Library
Geostatistics project of the National Uranium Resource Evaluation program
Additional work has been done to display radiometric data from the Lubbock quadrangle in pseudocolor maps. A digitized topographic map of the quadrangle was obtained from the U.S. Geological Survey and this is being incorporated into the study of the radiometric data. Single-record data from the Lake Mead calibration range and from the Slayton test line have been obtained from GeoMETRICS: Inc. and analysis of this data has begun. Principal component analyses have been used to investigate the relationship of geological formation to the location of points in a (Tl, Bi, K) coordinate system. LASL personnel attended a workshop in Grand Junction, Colorado, where some of the problems of calibrating aerial gamma-ray spectrometers were addressed.
Date:
February 1, 1978
Creator:
Bement, T.R.; McKay, M.D. & Wecksung, G.W.
Object Type:
Report
System:
The UNT Digital Library
Energy Program annual report
The national economy is particularly dependent on efficient electrical generation and transportation. Electrical demand continues to grow and will increasingly rely on coal and nuclear fuels. The nuclear power industry still has not found a solution to the problem of disposing of the waste produced by nuclear reactors. Although coal is in ample supply and the infrastructure is in place for its utilization, environmental problems and improved conversion processes remain technical challenges. In the case of transportation, the nation depends almost exclusively on liquid fuels with attendant reliance on imported oil. Economic alternates---synfuels from coal, natural gas, and oil shale, or fuel cells and batteries---have yet to be developed or perfected so as to impact the marketplace. Inefficiencies in energy conversion in almost all phases of resource utilization remain. These collective problems are the focus of the Energy Program.
Date:
February 1, 1988
Creator:
Borg, I.Y. (ed.)
Object Type:
Report
System:
The UNT Digital Library
Modeling studies on the precipitation of Kr after implantation into metals
A rate-theory approach is applied to interpreting observations on the precipitation of Kr injected into Ni at temperatures between 25 and 560/degree/C. At temperatures of 400/degree/C or higher, the implanted Kr precipitates evolve into a bi-modal size distribution containing small solid precipitates and an additional population of larger, faceted bubbles. The calculations explore the dependence of the observed bi-modal distribution on the maximum size of the solid Kr precipitates and the effect of this dependence on bubble mobility. The analysis suggests that during the irradiation, whereas the large bubbles move by surface diffusion, the solid Kr precipitates are immobile. The relevance of the Kr-Ni interaction on the solid Kr precipitates size cutoff is discussed. 18 refs., 8 figs., 2 tabs.
Date:
February 1, 1988
Creator:
Rest, J.
Object Type:
Article
System:
The UNT Digital Library
EPICS System: An Overview
This paper presents an overview of the EPICS control system at FERMILAB. EPICS is a distributed, multi-user, interactive system for the control and monitoring of particle beamlines at a high-energy experimental physics laboratory. The overview discusses the operating environment of the control system, the requirements which determined the design decisions, the hardware and software configurations, and plans for the future growth and enhancement of the present system. This paper is the first of three related papers on the EPICS system. The other two cover (1) the system structure and user interface and (2) RSX implementation issues.
Date:
February 1, 1984
Creator:
Bartlett, J. F.; Bobbitt, J. S.; Kramper, B. J.; Lahey, T. E.; MacKinnon, B. A. & West, R. E.
Object Type:
Article
System:
The UNT Digital Library
Resonant decay of finite extent cold electron plasma waves
The parametric decay of a finite extent cold electron plasma wave (slow wave) was studied experimentally. Using a frequency of ..omega../sub 0/ approximately greater than 10..omega../sub pi/, it was found that the decay waves propagated along the pump wave rather than in the Vector E/sub 0/ x Vector B direction. This is in agreement with the recent theoretical predictions of finite length stabilization.
Date:
February 1, 1978
Creator:
Wong, K. L.; Bellan, P. & Porkolab, M.
Object Type:
Report
System:
The UNT Digital Library
Analysis of fission product behavior in the Saclay Spitfire Loop Test SSL-1. [HTGR]
The behavior of the fission metal cesium and the fission gases krypton and xenon in the Saclay Spitfire Loop SSL-1 test has been compared to that predicted using General Atomic reference data and computer code models. This is the first in a series of analyses planned in order to provide quantitative validation of HTGR fission product design methods. In this analysis, the first attempt to rigorously verify fission product design methods, the FIPERQ code was used to model the diffusion of cesium graphite and release to the coolant stream. The comparisons showed that the cesium profile shape in the graphite web and the partition coefficient between fuel rod matrix material and fuel element graphite were correctly modeled, although the overall release was significantly underpredicted. Uncertainties in the source term (fissile particle failure fraction) and total release to the coolant precluded an accurate appraisal of the validity of FIPERQ. However, several recommendations are presented to improve the applicability of future in-pile test data for the validation of fission metal release codes. The half-life dependence of fission gas release during irradiation was found to be in good agreement with the model used in the reference design materials, providing assurance that this aspect …
Date:
February 1, 1978
Creator:
Jensen, D. D.; Haire, M. J. & Ballagny, A.
Object Type:
Report
System:
The UNT Digital Library
Statistical fluctuations in heavy-ion collisions
The relevance of the statistical equilibrium limit to the description of substantially relaxed degrees of freedom is discussed. Fluctuations are considered specifically in the following processes: the correlation between entrance-channel angular momentum and exit-channel kinetic energy; the sharing of the dissipated kinetic energy between the two fragments; the magnitude and the alignment of the fragment angular momentum including the effect of shell structure. It is found that statistical fluctuations play a major role and that the statistical equilibrium limit seems to have been reached for a number of degrees of freedom.
Date:
February 1, 1982
Creator:
Moretto, Luciano G.
Object Type:
Article
System:
The UNT Digital Library
Fusion energy development: Breakeven and beyond: Keynote address
The scientific feasibility, technological inevitability, and economic necessity of fusion as an energy source are discussed.
Date:
February 1, 1988
Creator:
Furth, H.P.
Object Type:
Article
System:
The UNT Digital Library
Operating manual for the de Phanger precision long counter (PLC)
The setting up, calibration operation, characteristics, and problems of the precision long counter for neutron intensity measurements are discussed. (WHK)
Date:
February 6, 1978
Creator:
Slaughter, D.
Object Type:
Report
System:
The UNT Digital Library
Thermophysical properties of argon
The entire report consists of tables of thermodynamic properties (including sound velocity, thermal conductivity and diffusivity, Prandtl number, density) of argon at 86 to 400/degree/K, in the form of isobars over 0.9 to 100 bars. (DLC)
Date:
February 1, 1988
Creator:
Jaques, A.
Object Type:
Report
System:
The UNT Digital Library
Ceramic microstructures and their elucidation by imaging, diffraction and spectroscopic methods
The development and potential utilization of ceramic materials is dependent on a systematic effort involving processing, characterization and appropriate property measurements. The methods of characterization are numerous and it is important to employ the one that is appropriate to the problem both in terms of its information content and the achievable level of resolution. With the incorporation of fine probe forming capabilities in a transmission electron microscope and the development of related diffraction, imaging and spectroscopic methods, it is now possible to obtain structural and chemical information from the same region of the sample at high spatial resolution. In this review, recent advances along with representative examples in the application of high resolution electron microscopy (HREM), convergent beam electron diffraction (CBED), low atomic number element microanalysis by x-ray emission spectroscopy (XES), fine structures in electron energy-loss spectroscopy (EELS) and specific site occupancy determination by channeling experiments are discussed.
Date:
February 1, 1992
Creator:
Kirshnan, K.M.
Object Type:
Article
System:
The UNT Digital Library
Kilowatt Isotope Power System: component test report for the ground demonstration system pump. 77-KIPS-99
The purpose of this test was to demonstrate that the pump utilized for the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) fulfilled the requirements of Test Procedure 398A, Component Test Procedure for the Ground Demonstration System Pump. The results of the tests are reported. From these results it was concluded that the pump for the Kilowatt Isotope Power System has satisfactorily completed the requirements of Sundstrand Pump Test Procedure, TP 398A.
Date:
February 8, 1978
Creator:
Brainard, E.L.
Object Type:
Report
System:
The UNT Digital Library
DAS performance analysis
This report begins with an overview of the Data Acquisition System (DAS), which supports several of PPPL's experimental devices. Performance measurements which were taken on DAS and the tools used to make them are then described.
Date:
February 1, 1984
Creator:
Bates, G.; Bodine, S.; Carroll, T. & Keller, M.
Object Type:
Report
System:
The UNT Digital Library
The safety record at the tritium systems test assembly
This work addresses an important objective of the TSTA-demonstrating that the large tritium inventories required for fusion reactors can be routinely handled, without radiation exposure to operating personnel and without significant environemtnal releases. The techniques by which TSTA has achieved low releases and personnel exposures include high-integrity primary piping systems that exclude contact between tritium and organic materials, a secondary containment system that encloses all primary tritium piping in a controlled environment, an efficient, all-purpose tritium waste-treatment plant with 100% availability, and ultrasensitive, real-time diagnostics for anticipating and preventing releases, and for detection and location of tritium leaks in a low-risk mode. 5 refs., 11 figs., 2 tabs.
Date:
February 1, 1988
Creator:
Coffin, D.O.
Object Type:
Article
System:
The UNT Digital Library
Western Gas Sands Project. Status report
The progress during December, 1977 of the major government sponsored endeavors undertaken to increase gas production from the low permeability gas sands of the western United States is summarized. The USGS is continuing geological and geophysical studies in the four major western basins to better characterize the resource base. Shipping arrangements for the core donated to the USGS by Inexco WASP (a well drilled for possible nuclear explosive stimulation in Wyoming) have been made, and cores for macrofossil and ostracode analysis from the Bowdoin Dome area have been collected. The National Laboratories, funded by DOE, are continuing their work in the area of research and development. The emphasis is on the development of new tools and instrumentation systems, rock mechanics, mathematical modeling and data analysis. Field tests and demonstrations active in the Uinta and Piceance Basins are Gas Producing Enterprises (GPE) Natural Buttes, Wells No. 14, 18, 19, 20, 21, and 22; Mobil Research and Development, Well No. F-31-13G; and Rio Blanco Natural Gas Company, Well No. 498-4-1. Colorado Interstate Gas Company has initiated activity on its project with the installation of equipment, and Mitchell Energy Company's proposal to conduct an MHF test in the Cotton Valley lime gas reservoir …
Date:
February 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library