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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.
System:
The UNT Digital Library
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy. Final Report
The objectives of the SNAP 7A program were to design, manufacture, test, and deliver a five-watt electric generation system for a U. S. Coast Guard 8 x 26E light buoy. The 10-watt Sr/sup 90/ thermoelectric generator, the d-c-to-d-c converter, batteries and the method of installation in the light buoy are describcd. The SNAP 7A generator was fueled with four capsules containing a total of 40,800 curies of Sr/sup 90/ titanate. After fueling and testing, the SNAP 7A electric generating system was installed in the Coast Guard light buoy at Baltimore, Maryland, on December 15, 1961. Operation of the buoy lamp is continuous. (auth)
Date:
February 1, 1962
Creator:
unknown
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
System:
The UNT Digital Library
GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961
Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced power plants, experimental investigations of heat transfer and fluid flow, development of equipment anmd test facilities. and fabrication studies. (M.C.G.)
Date:
February 1, 1962
Creator:
unknown
System:
The UNT Digital Library
Examination of Uranium-2 w/o Zirconium Experimental Fuel Slugs Irradiated in EBR-I. Final Report-Program 6.1.11
Six groups of U-2 wt% Zr fuel slugs were irradiated in the first core of the EBR-I to burnups of 0.080 to 0.189 at.% at calculated temperatures of 307 to 353 deg C. Two groups of cast specimens were found to be more dimensionally stable than four groups of wrought slugs. Of the wrought slungs, the as quenched group showed less tendency to grow than the three groups which had some annealing after quenching. Specimens at burnups of about 0.189 at.% and at 383 deg C showed the onset of swelling as indicated by density measurements. The hardnesses of these specimens seemed but little affected by radiation, but there was an indication of softening with increasing irradiation temperature. (auth)
Date:
February 1, 1962
Creator:
Murphy, W. F.; Klank, A. C. & Paine, S. H.
System:
The UNT Digital Library
Peregrine Falcon study. Final report
Three papers are included. A separate abstract was prepared for each. (MHR)
Date:
February 1, 1980
Creator:
unknown
System:
The UNT Digital Library
HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20
Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)
Date:
February 1, 1961
Creator:
Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
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.
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.
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
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.
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.
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.
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.)
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.
System:
The UNT Digital Library
Structural materials for breeder reactor cores and coolant circuits
The structural components of principal interest in LMFBR cores and cooling circuits include the reactor vessel, primary and secondary piping, intermediate heat exchanger (IHX), and steam generator. Load-bearing components inside the vessel, among these the fuel cladding and duct, are also included. The operating conditions present in a fast-breeder nuclear reactor impose a number of requirements on the mechanical, physical, and neutronic properties of the materials used to construct these components.
Date:
February 1, 1984
Creator:
Diercks, D. R.
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.
System:
The UNT Digital Library
KINETIC EXPERIMENTS ON WATER BOILERS-"A" CORE REPORT-PART II. ANALYSIS OF RESULTS
The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program utilizes the space-independent neutron kinetics equations with any number of delayed neutron groups to determine the reactivity in the reactor from the power and its derivative. The third program solves the space-independent kinetics equations for the neutron flux from an input reactivity or initial period. Up to 50 reactivity feedback equations includirg delayed neutrons are provided for in this program. A mathematical model of the reactor investigated extensively was one containing six delayed neutron groups, conventional treatment of temperature reactivity compensation, and void compensation of reactivity induced by radiolytic gas void growth proportional to the product of reactor power and energy release. Partial mathematical solutions to the kinetic equations were derived for reactivity feedback proportional to prompt temperature and void growth according to the product of power …
Date:
February 1, 1962
Creator:
Dunenfeld, M. comp.
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.
System:
The UNT Digital Library
Electrotransport of interstitial solutes in titanium. [C, N, O in. beta. -Ti at 1335 to 1575/sup 0/C]
None
Date:
February 1, 1975
Creator:
Lichtenberg, R.R.
System:
The UNT Digital Library
Management and organizational assessments: a review of selected organizations
This report is part of a larger project designed to assist the NRC in its responsibilities for assessing the management and organization of utilities applying for an operating license for a nuclear power plant. This report reviews the processes and criteria used by other organizations that conduct management and organization audits and evaluations. It was undertaken in order to provide data and a basis for future analysis by taking a comparative perspective. When considering changes in criteria and procedures as the NRC is doing, a standard benchmark is the performance of other organizations that are similarly situated. It was our goal to directly inform the NRC about the activities of other organizations so that a reconsideration of NRC activities could benefit from the perspective of organizations with a longer, broader, and different experience than the NRC has in the management and organization area. Data collected for this report has provided useful information in designing organization and administration guidelines and assessment procedures for consideration by the NRC.
Date:
February 1, 1984
Creator:
Nadel, M. V. & Kerwin, C. M.
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.
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
System:
The UNT Digital Library
NQR-NMR studies of higher alcohol synthesis Cu-Co catalysts
Methods of preparation of the copper, cobalt, and titanium catalysts were outlined. The catalyst samples were then analyzed through nuclear magnetic and nuclear quadrupole resonance.
Date:
February 1, 1990
Creator:
unknown
System:
The UNT Digital Library