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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
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.
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
SOME EXPERIENCES IN THE WELD FABRICATION OF REFRACTORY METALS
Discussion is given on the welding fabrication of tungsten, molybdenum, niobium, and tantalum. Properties which make the four refractory metals important are tabulatcd along with titanium which is given for comparison. Extensive evaluation was conducted using the gas, tungsten arc welding process employing both manual and machine welding. Design data were obtained exclusively from machine welded sheet materials. Flash welding, resistance spot welding and brazing, electron beam welding, and high frequency resistance welding processes were also applied to molybdenum alloys. The oxidation of molybdenum, tantalum, and niobium in flowing air at 2000 deg F is also given. (P.C.H.)
Date:
February 10, 1961
Creator:
Thompson, E.G.
Object Type:
Report
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.
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
EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER
EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, group-dependent buckling, or region-dependent buckling may be specified for rectangular geometry. This program is intended to fill the need for a rapid two-dimensional calculation suitable for survey calculations. During the iterative part of the computations, all operations are carried out in the core memory. The magnetic tape memory is used only for input, output, and program storage. The running time for a 1000-point problem requiring 100 iterations would be about 3 min.(auth)
Date:
February 21, 1962
Creator:
Fowler, T.B. & Tobias, M.L.
Object Type:
Report
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
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.
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
Integrated dry NO sub x /SO sub 2 emissions control system
The DOE Cooperative Agreement No. DE-FC22-91PC90550 dated March 11, 1991, Public Service Company of Colorado has prepared the following quarterly report for Phases I, IIA, and IIB of the Integrated Dry NO{sub x}SO{sub 2} Emissions Control System Project. This project includes low NO{sub x} burners with NO{sub x} ports (post firing air injection), humidification and dry sorbent injection.
Date:
February 15, 1992
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Office of Waste Isolation progress report, January 1978
This document, prepared to report progress on the National Waste Terminal Storage (NWTS) program, consists of project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. The project reports are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date:
February 28, 1978
Creator:
Zerby, C.D.
Object Type:
Report
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
Object Type:
Report
System:
The UNT Digital Library
Blanket technology experiments at Argonne National Laboratory
Argonne National Laboratory has the largest US program for the development of blanket technology. The goals of the program are to resolve critical issues for different blanket concepts, to develop the understanding and predictive capability of blanket behavior, and to develop the technology needed to build and operate advanced fusion blankets. The projects within the program are liquid metal MHD, breeder neutronics, tritium oxidation, transient electromagnetics, FLIBE chemistry, and insulator coatings. The present status and recent results of the projects are described.
Date:
February 1, 1988
Creator:
Mattas, R. F.; Reed, C. B.; Picologlou, B.; Finn, P.; Clemmer, R.; Porges, K. et al.
Object Type:
Article
System:
The UNT Digital Library
Health physics aspects of nuclear radiations from deuterium beam injectors
Estimations are made for X-ray generation from the accelerator column of various neutral beam injectors. For the case of deuterium beam operation where 2.5-MeV D-D neutrons pose a serious health physics concern, neutron and tritium production rates from beam targets are calculated for different beam energies. Biological doses from these radiations and shielding requirements are discussed.
Date:
February 1, 1978
Creator:
Kim, J.
Object Type:
Report
System:
The UNT Digital Library
Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the fuel was ejected from the rod as particulates. The feasibility and conceptual design study for an experimental facility to verify fission product transport computational models has been completed. Although the study focused entirely on a facility which would be employed to verify those aspects of the transport models that dealt with fission product source-term attenuation factors in the primary coolant circuit external to the pressure vessel, the need for a second facility, to simulate conditions within the pressure vessel, was also indicated.
Date:
February 1, 1978
Creator:
Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Object Type:
Report
System:
The UNT Digital Library
Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977
The exposures of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a ..beta.. dose of 10 ..mu..Ci/cm/sup 3/, a ..gamma.. dose of 10/sup -5/ ..mu..Ci/cm/sup 3/, and an ..cap alpha.. dose of 4.9 x 10/sup -3/ ..mu..Ci/cm/sup 3/ were completed. Exposure to ..beta.. and ..gamma.. radiation did not affect membrane performance. After a simulated six months of exposure to ..cap alpha.. radiation some degradation of membrane performance occurred. Several experiments were made on a laboratory-scale reverse-osmosis unit using the product from ultrafiltration as feed. Rejection of activity ranged from 88 to 99 percent. The ''continuous'' ultrafiltration pilot run was completed. Approximately 40,000 gal were processed in over 70 hr of operating time without shutdown for cleaning. Flux and rejection were maintained relatively steady over this period. Rejection of gross alpha ranged from 80 to 99.5 percent depending on the ionic content of the waste stream. Flux rates ranged from 5 to 8 liters/min over this period. The engineering column tests were continued using uranium-233 with product from the ultrafiltration pilot plant. Flow rates and pH were varied in order to determine optimum operating conditions.
Date:
February 24, 1978
Creator:
Koenst, J. W.; Herald, W. R. & Roberts, R. C.
Object Type:
Report
System:
The UNT Digital Library
Equipment develoment report: downhole fluid injector
The development, design, fabrication, and operation of a tool used for injecting a discrete quantity of fluid (e.g. a dye) at a desired location within a hot geothermal borehole are described. Assembly and operating instructions are included.
Date:
February 1, 1978
Creator:
Archuleta, J. R.; Fink, C. F. & Kurtenbach, J.
Object Type:
Report
System:
The UNT Digital Library
Silicon mass transfer in sodium loops and the resulting/thermal hydraulic effects. [LMFBR]
The element silicon in the surface of new, 300 series stainless steel has been shown to rapidly dissolve in sodium above 525/sup 0/C. It deposits in slightly cooler regions as a crystalline compound with sodium and oxygen. In tests, the deposits have caused increases in hydraulic friction factor (hence, increased pressure loss) of up to 300% at Reynolds Numbers of 14/sup 4/ to 10/sup 5/.Also, they have contributed to local losses of heat transfer rate to 1/10 the original value, at a Reynolds Number of approximately 10/sup 4/. The crystals quickly decompose when out of sodium. Measurements made with a sodium loop (volume = 0.42 m/sup 3/) include compound solubility vs temperature, loop conditions vs source rates and deposit transfer rates. Laboratory examinations and analyses of the crystals have also been made. The effects of this material have been observed also in a number of other loops. With the data from these studies, such effects are now explained and can be controlled or eliminated by system design and operation.
Date:
February 1, 1980
Creator:
Yunker, W.H.
Object Type:
Article
System:
The UNT Digital Library