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External-Fuel Thermionic Reactors

Description: The concept of the external-fuel thermionic converter, in which the fuel surrounds an inner emitter annulus, is introduced and the major advantages of its use in a thermionic reactor are discussed. In-core reactors, ranging from 15-ekW to megawatts, can be designed based on external-fuel converter modules of fixed emitter and collector dimensions. Sizes and weights of typical reactors in this power range are shown.
Date: May 1, 1968
Creator: Abbate, M. J.; Eisen, C. L.; Raab, B. & Schock, Alfred
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: April 1963

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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High Dilution On-Stream Isotopic Tracers Annual Report: 1961

Description: Introduction: The primary objective of the work of this report was research and development leading to large-scale applications of low level isotope tracer technology.
Date: May 1961
Creator: Aebersold, Paul C. & Bizzell, Oscar M.
Partner: UNT Libraries Government Documents Department
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Final report: PITA-18 use of nonpoisonous splines for longitudinal flux traversing

Description: Optimization of the reactor process involves the knowledge of the longitudinal flux distribution on a semicontinuous, routine basis. The nonpoisonous spline was proposed as a way for obtaining flux traverses at any time during reactor operation, in virtually any location in the core. This report summarizes the findings of a feasibility study conducted in conjunction with PITA-18 and thus serves as a termination of the test phase of spline traversing.
Date: May 1, 1963
Creator: Albertson, D. G. & Bowers, C. E.
Partner: UNT Libraries Government Documents Department
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Scale "Up or Down" Analysis for Prototype Test

Description: Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually … more
Date: May 1, 1960
Creator: Alco Products (Firm)
Partner: UNT Libraries Government Documents Department
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THORIUM BREEDER REACTOR EVALUATION. PART 1. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GGBR), and deuterium- moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site. The maximum annual fuel yields were 1.5 mills/ kwhr. The minimum estimated fuel cycle costs were … more
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas cooled graphite-moderated (GGBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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THORIUM BREEDER REACTOR EVALUATION. PART I. FUEL YIELD AND FUEL CYCLE COSTS IN FIVE THERMAL BREEDERS. APPENDICES

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium- moderated gascooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected with continuous processing of fuel and fertile streams. The maximum annual fuel yields were 16, 7, 4, 4, and 4.5%/yr, respectively at a fuel cycle cost of 1.5 mills/kwhr… more
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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Thorium Breeder Reactor Evaluation. Part I. Fuel Yield and Fuel Cycle Costs in Five Thermal Breeders. Appendices

Description: The performances of aqueous-homogeneous (AHBR), molten-salt (MSBR), liquid-bismuth (LBBR), gas-cooled graphite-moderated (GCBR), and deuterium-moderated gas-cooled (DGBR) breeder reactors were evaluated in respect to fuel yield, fuel cycle costs, and development status. A net electrical plant capability of 1000 Mwe was selected, and the fuel and fertile streams were processed continuously on-site.
Date: May 24, 1961
Creator: Alexander, L. G.; Carter, W. L.; Chapman, R. H.; Kinyon, B. W.; Miller, J. W. & Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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NPR delayed neutron fractions and decay constants

Description: This report discusses the delayed neutron characteristics of a reactor which are a function of the distribution of fissions in the various fissionable isotopes. The delayed neutron characteristics of the NPRL delayed fraction and decay constants, are presented as functions of exposure to 2000 MWD/T for both room temperature and operating temperature. It is of importance to note that the delayed neutron fraction decreases from 0.693% to 0.539% with increased exposure. Thus 22% less reactivity ch… more
Date: May 26, 1961
Creator: Allen, C. W.
Partner: UNT Libraries Government Documents Department
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Thorium Isotopes Method for Dating Marine Sediments

Description: This thesis is concerned with a possible method of improving the well-known ionium method of age determination of deep-sea sediment sections (Pet-53, Zou-58, Kul-55, Ran-54) both with respect to accuracy of individual determinations and with respect to the range of applicability of the method.
Date: May 31, 1960
Creator: Almodóvar, Ismael
Partner: UNT Libraries Government Documents Department
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A Study of Resonances of the Z-7r System

Description: Recently a T = 1 resonance in the {Lambda}-{pi} system called Y{sub 1} has been observed with a mass of 1385 MeV. Two types of resonances have been predicted that might relate this observation to other elementary-particle interactions: (1) P 3/2 resonances in the {Lambda}-{pi} and {Sigma}-{pi} systems predicted by global symmetry, corresponding to the (3,2/ 3/2) resonance of the {pi}-N system, (2) a spin-1/2 Y-{pi} resonance resulting from a bound state in the {bar K}-N system. The position and… more
Date: May 23, 1961
Creator: Alston, Margaret H.; Alvarez, Luis W.; Eberhard, Philippe H.; Good, Myron L.; Graziano, William; Ticho, Harold K. et al.
Partner: UNT Libraries Government Documents Department
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Critical Studies of a Dilute Oxide Fast Reactor Core (ZPR-III Assembly 30)

Description: BS>Critical studies of a fast reactor core containing a simulated oxide fuel having an oxygen-uranium atomic ratio of 1: 1 are described. Calculated and experimental critical masses are compared. Experimental results are given for fission ratio, central reactivity coefficient, fuel bunching, and distributed worth measurements. (auth)
Date: May 1961
Creator: Amundson, P. I.; Hess, A. L.; Keeney, W. P.; Long, J. K. & McVean, R. L.
Partner: UNT Libraries Government Documents Department
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BAND-1--a Data Reduction Program for the IBM-704

Description: BAND-1 is an IBM-704 program to reduce the experimental data obtained from measurements of the neutron activation distribution within a critical facility. The data reduction consists of correcting the measured data, sorting and ordering it, and calculating the critical buckling parameters by means of a least squares analysis. (auth)
Date: May 1961
Creator: Anderson, B. L.; Hemphill, A. P.; Jarvis, P. H. & Kettler, R. E.
Partner: UNT Libraries Government Documents Department
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CLIP-1--an IBM-704 Program to Solve the P-3 Equations in Cylindrical Geometry

Description: A second order form of the cylindrical P-3 equations is obtained for the case of an isotropic source. The boundary conditions and numerical method are discussed. Input preparation and operating instructions are included. (auth)
Date: May 1962
Creator: Anderson, B.; Davis, J.; Gelbard, E.; Jarvis, P. & Pearson, J.
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: April 1964

Description: This is the forty-forth progress report from April 1964 detailing progress made in areas such as the issuing of Topical Report No. 2 giving details on Test 1, completion of preliminary operations on Test 3, near completion of data analysis on Test 4, and plans to begin Test 5 after preliminary operations.
Date: May 15, 1964
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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METALLOGRAPHY OF URANIUM CONTAINING SMALL ADDITIONS OF IRON, SILICON, OR ALUMINUM

Description: In uranium with alloying additions of up to 400 ppm Fe and up to 800 ppm of either Si or Al, the various U-containing phases were examined with the electron microscope. These phases were also extracted chemically and identified by electron diffraction. During gamma -phase heat treatments, the alloying additions, as well as impurity atoms, segregate into networks of incipient'' precipitates that can be seen only afier certain etching treatments. (auth)
Date: May 1, 1963
Creator: Angerman, C. L. & Louthan, M. R. Jr.
Partner: UNT Libraries Government Documents Department
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The Influence of Isotopic Composition on the Maximum in the Cosmic Ray Energy Spectra

Description: "The previously found maximum in the cosmic radiation energy spectrum is discussed, and the possibility that it arises in part from a misinterpretation of the data due to oversimplifying assumptions about the composition of the beam is examined. The importance that lack of recognition of isotopic composition may have is pointed out, and it is clear that this importance is strongly dependent on the measurements made and on the cut-off rigidity."
Date: May 8, 1961
Creator: Appa Rao, M.V.K. &
Partner: UNT Libraries Government Documents Department
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