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in creator/contributor: "Alexander, L G"  
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HEAT RELEASE IN NUCLEAR REACTORS

Description: Discussions are included on energy sources and modes of local deposition of heat, fission fragment and BETA decay energy, neutron energy, energy release by BETA decay of activated nuclei, neutron flux distribution, gamma heating calculations, and integration of the gamma heating equation for simple cases. (M.H.R.)
Date: October 1, 1956
Creator: Alexander, L.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NEUTRON LOSSES TO Pa$sup 233$ IN THE AQUEOUS HOMOGENEOUS BREEDER REACTOR

Description: Neutron losses to Pa/sup 2//sup 3//sup 3/ in the blanket of the AHBR were computed and compared for two cases: (1) concentration of Pa/sup 2//sup 3// sup 3/ is maintained uniform by continuous mixing, and (2) batches of fertile material are shifted periodically from high- to low-flux regions of blanket. It was found that, if the fertile material is cycled through three radial positions in three days, the loss of neutrons to Pa/sup 2//sup 3//sup 3/ is no more than one per cent greater than if it… more
Date: April 26, 1961
Creator: Miller, J.W. & Alexander, L.G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

Description: The design of internally cooled electrical coils for the production of high intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of this equati… more
Date: May 25, 1959
Creator: Alexander, L G
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Performance Characteristics of Advanced Evaporator Tubes for Long-Tube Vertical Evaporators

Description: From Introduction: "The investigation detailed in this report were undertaken to compare effectiveness of tubes enhanced in various ways and, then, to provide performance data on selected tubes of most promising type."
Date: January 1971
Creator: Hammond, R. P.; Alexander, L. G.; Hoffman, H. W. & Hoffman, H. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Brief Review of Heat Transfer Problems Encountered in the Production of Magnetic Fields

Description: The design of internally cooled electrical coils for the production of high frequency intensity magnetic fields presents many new aspects and combinations of the familiar modes of heat transfer. However, the customary methodology appears to be sufficient for preliminary analysis and understanding of those problems. This methodology comprises the derivation of a qualitative, approximate equation expressing the relative performance of the various parts of a system, followed by an examination of … more
Date: May 25, 1959
Creator: Alexander, L. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A PRELIMINARY STUDY OF MOLTEN SALT POWER REACTORS

Description: A preliminary study of molten salt pcwer reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium. The chlorides were found to have lower melting points but were less stable and more corrosive than the fluorides. A Li/sup 7/ F- - BeF/sub 2/ mixture with ThF/sub 4/ and UF/sub 4/appeared to perform best. Of the numerous alloys tested as container material, Inconel and a nickel-- molybdenum alloy INOR-8 appeared to be … more
Date: April 29, 1957
Creator: MacPherson, H. G.; Alexander, L. G.; Carrison, D. A.; Estabrook, J. Y.; Kinyon, B. W.; Mann, L. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Preliminary Study of Molten Salt Power Reactors

Description: A preliminary study of molten salt power reactors was made. The most promising fuel carrier salts were the fluorides and chlorides of the alkali metals, zirconium, and beryllium. The chlorides were found to have lower melting points but were less stable and more corrosive than the fluorides. A Li/sup 7/ F- - BeF/sub 2/ mixture with ThF/sub 4/ and UF/sub 4/appeared to perform best. Of the numerous alloys tested as container material, Inconel and a nickel-- molybdenum alloy INOR-8 appeared to be … more
Date: April 29, 1957
Creator: MacPherson, H. G.; Alexander, L. G.; Carrison, D. A.; Estabrook, J. Y.; Kinyon, B. W.; Mann, L. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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