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Fuel Cycle Costs in a Graphite Moderated Slightly Enriched Fused Salt Reactor

Description: A fuel cycle economic study has been made for a 315 Mwe graphite- moderated slightly enriched fused-salt reactor. Fuel cycle costs in the order of 3.3 mills/kwh were calculated for the throw-away cycle. Recovery of the uranium and plutonium at the end of the cycle reduces the fuel cycle costs to approximately 1.6 mill/kwh. Changes in the waste storage cost and reprocessing cost have a relatively minor effect on fuel cycle costs.
Date: February 24, 1959
Creator: Guthrie, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Costs in a Graphite Moderated Slightly Enriched Fused Salt Reactor

Description: A fuel cycle economic study has been made for a 315Mwe graphite- moderated slightly enriched fused-salt reactor. Fuel cycle costs of less than 1.5 mills may be possible for such reactors operating on a ten-year cycle even when the fuel is discarded at the end of the cycle. Recovery of the uranium and plutonium at the end of the cycle reduces the fuel cycle costs to approximates 1 mill/kwh. Changes in the waste storage cost, reprocessing cost or salt inventory have a relatively minor effect on f… more
Date: January 9, 1959
Creator: Guthrie, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Processing of Molten Salt Power Reactor Fuel

Description: Fuel reprocessing methods are being investigated for molten salt nuclear reactors which use LiF-BeF2 salt as a solvent for UF4 and ThF4. A liquid HF dissolution procedure coupled with fluorination has been developed for recovery of the uranium and LiF0BeF2 solvent salt which is highly enriched in Li-7. The recovered salt is decontaminated in the process from the major reactions poisons; namely, rare earths and neptunium. A brief investigation of alternate methods, including oxide precipitation,… more
Date: April 1, 1959
Creator: Campbell, David Owen, 1927- & Cathers, G. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date: 1962
Creator: Oak Ridge National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurements of the Viscosity of FLiNaK : (11.5 Mol % NAF, 42 Mo. % KF, and 46.5 Mol % LiF)

Description: Abstract: "To supplement measurements made with the falling-ball viscometer it was decided to obtain data taken by more rapid, though probably less exact devices. Three essentially different methods were employed to obtain this data. Measurements were made on Flinak which deviated from the average by about +/- 1 centipoise. The data obtained by the Physical Properties Laboratory is in substantial agreement with the measurements made by Francois Kertess and Frank Knox of the Chemistry Section. … more
Date: 1952
Creator: Tobias, M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Preparation of Anhydrous White Salt in Green Salt Type Box Reactors

Description: Report discussing a method for producing anhydrous TO2F2 in a box-type reactor, which takes approximately seven hours. "The method consists of a heating period of the charge oxide under oxygen, treatment, with anhydrous hydrofluoric acid gas combined with oxygen, and flushing or removal of the excess hydrofluoric acid and formed water with nitrogen gas."
Date: January 29, 1946
Creator: Johnsson, Karl Otto & Clewett, G. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress is presented. This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Briggs, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1965

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.
Date: June 1965
Creator: Briggs, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Xenon Poisoning in Molten Salt Reactors

Description: The xenon poison fraction in a 1000-mwe molten salt breeder reactor power plant (MSBR) was calculated as a function of sparging cycle-time and the rate of diffusion of xenon into graphitic structure in contact with the fuel salt. It was found that the xenon poison fraction can be held to 0.005 neutrons per neutron absorbed in fuel atoms by passing the fuel stream through a helium sparge-chamber at the rate of 10 ft/sup 3//sec if the coefficient of diffusion is no greater than 10(-7) cm2/sec. or… more
Date: May 3, 1961
Creator: Miller, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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