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LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS

Description: BS>The use of a lead-bismuth alloy as a coolant in the removal of heat from power-generating nuclear reactors was considered with the possibility that its ternary alloy with uranium or plutonium might be of use in a reactor of the circulating-liquid-fuel type. Information collected from the literature covering phase-equilibrium studies, physicalproperty data, and reactivity of this alloy toward other substances is presented. (auth)
Date: February 14, 1950
Creator: Lee, M.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report, March 1962

Description: ABS>Developmental work is reported on the EBWR and Borax-V other general development work is reported in the area of liquid metal cooled reactors and particularly on the EBR-I and H, and the fast reactor test facility. General reactor technological development is described on applied reactor physics, reactor fuels development, reactor materials development, heat engineering and fluid flow, chemical separations, advanced systems, and nuclear safety. (J.R.D.)
Date: April 15, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Doppler and Related Measurements in a Soft Fast-Reactor Spectrum.

Description: This report deals with a group of both theoretical and experimental investigations which have been carried out, utilizing Core 15, one in a series of critical assemblies that have been constructed at Atomics International's Epithermal Critical Experiments Laboratory (ECEL).
Date: October 31, 1969
Creator: Springer, T. H.; Tuttle, R. J.; Otter, J. M. & Paschall, R. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SRE CONTROL ROD SHIELDING REQUIREMENTS

Description: Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended pow… more
Date: October 22, 1957
Creator: Whittum, H.O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control Characteristics of Rankine Cycle Systems Which Simulate the Mpre Fluid System.

Description: In conjunction with the Medium power Reactor Experiment Program at ORNL, studies were conducted on two single-loop Rankine cycle systems. These systems were controlled using the same design concept which has been proposed for control of the MPRE fluid system. Experiments were run with water and potassium test facilities which were reduced scale electrically heated mockups of the proposed reactor and power recovery system. Results from these studies demonstrate that with proper design, the distr… more
Date: October 31, 1969
Creator: Yarosh, M.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RADIOLOGICAL HAZARDS FROM RUPTURE OF THE SECONDARY COOLANT SYSTEM OF THE 10 Mw ESCR

Description: The hazards study was made to determine the radiation level from the secondary sodium lines of the l0-Mw ESCR, and to evaluate the corresponding radioactive concentration in the secondary loop and the maximum permissible effective activation flux in the intermediate heat exchanger. The results are presented graphicallyn the radiation level from the coolant lines during normal operation as a function of line diameter and Na/sup 4/ concentration; the effective thermal neutron activation flux leve… more
Date: January 19, 1960
Creator: Piccot, A.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments. Experimental Program, Experimental Procedures and Safety Considerations

Description: Revisions in the reactor system and operating procedures necessary for carrying out a proposed dry critical experiment in the EBR-II are described. The safety aspect of the program is considered. The critical experiment will be conducted in the EBR-II prior to filling the primary system with sodium. The facility, experimental program, operational and experimental procedures, and hazards and plant safety are described. (M.C.G.)
Date: February 1, 1961
Creator: Kock, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Status Report on LAMPRE Program for Period Ending February 20, 1962

Description: BS>LAMPRE I. The reactor operation is discussed. A malfunction in the shim operation was found and corrective measures taken. The core reloadings and other reactor modifications are described. The results of a gamma scanning of a fuel capsule are given. Fuel and Container Development. The properties and behavior of the Core I and the materials developed for Core II are described. Corrosion tests were carried out on pure Ta containers with molten Pu-Ce-Co alloys at 750 to 900 deg C, and the resu… more
Date: March 1, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Evaluation of Reactor Concepts for Use as Separate Steam Superheaters

Description: Various reactor concepts were compared for use as a separate superheater which could be added on to an advanced 300-Mwe reactor producing saturated steam. Fossil steam plant superheat temperatures were used as a criterion for selecting nuclear superheat temperatures. Therefore, the performance specified for the superheater was a minimum exit steam temperature of 566 deg C (1050 deg F) when supplied with saturated steam at either 7l atm (l050 psia) or l67 atm (2450 psia). A preliminary screening… more
Date: October 1, 1961
Creator: Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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