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Monthly report of the Design Analysis Group for September 1954

Description: The following topics were discussed in this report: pressurization of the rear face for existing reactors; loss of steam in existing reactors; in-pile boiling in the 105-KER recirculation facilities; feasibility report for special study reactor plant; shielding requirements of the special study reactor plant; sulfuric acid addition to 100-K; radiation from activated iron in a recirculating system; ion exchanger activity from Fe corrosion; thermal shock-KER loop; shielding of tube bundles; adjus… more
Date: October 26, 1954
Creator: Andersen, R. K.
Partner: UNT Libraries Government Documents Department
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Hanford Atomic Products Operation monthly report for September 1954

Description: This document presents a summary of work and progress at the Hanford Engineer Works for September 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Secti… more
Date: October 25, 1954
Partner: UNT Libraries Government Documents Department
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Nickel ferricyanide scavenging flowsheet for neutralized concentrated raw

Description: From the startup of the TBP Plant until late in September, 1954, when in-line scavenging operations were begun, the wastes from the TBP Plant had been stored after neutralization and concentration in underground storage tanks. Some of this TBP waste has been given a secondary concentration in the waste concentration facilities (first cycle waste evaporators) at the tank farms. Studies by the chemistry Unit have indicated that a further reduction in the volume of waste permanently stored is poss… more
Date: October 26, 1954
Creator: Smith, R. E. & Coppinger, E. A.
Partner: UNT Libraries Government Documents Department
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Preliminary BPX flowsheet

Description: Current H.A.P.O. planning has scheduled significant increases in low-NGS irradiated fuel production for the near future. This action, coupled with the imminent activation of the K-Reactor areas, will result in a uranium production rate which exceeds the anticipated capacities of the Purex, Redox and T Plant separations facilities. Additional separations capacity is scheduled to be provided by reactivating B Plant. However, a number of other separations processing schemes -- which will provide a… more
Date: October 6, 1954
Creator: Platt, A. M.
Partner: UNT Libraries Government Documents Department
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Nitric acid recovery and ammonia removal: Modifications to the Redox dissolver off-gas systems

Description: Project CG-588 authorized the design and construction of dissolver and waste neutralizer off-gas scrubbers to remove the ammonia given off during coating removal and waste neutralization steps of the Redox operation. It has always been recognized that the nitrogen oxides in the dissolver off-gases, resulting from the dissolution of bare uranium slugs, could also be absorbed in water under proper conditions to give re-useable nitric acid. Consequently it appeared feasible to provide facilities w… more
Date: October 1, 1954
Creator: Stoker, D. J.
Partner: UNT Libraries Government Documents Department
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REACTOR ENGINEERING DIVISION QUARTERLY REPORT FOR PERIOD JULY 1, 1954 THROUGH SEPTEMBER 30, 1954

Description: Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor was intentionally destroyed by suddenly adding 4% excess reactivity. Design of the Borax-II reactor is described. It will be used for studies of transient behavior and steadystate operation as a steam producer. A preliminary design configuration has been established in EBR-II employing central, inner, and outer blankets. Fuel geometries including a smaller pin-type element are being investigated. … more
Date: October 15, 1954
Partner: UNT Libraries Government Documents Department
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The Tensile Strength of Solid-State Bonded Aluminum and Nickel-Plated Uranium

Description: To aid in the evaluation of solid-state bending techniques for cladding natural-uranium fuel-element cores with aluminum, tensile specimens, 1/4 in. in diameter and 3 in. long were made and tested. Results show that these techniques are capable of producing satisfactory bonds between aluminum and nickel-plated uranium. Pressing conditions of 1 min at 950F and 6000 psi produced consintent bond strengths equal to the yield strength of 25 aluminum. When optimum bonding conditions are used, anodic … more
Date: October 21, 1954
Creator: Saller, H. A.; Dickerson, R. F. & Carlson, R. J.
Partner: UNT Libraries Government Documents Department
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Studies of Graphite for Fuel Elements

Description: Improved graphites for use in fuel elements were developed from artificial graphites and phenolic resins. These materials are particularly well suited for fuelelement preparation. The resins do not soften during baking, so bodies hold their shape and show good dimensional uniformity. The physical properties of graphite were obtained without heating at "graphitizing" temperatures, which would be detrimental to UO/sub 2/ or other inclusions of nuclear fuel. High densities and bending strengths, v… more
Date: October 13, 1954
Creator: Loch, L. D.; Slyh, J. A. & Duckworth, W. H.
Partner: UNT Libraries Government Documents Department
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