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LABORATORY DEVELOPMENT OF A CARRIER-PRECIPITATION PROCESS FOR THE RECOVERY OF STRONTIUM FROM PUREX WASTES

Description: Strontium recovery from Purex 1WW was investigated with simulated feeds and tracer activities. Initial experiments demonstrated recovery of over 70% of the strontium by sulfate precipitation from partially neutralized 1WW by either increasing the sulfate concentration to about 3 M or by adding carriers such as lead. Precipitation of iron was avoided by addition of one or more moles of tartrate per two moles of iron. Precipitation at elevated temperatures and addition of lead after pH adjustment… more
Date: May 1, 1961
Creator: Bray, L.A. & Van Tuyl, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SAFETY OF ORGANIC SOLVENTS IN WASTE TANKS

Description: This report addresses flash points and flammability limits of flammable gases found in waste tanks, primarily hydrocarbon mixtures derived from waste solvents. The effect of vapor pressure is discussed. Particular attention is given to Purex solvent. The pertinent facts are then applied to the safety of the waste tanks of concern.
Date: August 1, 1983
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of cesium from Purex plant wastes by metal ferrocyanides and ferricyanides II: Full level laboratory investigations

Description: Laboratory scale experiments with synthetic Purex 1WW and HAW have demonstrated the feasibility of recovering cesium by precipitation with metal ferrocyanides and ferricyanides. One method for recovery of cesium involves neutralization of the precipitate ferric hydroxide and sodium diuranate, and recovery of cesium from the supernate by precipitation with zinc ferrocyanide. Another method involves precipitation with nickel or ferric ferrocyanide from partially neutralized 1WW, or from HAW. The … more
Date: February 28, 1957
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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CAPABILTY FOR PROCESSING POWER REACTOR FUELS

Description: The reprocessing of commercial power reactor fuels in existing or modified facilities has been examined for four different reprocessing rates. Existing capabilities in the 325A hot cells will permit processing up to 2 kg of fuel per day using an 8-stage centrifugal contactor and discarding the uranium-plutonium stream in the organic phase. The principal problems with this system are feed clarification, equipment reliability, and waste disposal. The cost is anticipated to be about $30,000 per ru… more
Date: March 1, 1976
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method

Description: Impurities are separated from plutonium solutions by means of TTA (thenoyltrifluoracetone) extractions. Plutonium in hydrochloric acid solution is reduced to the trivalent state with hydroxylamine, and some impurities are extracted into hezone or a solution of TTA in hezone. The organic phase is removed, and the plutonium in the aqueous phase is oxidized to the tetravalent state with nitric acid. Investigations of several variables which affect the extraction are described..
Date: June 29, 1953
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Composition of Solids from Purex LWW

Description: The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww tha… more
Date: January 22, 1959
Creator: Van Tuyl, H.H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Recovery of Plutonium and Neptunium from Purex IWW by Anion Exchange

Description: The recovery of plutonium and neptunium by anion exchange has been well demonstrated on a laboratory scale. (1, 2,3,4) The specific adsorbed by the resin is the tetravalent hexanitrate complex of either element. With plutonium (IV) and neptunium(V) in IWW, the plutonium is adsorbed but the neptunium is not. If nitrite is used as the reductant in strong (preferably 8 M or over) nitric acid, both plutonium and neptunium are obtained in the tetravalent state, and both are adsorbed on the resin. Wi… more
Date: July 16, 1959
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Potential for Exothermic Chemical Reactions in Waste Tanks

Description: The potential for exothermic chemical reactions in waste tanks at Hanford is discussed. Organic chemicals have been added to Hanford waste tanks, particularly as ferrocyanides and when processing sludges at B Plant. Recent planned or ongoing activities involving stored wastes have possibly increased the potential for reaction of these wastes with nitrate salts in the waste tanks. Risk evaluations appear to be deficient in assessing the consequences of a deflagration, and in determining the prob… more
Date: February 3, 1983
Creator: Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Results of research to evaluate solid plutonium nitrate as a safe shipping form

Description: The results of the research described indicate that the compound Pu(NO/sub 3/)/sub 4/.XH/sub 2/O is a viable material for consideration as a solid shipping form. It meets the criteria set forth to define a suitable solid form of plutonium. Several plutonium compounds were considered for study as a shipping form before selecting Pu(NO/sub 3/)/sub 4/.XH/sub 2/O as having the most desirable characteristics. It is reasonably easy to prepare on a kilogram scale with relatively simple equipment using… more
Date: November 1, 1976
Creator: Bryan, G. H.; Thompson, J. K.; Van Tuyl, H. H.; Brown, C. L. & Ryan, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fission product production plant engineering study basis: Chemical flowsheet

Description: At the request of the US Atomic Energy Commission, the General Electric Company has undertaken an engineering-study preliminary to the design and construction of a fission product heat source production plant at Hanford. This document presents proposed feed materials, product specifications, and the chemical flowsheet basis for the engineering study. A preliminary waste extraction chemical flow-sheet is included to illustrate the integration of the proposed production plant with the Hanford Was… more
Date: March 13, 1963
Creator: Moore, R. L.; Richardson, G. L.; Swift, W. H. & Van Tuyl, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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