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Reactivity Changes Due to Buildup of LI° in the MTR Reflector

Description: The effect on the operational characteristics of the MTR of the Li6 poison produced by the fast neutron reaction has been investigated using the adjoint perturbation and group methods.
Date: unknown
Creator: McMurry, H. L. & Webster. J. W.
Partner: UNT Libraries Government Documents Department
open access

Materials Testing Reactor Irradiation of Thorium

Description: Various methods of irradiating thorium in the MTR for production of U233 have been considered. The effects on reactor operation and experiment facilities have also been investigated
Date: unknown
Creator: Leyse, C. F.
Partner: UNT Libraries Government Documents Department
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Report on the MTR Fuel Assembly Data Correlation

Description: The limits of uncertainty inherert in computations of SF material contert of MTR fuel assemblies were calculated. The major source of uncertainty is systematic error in the chemical analysis for U
Date: unknown
Creator: Vance, F. P. & Hudson, M. N.
Partner: UNT Libraries Government Documents Department
open access

Materials Control Techniques in Reprocessing Enriched Uranium

Description: In operating nuclear reactors it is impossible to burn up all fissionable material contained in fuel elements due to buildup of fission product poisons, the depletion of fissionable material and radiation damage to the elements. Accountability in a liquid, liquid solvent extraction type process is described.
Date: unknown
Creator: Huff, G. A. & Tingey, Fred H.
Partner: UNT Libraries Government Documents Department
open access

Solvent Extraction of Enriched Uranium

Description: A compilation of information on solvent extraction including the Hexone-25 process, TBP-25 process is presented. Information is also included on solvent extraction of combined fuels containing Zr and stainless steel compositions
Date: unknown
Creator: Griffin, D. E.
Partner: UNT Libraries Government Documents Department
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Waste Management at the Idaho Chemical Processing Plant

Description: The Idaho Chemical Processing Plant recovers the unused uranium from spent, highly enriched reactor fuel elements. Waste management is designed to maintain the release of radioactive and chemical wastes to plant environs within the limits established by AEC Health and Safety.
Date: unknown
Creator: Ayers, A. L. & Burn, P.
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Alloys in Aqueous Hydrofluoric-Nitric Acid Solutions

Description: Materials for construct of dissolvers, columns, evaporators, and piping were evaluated in boiling mixtures of hydrofluoric-nitric acids for three 48-hour periods.
Date: unknown
Creator: Bordeau, J. J. & Adams, G. S.
Partner: UNT Libraries Government Documents Department
open access

Corrosion of Titanium in the System: HNO3-HC1-H2O

Description: Corrosion resistance of titanium was determined in solution compositions arranged as to give statistical coverage to the HNO3-HC1-H2O ternary diagram up to the point where no water was added to reagent strength acids.
Date: unknown
Creator: Klemens, O. R.
Partner: UNT Libraries Government Documents Department
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Treatment : Processing and Future Disposal of Radioactive Wastes at the Idaho Chemical Processing Plant

Description: Acidic wastes from the recovery of enriched uranium from aluminum, zirconium, and stainless steel fuels at the Idaho Chemical Processing Plant are stored underground tanks of two configurations and nominal sizes of 30,000 and 300,000 gallons. The design and operation of the waste tank farm as well as the methods of environmental disposal of low level wastes is described.
Date: unknown
Creator: Stevens, James Irwin, 1920-
Partner: UNT Libraries Government Documents Department
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ICPP Input Measurement Program

Description: The measurement of residual fissionable material in spent reactor fuel elements requires specialized equipment, methods and control procedures. As a result of processing a variety of fuels at ICPP an integrated measurement generation, control and interpretation system has evolved which provides highly precise measurements from which plant material balances are constructed.
Date: unknown
Creator: Tingey, Fred H. & Rein, J. E.
Partner: UNT Libraries Government Documents Department
open access

Technical Progress Report for October Through December 1957: Idaho Chemical Processing Plant

Description: Aluminum-uranium alloy was processed successfully through the ICPP continuous dissolving-TBP extraction system. Process and equipment changes resulted in reduced waste volume. Recovery of uranium from a second zirconium alloy core was initiated. Separation of barium-140 was continued
Date: unknown
Creator: Stevenson, C. E.; Paige, D. M.; Slansky, C. M. & Warzel, F. M.
Partner: UNT Libraries Government Documents Department
open access

Performance of the TBP Process for Aluminum Fuels: Idaho Chemical Processing Plant, 1955-1956

Description: Observations of the performance of the Idaho Chemical Processing Plant as modified for continuous dissolution and TBP 1st cycle extraction, as to process chemistry and process engineering are reported for the initial plant scale, full irradiation level operating run
Date: unknown
Creator: Rohde, Kenneth L.
Partner: UNT Libraries Government Documents Department
open access

Technical Progress Report for July Through September 1957 : Idaho Chemical Processing Plant

Description: Plant modifications made during the reporting period to permit continuous dissolution of fuel shapes other than slugs, to improve solution transfer by air lifts in place of pumps, and to minimize waste volumes by raffinate recycle and elimination of jet dilutions were completed and successfully tested
Date: unknown
Creator: Stevenson, C. E.; Paige, D. M.; Slansky, C. M. & Warzel, F. M.
Partner: UNT Libraries Government Documents Department
open access

Technical Progress Report for April Through June, 1957 Idaho Chemical Processing Plant

Description: No fuel was processed for uranium recovery during the period and plant decontamination was carried out in preparation for minor equipment modifications. A comparative study of decontaminating reagent effectiveness was carried out. Recovery of barium-140 from freshly irradiated MTR elements was accomplished.
Date: unknown
Creator: Stevenson, C. E.
Partner: UNT Libraries Government Documents Department
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