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Review of Redox Plant Head-End treatment

Description: Oxidation of the dissolver solution is required before processing through the Redox Plant. Two different Head-End treatment procedure have been used in the plant since start-up, the original one employing sodium dischrocate as the oxidant and the current one (initiated in May of 1953) employing potassium permanganate. In addition to oxidizing the plutonium, the permanganate Head-End procedure removes substantial quantities of radio-ruthenium (the fission product most difficult to remove by solvent extraction) from the IAF and, thus, benefits the overall decontamination of the uranium and plutonium products markedly. The purposes of this paper are: to describe briefly the dichromate and permanganate Head-End procedures and conditions of oxidation; to present and discuss the advantages of the permanganate procedure as compared with the dichromate procedure; and to present and discuss the disadvantages of the permanganate procedure and the difficulties associated with equipment maintenance when this process is utilized.
Date: June 17, 1954
Creator: Kiel, G. R.
Partner: UNT Libraries Government Documents Department

Total-Head Meter With Small Sensitivity to Yaw

Description: The total-head meter is essentially a venturi, housing a pitot tube for obtaining the total head. In yaw the flow within the nozzle is deflected, depending upon the degree of yaw, to a greater or lesser extent into the axial direction of the nozzle. After experimenting with several nozzle forms as to their suitability, the best design was finally adopted. When, with the chosen nozzle form, the total head is 0.5 entrance section diameter downstream, the instrument supplies the genuine total head at low Reynolds Numbers up to 43 degrees yaw.
Date: August 1935
Creator: Kiel, G.
Partner: UNT Libraries Government Documents Department

Input and decayed values of radioactive solid wastes buried in the 200 areas through 1971

Description: Solid radioactive wastes resulting from chemical separations processing of spent reactor fuels have been disposed by burial in trenches in the 200 Areas since 1944. Solid radioactive wastes from other Hanford facilities and from off-site AEC contractors have also been buried in the 200 Areas` Waste Burial Grounds. Since 1970, industrial wastes containing or suspected of containing transuranic radionuclides have been packaged in concrete boxes and {open_quotes}dry wastes{close_quotes} have been packaged in steel boxes or drums and buried in segregated trenches. A land area of approximately 149 acres has been used to bury 5.2 million cubic feet of contaminated solid waste through calendar year 1971. Annual reports of radioactive solid waste burials issued, beginning in 1968, have shown land area used, and volume and quantity of radioactivity grams U and/or Pu and curies buried. No corrections for radioactive decay have been reported. In July 1972, J. D. Anderson, G. L. Hanson, G. R. Kiel, B. J. McMurray, and N. P. Nisick were assigned the responsibility for a study to provide the decayed inventory of radioactivity in each solid waste burial ground in the 200 Areas. The results of this study are included as Tables 1 and 2 in this report.
Date: March 22, 1973
Creator: Hanson, G. L.; Anderson, J. D.; Kiel, G. R.; McMurray, B. J. & Nisick, N. P.
Partner: UNT Libraries Government Documents Department

Extraction of uranium from seawater: chemical process and plant design feasibility study

Description: A major assessment was made of the uranium resources in seawater. Several concepts for moving seawater to recover the uranium were investigated, including pumping the seawater and using natural ocean currents or tides directly. The optimal site chosen was on the southeastern Puerto Rico coast, with the south U.S. Atlantic coast as an alternate. The various processes for extracting uranium from seawater were reviewed, with the adsorption process being the most promising at the present time. Of the possible adsorbents, hydrous titanium oxide was found to have the best properties. A uranium extraction plant was conceptually designed. Of the possible methods for contacting the seawater with the adsorbent, a continuous fluidized bed concept was chosen as most practical for a pumped system. A plant recovering 500 tonnes of U/sub 3/O/sub 8/ per year requires 5900 cubic meters per second of seawater to be pumped through the adsorbent beds for a 70% overall recovery efficiency. Total cost of the plant was estimated to be about $6.2 billion. A computer model for the process was used for parametric sensitivity studies and economic projections. Several design case variations were developed. Other topics addressed were the impact of co-product recovery, environmental considerations, etc.
Date: February 1, 1979
Creator: Campbell, M.H.; Frame, J.M.; Dudey, N.D.; Kiel, G.R.; Mesec, V.; Woodfield, F.W. et al.
Partner: UNT Libraries Government Documents Department