The Isolation and Purification of Americium (open access)

The Isolation and Purification of Americium

Gram amounts of americium were separated quantitatively from kilogram quantities of lanthanum to yield an americium product approaching 90% purity. The remaining impurity was chiefly yttrium. Elution of americium from 25% loaded Dowex 50 resin column with 0.15 M citric acid— 0.10 M diammonium citrate — 0.3 M ammonium nitrate, pH 3.3 gave a product containing 99% of the americium with a La/Am ratio of 1/100 or less in one fourth of a column volume, in this case about 1 100-fold volume reduction. Approximately 9 g of americium was purified by this method. Elution with 12.8 M hydrochloric acid from a 20 to 30% loaded column gave 90% of the americium in two column volumes of product with a La/Am ratio of about 1/4. About 1 g of americium was purified by this method.
Date: April 17, 1956
Creator: Campbell, D. O.
System: The UNT Digital Library
Development of the Excer Process (open access)

Development of the Excer Process

Two revised Excer process flowsheets are presented for the production of UF4 from urnayl nitrate solution. In both, the uranium is sorbed on a cation-exchange resin and eluted with aqueous HF. In one, the resulting UO2F2 in dilute HF is mixed with dilute sulfuric or hydrochloric acid and electrolytically reduced in a cation-exchange-membrane cell, and the precipitated UF4·0.75H2O is dried and dehydrated to anhydrous UF4. A cost of 20¢ per pound of reduced uranium is estimated. In the other, ammonium fluoride is also added to the uranyl fluoride solution before the electrolytic reduction step, and the precipitate is UF4·04NH4F. A flowsheet for preparing UF4 from raw ore is also shown. The uranium is sorbed on an anion-exchange resin from a sulfuric acid leach liquor and eluted with dilute HCl. Ammonium fluoride and HF are added to the UO2Cl2-HCl solution before the uranyl ion is electrolytically reduced to precipitate UF4·0.4NH4F. Decontamination factors as high as 45 and 9 for gross beta and gamma activities and of 10 to 5000 for light metal impurities were obtained in the electrolytic reduction step.
Date: April 17, 1956
Creator: Marinsky, J. A.
System: The UNT Digital Library
Air Scattering of Co60 Gamma Rays: Theory Versus Experiment (open access)

Air Scattering of Co60 Gamma Rays: Theory Versus Experiment

For Co60 source at 15 meters, the air-scattered gamma dose rate predicted by theory is excerpted from ORNL-1575, pp. 167-203. This is compared with experimental measurements for the same source and comparable geometry reported by Convair in CVAC-170T. After applying an appropriate correction for ground scattering as estimated in Mart-55-16T (Convair), the two results are found to be in substantial agreement.
Date: April 17, 1958
Creator: Moran, Rubert S.
System: The UNT Digital Library
Estimation of the Thermal Conductivity and the Viscosity of Gases at High Pressure (open access)

Estimation of the Thermal Conductivity and the Viscosity of Gases at High Pressure

Few data exist for the thermal conductivity and viscosity of gases at very high pressure. The possibility of using gases for heat transfer media at pressures up to 100 atmospheres and above raised the problem of estimating variations in the conductivity and viscosity at high pressure. Generalized plots are presented which are based on the work of Enskog, Eucken, and Hirschfelder et al. Some pertinent data from Hirschfelder et al and from Hilsenrath et al are presented.
Date: January 17, 1957
Creator: Lyon, Richard Norton
System: The UNT Digital Library
The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes (open access)

The Alkaline Method for Treatment of High Radiation Level Aluminum Wastes

The method is based on caustic precipitation and centrifugation (which removes the Cs and small amounts of Sr, rare earths, Zr, Nb, and Ru). These are removed in the supernatant and run through a cation exchange column. This separates Zr-NB and Ru. The effluent is precipitated and the Zr-Nb is stored in an asphalt pit. The Ru then may be recovered from the precipitate. The precipitate from the original centrifugation is calcined, pressed and transported to a deep well.
Date: January 17, 1957
Creator: Higgins, I. R.
System: The UNT Digital Library
HRT Temperature Measurement System - Issue No. 3 (open access)

HRT Temperature Measurement System - Issue No. 3

The following temperature measurement tabulation consists of two parts. Part I lists all HRT thermocouples, their location, the junction box thru which the leads pass, and their termination, if on an instrument. Part II lists all temperature read out instruments and their location. A total of 577 thermocouples are listed in this tabulation. The roughly 77,000 ft of wire used in connecting them up cost $6,799. Temperatures are read on 24 instruments. Cost of these was approximately $15,688. Accessories such as patch panels, conduit, disconnects, etc., used in installing the thermocouples cost about $8,069. Total cost for material and instruments for temperature measure comes to approximately $30,556.
Date: January 17, 1957
Creator: Grimes, J. D.
System: The UNT Digital Library
Power Distribution of Tower Shielding Facility Reactor (TSR) (open access)

Power Distribution of Tower Shielding Facility Reactor (TSR)

The horizontal and vertical power distribution for a 5 x 7 fuel element loading of the TSR is presented. (auth)
Date: January 17, 1957
Creator: Blessing, W. G.
System: The UNT Digital Library
Observed Pressure Drop Across HRT Off-Gas Adsorber Units (Charcoal Beds) at Various Flows of Oxygen (open access)

Observed Pressure Drop Across HRT Off-Gas Adsorber Units (Charcoal Beds) at Various Flows of Oxygen

A plot of the pressure-drop data shows that the pressure drop through a single HRT off-gas adsorption unit is equal to 2.66 times the O2 flow (measured in liters/min at 70 F, 14.7 psia).
Date: April 17, 1957
Creator: Van Winkle, R.
System: The UNT Digital Library
Status and Future Program of Homogeneous Reactor Fuel Processing Studies (open access)

Status and Future Program of Homogeneous Reactor Fuel Processing Studies

The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
System: The UNT Digital Library
Instantaneous Velocity Profile Measurement by Photography (open access)

Instantaneous Velocity Profile Measurement by Photography

The following is taken from ORNL-2257, Instantaneous Velocity Profile Measurement by Photography, by R. E. Lynch, L. D. Palmer, and G. M. Winn. This report is in in preparation status; and errors, inconsistances, and omissions in he language, as well as in the technical aspects, may exist. The technique of using phosphorescent particles to enable photographic determination of qualitative and quantitative instantaneous velocity profiles is covered by AEC Patent Application No. SN-710, 371 issued to F. E. Lynch, L. D. Palmer, H. F. Poppendiek, and G. M. Winn and entitled " A Method of and Means for Visualizing Fluid Flow Patterns.
Date: August 17, 1959
Creator: Lynch, F. E.; Palmer, L. D.; Winn, G. M. & Hoffman, H. W.
System: The UNT Digital Library