Sweeping of Fission Gases from Solutions of U and Plutonium (open access)

Sweeping of Fission Gases from Solutions of U and Plutonium

Technical report describing two experiments performed to compare the amounts of fission gases swept out of UNH solution with those amounts swept out of PU solution under idential condiditons. The charge wire technique was used. The essential date and the results are given in tables in the report.
Date: September 4, 1945
Creator: Adams, R. M. & Finkelstein, H.
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, the Effect of Radiation on Water and Aqueous Solutions of Inorganic Substances (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, the Effect of Radiation on Water and Aqueous Solutions of Inorganic Substances

Technical report summarizing our knowledge of the chemical effects of ionizing radiation upon water and upon aqueous solutions of inorganic compounds. The types of radiation considered are beta rays, gamma and X rays, and heavy particles, notably neutrons, deuterons, alpha rays and fission recoils.
Date: February 22, 1944
Creator: Allen, A. O.
System: The UNT Digital Library
The Effect of Radiation on the Corrosion of Metals by Water (open access)

The Effect of Radiation on the Corrosion of Metals by Water

Technical report. Long-time tests have been made on the effect of various types of radiation on the corrosion of 2S aluminum in simulated W water. In no case was any acceleration of corrosion by the radiation observed; the effect of radiation, if any, appeared to be a protective one. Deuteron irradiation did accelerate the corrosion of mild steel at low flow rates in hot water of pH 6 to 7, but no appreciable effect was observed with copper, stainless steel, or tuballoy. The general theory of the effect of radiation on corrosion is discussed, with the conclusion that no acceleration of corrosion by radiation is to be expected in most cases of practical interest.
Date: July 6, 1944
Creator: Allen, A. O. (Augustine O.); Bowman, M. C.; Goldowski, Nathalie; Larson, R. G. & Treiman, L.
System: The UNT Digital Library
Radiocarbon from Pile Graphite; Chemical Methods for its Concentration (open access)

Radiocarbon from Pile Graphite; Chemical Methods for its Concentration

Abstract. Samples of pile graphite, irradiated in a test-hole at Hanford for 15 months, have been assayed for radioactive C14, yielding 0.38 ± 0.04 microcuries per gram. At this level of activity, the pile graphite contains very valuable amounts of C14. The relation between the above assay and the probable average assay of pile graphite is discussed, and it is concluded that the latter is almost certainly above 0.3 uc/ gram. Controlled oxidation of this graphite, either with oxygen at ~ 750°C, or with chromic acid "cleaning solution" at room temperature, yields early fractions which are highly enriched in C14. Concentrations of 5-fold with oxygen, and 50-fold with CRO{sub3}, have been observed. The relation between the observed enrichment and the Wigner effect is discussed, and a mechanism accounting for the observations put forward. According to this, about 25% of the stable carbon atoms in the lattice have been displaced by Wigner effect, a large fraction of which have healed the migrating to crystal edges. All the C14 atoms have been displaced, and the same fraction of these migrate to the edges. The enrichment then results from surface oxidation, in the oxygen case. Predictions are made on the basis of this …
Date: October 10, 1946
Creator: Arnold, James R. & Libby, Willard F.
System: The UNT Digital Library
Analysis for Oxide in Thorium Metal (open access)

Analysis for Oxide in Thorium Metal

Abstract. to estimate the oxygen picked up by thorium in casting a rapid method of running the acid insoluble content was developed. the quickest procedure consists of reacting with mixed acids, fuming with perchloric and filtration to separate the "free" thorium from the "combined". The precipitate is ignited and weighed as thorium dioxide.
Date: May 12, 1945
Creator: Ayers, A. S.
System: The UNT Digital Library
Analysis  of Uranium-Manganese Alloys (open access)

Analysis of Uranium-Manganese Alloys

Introduction. the conventional procedures of analysis for uranium and manganese can be employed in the analysis of alloys of these metals. The alloys are reacted with perchloric acid and hydrogen peroxide, fumed to remove any chloride ions, diluted to volume and aliquots analyzed by redoximetry.
Date: October 5, 1945
Creator: Ayers, A. S.
System: The UNT Digital Library
Precipitation of Thorium Oxalate from Nitric Acid Solutions (open access)

Precipitation of Thorium Oxalate from Nitric Acid Solutions

Introduction. It has been known for a long time that thorium is precipitated by oxalic acid in acid solutions, but a survey of the literature showed no study of the limits of the acidity and oxalic acid excess which yield quantitative results. V. I. Spitzin reports on the solubility of thorium oxalate in varying concentrations of several acids, but the effect of an excess oxalic acid is not included. Since solutions are sometimes presented for analysis that contain more than the recommended two per cent mineral acid, it would be advantageous to be able to quantitatively remove the thorium without otherwise altering the solutions. This was especially of interest in solutions containing bismuth, since it was hoped that some amounts of thorium could be precipitated in nitric acid solutions containing large quantities of bismuth. In removing the bismuth, first by a bismuth oxychloride precipitation, thee is every opportunity for carrying of the thorium.
Date: October 5, 1945
Creator: Ayers, A. S.
System: The UNT Digital Library
Effect of Radiation on Chromate in Water.  III. Inhibition Experiments in the CP-3 Pile (open access)

Effect of Radiation on Chromate in Water. III. Inhibition Experiments in the CP-3 Pile

Abstract. The effect of various inhibitors on the production of CrIII in W waters containing chromatic has been studies at a variety of pH's in the CP-3 pile. The addition of 2 ppm NaClO3 appears to have little effect a a pH of 5.3, but 2 ppm NaClO3 cr 0.15 ppm of Cl2 (in the form of NaOCl) somewhat decreases the amount of chromatic reduced at a pH of 7.1. The inhibition is not great enough, however, to reduce the amount of CrIII formed to the maximum concentration permissible at W (0.02 ppm). The addition of 3 ppm (NH4)2S2O3 as an inhibiter will permit W water to be used a a Ph of 7.0, but not at a pH of 6.5 as far as chromate reduction is concerned. The concentration of CrIII would be 0.01 ppm and 0.05 ppm, respectively, after one passage through the pile. Previous conclusion as to the effects of temperature, pH, intensity and the addition of ammonium persulfate, which had been reached from experiments with simulation W water, have been checked by studies with solutions made from water chipped directly from Hanford. All of the effects noted were found to be similar to those already reported, …
Date: November 2, 1944
Creator: Bowman, M. G.; Burton, Milton, 1902-; Davis, S. G., 1907-; Ghormley, J. A. & Gordon, S.
System: The UNT Digital Library
Uranium Oxide Slurry Pumping Experiments (open access)

Uranium Oxide Slurry Pumping Experiments

Abstract: Experiments on colloid milling and pumping show that uranium trioxide, when carefully dehydrated, can be dispersed in water to form a relatively stable slurry, suitable for a homogeneous slurry pile. At temperatures considerably below those of anticipated pile operation particle size growth occurs attended by increase in settling rate and decrease in viscosity. Theses properties of the slurries may be strongly affected by impurities present as well as by special operating conditions.
Date: September 15, 1944
Creator: Brandt, R. & Dean, G. R.
System: The UNT Digital Library
The Effect of Impurities Upon Sulfide Refractories (open access)

The Effect of Impurities Upon Sulfide Refractories

Abstract. A summary of the effect of metal, carbon, silicon, and oxygen impurities upon the various sulfide refractories is given and the proper procedures for elimination of the impurities are discussed. CeS which is properly prepared can be handled in air without danger of catching fire or appreciable oxidation. 650 satisfactory crucibles have been made to date using sulfides which were screened and pressed in air with less than 0.5% oxygen pickup. The other cerium and thorium sulfides are even more inert to oxidation than is CeS. Phase diagram possibilities are discussed for the cerium and thorium sulfide and oxy-sulfide systems. Further study of the ThS has shown that ThS crucibles are the highest melting and least volatile of the sulfide crucibles and ThS may be used for remelting of some metals up to 2000 degrees C. ThS crucibles appear to be the most suitable containers for metal reductions.
Date: January 20, 1945
Creator: Brewer, L.; Bromley, L. A.; Gilles, P. & Lofgren, N.
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending March 15, 1945 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending March 15, 1945

Technical report with short reports on (1) Effect of radiation on water and aqueous systems; (2) Gas evolution from uranyl solutions; (3) Effect of radiation on solid compounds; (4) Instruments; and (5) Scattering.
Date: March 15, 1945
Creator: Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Period Ending January 15, 1945

Technical report with short reports covering (1) Effect of radiation on water and aqueous systems; (2) Effect of neutrons on graphite; (3) Effect of radiation on solid compounds; and (4) Scattering, stopping-power, ion-pair production, etc.
Date: February 1, 1945
Creator: Burton, Milton, 1902- & Allen, A. O. (Augustine O.)
System: The UNT Digital Library
The Behavior of Some Solid Materials Under Pile Operating Conditions (open access)

The Behavior of Some Solid Materials Under Pile Operating Conditions

Technical report abstract. The present state of knowledge concerning the effect of pile radiation on a variety of solid materials is reviewed. Radiation corrosion will not be a serious hazard for aluminum or stainless steel but it can be for iron or lead if either are exposed to water. Apart from corrosion the principal uncertainty is in regard to the Wigner effect on the behavior of metals. There is at present no ground for optimism regarding the behavior of tuballoy. The effect on aluminum or a bonding material while less severe must also be considered serious. The expectation in regard to graphite is that its behavior will not cause trouble during the first 100 days of operation although serious troubles will probably arise within two years of operation. Organic materials can be used safely only in regions of limited exposure.
Date: July 20, 1944
Creator: Burton, Milton, 1902- & Seitz, Frederick, 1911-2008
System: The UNT Digital Library
Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2] (open access)

Preliminary Report on a Colorimetric Method for the Determination of Microgram Quantities of Thorium : Experiments in the Dissolution of O2 Metal [UO2]

Abstract. thorium can be precipitated as a salt of p-dimethylaminoazophenylarsonic acid at a pH of about 1.5. the precipitate, collected on a sintered glass filter is washed with dilute ammonium hydroxide to dissolve the dye. the amount of thorium is determined by measuring the concentration of the dye spectrophotometrically at a wavelength of 450 millimicrons. Zirconium, which interferes, can be separated and determined using the same reagent in strong hydrochloric. the behavior of thorium metal upon treatment with various acids and upon fusion withKHSO4 is described. three satisfactory procedures are given for dissolving the metal with sulfuric acid, phosphoric acid, and by a potassium hydrogen sulfate fusion. The laboratory was presented with the problem of analyzing for a large number of elements in O2 metal. the results of a systematic study of methods for effecting solution of the metal are offered here since they may be of some interest and use to other laboratories. The four methods which effected complete solution of the metal are (1) Sulfuric acid method; (2) Fusion method; (3) Phosphoric acid method; and (4) Nitric acid-hydrofluoric acid method.
Date: January 1, 1945
Creator: Byerly, W.; Niedrach, L.; Davin, W.; Dyas, H. & Bane, R. W.
System: The UNT Digital Library
Pyrohydrolysis in the Analysis of Fluorides and Other Halides (open access)

Pyrohydrolysis in the Analysis of Fluorides and Other Halides

Abstract. Fluorides and other halides are hydrolyzed completely by passing a rapid stream of superheated steam over the sample near 1000 degrees C in a specially designed platinum reaction tube. The steam and hydrogen halide are condensed by cooling, and the resulting distillate titrated with standard sodium hydroxide solution. The fluorides and chlorides of the light metals, hitherto thought of as very difficult to hydrolyze, are mixed with U3O8, or other metallic oxides, which reacts with the products of hydrolysis, thus shifting the equilibrium so that the reaction is complete in a comparatively short time. A description of the apparatus, including photographs, the recommended method of procedure, hydrolysis rate graphs, and suggestions for further applications of the method are given.
Date: June 30, 1945
Creator: Cline, W. D.
System: The UNT Digital Library
The U + 4 - U02 ++ Couple in H2SO , and the U + S - u + 4 Couple in HCl (open access)

The U + 4 - U02 ++ Couple in H2SO , and the U + S - u + 4 Couple in HCl

Technical report: Measurements have been made on the equilibrium between Cu, Cu2+, U4+, and UO22+ in H2SO4 in an attempt to establish the value of the U4+ - UO22+ couple potential. The value of the formal potential for the U3+ - U4+ couple in 1N HCl at 0 degrees C was determined to be + 0.65 v.
Date: March 19, 1946
Creator: Cubicciotti, D.
System: The UNT Digital Library
Properties of Uranyl Fluoride (open access)

Properties of Uranyl Fluoride

Abstract: Pure UO2F2 is made by reaction between anhydrous HF and pure UO3. Although it is difficult to prepare free of water, it is not very hygroscopic. Prolonged heating at 100-105 degrees releases 99.9% of the water in an aqueous solution; the rate of loss of water is very small after saturation is reached. X-ray diffraction data give a density of 6.2 for the solid. The density of a 1.004 M solution is 1.274; the density of a saturated solution (5.130 M) is 2.400. The densities of F-9 solutions have been calculated from the densities of ordinary aqueous solutions, and the values are compared graphically. Data on the solubility indicate that there is a small increase in the range 25-100 degrees. Recovery of pure F-9 from a solution is hampered by hydrolysis of U)2F2 to give HF. The HF may be held back by addition of UO3 or CaO; the use of the latter, however, makes more difficult the recovery of all the F-9. Molar conductivities of UO2F2 solutions at 25 degrees, as well as the specific conductivities of a 1 molar solution containing various concentrations of UO3, have been determined. The addition of UO3 lowers the conductivity. The low …
Date: September 11, 1944
Creator: Dean, G. R.
System: The UNT Digital Library
Transference and Adsorption on Glass of Carrier Free Zirconium (open access)

Transference and Adsorption on Glass of Carrier Free Zirconium

.Technical report describing the transference experiments. The carrying of zirconium and columbium by ferric hydroxide has a very marked dependence on pH. In the experiments it was noticed that the concentration of Zr activity in various solutions changed with time This indicated that the Zr was being adsorbed on the glass. The carrier free trace is adsorbed on glass. This effect must be considered in experiments with Zr tracer in glass apparatus.
Date: January 3, 1945
Creator: Dodgen, H. W. & Rollefson, G. F.
System: The UNT Digital Library
The Determination of Thorium in Uranium-Thorium Alloys, Using Cupferron (open access)

The Determination of Thorium in Uranium-Thorium Alloys, Using Cupferron

Technical report describing that the use of controlled amounts of carbonate, acting both as complexing agent buffer led to a fairly satisfactory procedure for the determination of Th in Th-U alloys, using cupferron. The alloy, dissolved in NHO2, in the presence of HF, is treated with H2SO4 and the mixture is evaporated in SO2 fumes. The solution is diluted and (NH4)2CO2 is added. Th is precipitated from this solution with cupferron. The precipitate is weighed as ThO2 after ignition. An accuracy of 6% was obtained. A method was developed specifically for the determination of Th in U-Th alloys containing 1 to 10% Th. An ion exchange resin in column is used to separate Th from U, with NH2OH-HCl as complexing agent. The Th is then precipitated, ignited, and weighed in the conventional manner.
Date: November 23, 1945
Creator: Eckert, A. C. & Bane, R. W.
System: The UNT Digital Library
Analysis of Iron in Thorium, Beryllium, and Cerium (open access)

Analysis of Iron in Thorium, Beryllium, and Cerium

Introduction. the colorimetric determination of iron based on the formation of the colored ferrous-1,10-phenanthroline complex has been used successfully by a number of investigators. In this technical report, its adaptation to the routine determination of iron in cerium, thorium, and beryllium metals and their compounds is described.
Date: September 10, 1945
Creator: Ericson, R. P & Fornefeld, E. J.
System: The UNT Digital Library
Analysis of Uranium-Nicked Alloys (open access)

Analysis of Uranium-Nicked Alloys

Abstract. Methods for determination of both uranium and nickel in solutions of these metals are described. Alloys can be dissolved in nitric acid treated with citric acid to complex the uranium, and the nickel precipitated as nicked dimethylglyoxime. The uranium is reduced and titrated with standard ceric sulfate. These methods are for the determination of macro amounts of uranium and nickel with errors on the order of 0.1%.
Date: June 7, 1945
Creator: Ericson, R. P.
System: The UNT Digital Library
Fractionation of Fission Products and Heavy Elements by Volatilization Methods (open access)

Fractionation of Fission Products and Heavy Elements by Volatilization Methods

Technical report describing the attempt to separate the long lived fission product oxides by volatilization methods. A fractionization crucible was used. The fractionations give a fair idea of the relative volatilities of the longer lived fission products and also of the degrees of separation of the plutonium oxide or oxides from the fission products.
Date: August 27, 1946
Creator: Erway, N. D. & Simpson, O. C.
System: The UNT Digital Library
Recovery of D2O and UO2F2 by Distillation (open access)

Recovery of D2O and UO2F2 by Distillation

Technical report describing the purification and separation by distillation of UO2F2 from D2O. In the experiment which is discussed 2,129.6 lbs of UO2F2 were dissolved in 6,605 lbs of D2O. The average isotopic purity of the D2O decreased during the distillation from 99.77% to 99.73%. The dissolved impurities were less than those present originally in the heavy water.
Date: October 10, 1945
Creator: Fischer, R. & Wattenberg, Albert, 1917-
System: The UNT Digital Library
Analysis of Heavy Water by Equilibration (open access)

Analysis of Heavy Water by Equilibration

Technical report discussing that the deuterium concentration of heavy water can be determined by equilibrating the water with deuterium gas in the presence of a catalyst with subsequent analysis of the equilibrated gas on the mas spectrometer. The apparatus for equilibration analyses maybe be considered in three parts: 1) apparatus for introducing the ingredients into the reaction chambers; 2) the reaction chambers; 3) the mass spectrometer for analysis of the equilibrated gas. The isotopic composition of the deuterium gas to be used as the starting material is primarily governed by what gases are available. In general it is best to use gas within about one percent on either side of the final equilibrium composition. No reaction takes place between deuterium gas and water molecules in the absence of a catalyst. Platinum oxide is used as the catalyst.
Date: May 15, 1945
Creator: Fischer, R. B.; Potter, R. A. & Voskuyl, R. J.
System: The UNT Digital Library