Report discussing reaction of hydrogen with uranium in a range of temperatures and pressures. Experimental materials, methods and results are included.

The following report describes two rapid, micro methods for the determination of UNH in Redox waste samples that had been developed fir the concentration range 0.2 to 100 g/l.

A high-vacuum casting furnace with an internal diameter of 15 inches has been designed, fabricated, and installed at LASL. The furnace was designed to accommodate casting crucibles up to 7 inches OD; however with a larger diameter heating element, casting crucibles up to 9 inches could be accommodated. This report describes the basic features of the furnace and presents engineering drawings of both the furnace and the furnace box.

Report outlining a study that tested the use of colorimetric methods with high concentration phosphoric acid as a solvent for rapid analysis of mixtures of T^+4 and T^+6.

The following report is a study of the separating qualities of a loop-type separator that can obtain separation with a smaller pressure drop.

The horizontal and vertical power distribution for a 5 x 7 fuel element loading of the TSR is presented. (auth)

The preparation of radioactive metallurgical specimens for microscopic examination is one of the responsibilities of the Radiometallurgy Sub-Unit. An abrasive cut-off machine development program, based upon a previous experimental model, was undertaken to provide a method for sectioning of irradiated materials without undue personnel exposure or spread of contamination and finally to provide data for the design of an abrasive cutting unit for use in the work cells in the Radiometallurgy Building. A horizontal-feed type set-off machine, powered by a 7 1/2 hp motor with V-belt drive, has been developed for the submerged sectioning of irradiated uranium and is currently being used successfully to obtain samples for metallurgical, chemical and physical investigations without excessive personnel exposure or spread of radioactive contaminates.

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.

Report summarizing physical studies on Redox solutions and metal waste solutions, including refractometric investigations.

The creep problems associated with zircaloy-2 process tubes and the factors affecting the creep of these tubes were discussed in detail. Emphasis was placed on the determination of the tube wall thickness for an SPR tube, whose minimum thickness is limited by creep considerations. It was concluded that, at the present time, there is not enough information available to design zircaloy-2 process tubes on a realistic basis. Various experiments were suggested to supplement the creep rate testing program being pursued by Battelle Memorial Institute.

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.

The following report provides data taken from investigations on radiation and the different biologic effects on it.

In the Columbia River downstream from Richland, Washington there is a gradual decrease in concentration of radioactive isotope. At any one location there are fluctuations due to factors such as dilution and decay time. During this period at all locations the concentration of alpha particle emitters in water averaged below the detection limit. Beta particle emitters in water upstream of McNary Dam decreased slightly due to increased river flow this quarter, with averages at various locations. Downstream from McNary Dam, beta particle emitter average concentrations in water were about the same as the past three quarters.

This report summarizes the research and development work carried out during June, July, and August, 1959, for Budget Activity 2790- Separations Development for Non-Production Reactors. The effort on Activity 2790 - Separations Development for Non-Production Reactors. The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.

Report that summarizes unreported neutron-yield data for the MnSO₄ tank method. Other yield measurements had been reported in other quarterly reports prior to the completion of this one.

Summary of research progress conducted on subjects such heavy element energy cycles and scattering.

The resonance absorption of a lump is described in terms of three components. Calculations of resonance absorption are carried out using the model for the resonance spectrum of uranium recently derived; calculations are also made with variations of this model which involve local fluctuations in level strengths. For metal and oxide lumps the agreement with observation is satisfactory. For dilute mixtures, whose resonance activation was measured by Mitchell, computed values fall 20% to 30% above measured ones.

This report covers the S-I-5-B-M fuel irradiation in the GETR Maritime Loop during the final quarter of fiscal year 1962 plus the month of July 1962 to conclude the irradiation program. The data are summarized in Section II.

A need for a small vertical cylinder-type furnace arises frequently in the Chemistry Department at the Lawrence Radiation Laboratory (LRL). Adequate heat is the major requirement; close control or calibration is not usually necessary. A heating unit of this type can either be used for quickly concentrating solutions in centrifuge cones or, by the addition of a refractory pedestal--can be made into a crucible furnace for size 0 and 00 crucibles. Because much of the chemistry done at LRL is with radioisotopes, disposal of contaminated equipment is an important consideration. In general, furnaces are difficult to decontaminate, hence there was a need for a disposable type. Because nothing meeting the requirements seemed to be commercially available, the Health Chemistry Department made up a simple furnace that has proved useful.

Abstract:"A method is described for the electroreduction of plutonium to the +3 valence state in a nitric acid-sulfamic acid solution. Exploratory experiments in the search for a coulometric titration of Pu(III) using electrolytically generated ceric ion are also described. The results strongly indicate that a convenient procedure can be devised. Suggestions for future work are presented."

"As a part of a program to determine the p-p scattering matrix at 213 Mev, the triple scattering parameters R and A were measured at 30, 40, 50, 60, 70, 80. and 90 deg in the center-of-msss system. The results are compared with a phase shift analysis by MacGregor and Moravcsik and with the predictions of the boundary condition model of Saylor, Bryan and Marshak."

Abstract: "A method for determination of dibutyl phosphate in solvent streams containing tributyl phosphate is outlined. The method is based on analysis for total uranium of total phosphate after removal of uranium and phosphate in excess of that present as uranyl dibutyl phosphate. Results on plant solvent samples are presented. Difficulties with precipitation of [...] dibutyl phosphate, when fresh solvents were employed, are discussed. Small amounts of nonphosphate uranium-complexing agents were found in plant solvents. Diluent degradation is postulated as the source of these components. Emulsion-formation tendencies appeared to correlate better with concentrations of these contaminants than with dibutyl phosphate content."

This summary of the research progress meeting on June 17, 1948 discusses the following topics: (1) Potassium 43 (R. Overstreet); (2) Recoils (A. Ghiorso); (3) M.I.T. accelerator conference (W. Panofsky); and (4) Cosmic rays (Prof. Louis Le prince - Ringuet, France)

Detailed information on the radiations associated with several even-even isotopes has been obtained. In some instances enough information has been gathered to allow construction of skeleton energy level diagrams for the isotopes. Activities studied were obtained from pile irradiation of pure odd-even natural isotopes and included Dy160, W182, Sm152, Gd152 and Gd154. Details of the work done on and results obtained for these isotopes are reported in section 3. Some analytic and experimental studies were carried out on the application of tilting beta-ray spectrograph sources for improvement of resolution. The uses and limitation of this technique are discussed in section 2.