The process of age calculation for Hanford exponential lattices containing aluminum-matrix slugs, where the sums run over the materials of the lattice cell.

Abstract: "A titrimetric method for the determination of fluoride in plutonium is reported. Prior to a steam distillation of the fluoride, the bulk of the plutonium is separated by precipitation of the sulfate. The fluoride in the distillate is titrated at a pH of 3.2 with 0.001 M thorium nitrate, using chrome azurol-S indicator. Applied to samples containing 1 to 15 parts per million fluoride, the recovery is 87% and the precision on the 95% confidence level is +/- 0.65 ppm."

Experimental data pertinent to the evaluation of hazards involved in the exposure of personnel to tritium and tritium oxide are reviewed. Conclusions are drawn and recommendations made with regard to the control of these hazards.

An electromagnetic instrument similar to the Multitest was built and used to test 2200 uranium slugs. It was found that the equipment could be used to detect inclusions and cracks in the uranium, but that small cracks are not readily detectable on a production basis unless the material is absolutely uniform in inclusion content. The instrument can be used, however, to sort out hidden defects of a reasonable size and to reject grossly dirty uranium.

Several failures have occurred in reduction bombs used in metal production operations. A test program is being initiated to evaluate new metals for the construction of the bomb. In the test program, a tensile specimen is cycled through temperatures simulating operating temperatures, and the time to rupture is recorded in order to estimate the life in operation of a reduction bomb made with the candidate metal. In order to find the worst stress condition, the compressive, hoop, and bending stresses must be considered.

Large savings in waste storage space may be realized by lowering the pH at which TBP waste is stored. Additional savings in neutralizing chemicals and operating time would also increase the monetary gain from such a process change. However, before such a change could be made, the corrosive effect of TBP waste at a lower pH on the mild steel waste storage tanks had to be determined.

The prompt administration of zirconium citrate was at least twice as effective as the prompt administration of calcium disodium salt of ethylenediaminetetraacetic acid (CaEDTA) in preventing deposition of plutonium in the skeleton. On the other hand, CaEDTA was twice as effective as zirconium citrate in preventing the deposition of plutonium in soft tissues. The combined administration of zirconium citrate and CaEDTA was the most effective treatment for preventing the deposition of plutonium in the total rat. Zirconium malate offered no advantage over zirconium citrate, and appeared to be somewhat more toxic. Three doses of the zirconium salts over a four-day period were no more effective than a single dose.

Four D-12 coil nests have failed since the start-up of the Redox Separations plant. Due to the high contamination and radiation levels of these vessels, the cost of decontamination has prevented the examination of all but one of the four. It was hoped that the examination of D-12 pot #2 would lead to an explanation of all four failures. This report will deal primarily with the metallurgical examination of the failure of D-12 pot #2.

An addendum to report HW-30390 a additional power generation calculation for P, the rate of energy release, in kilowatts, was derived.

The investigation to be described in this paper was one of several undertaken to resolve a curious discrepancy that had arisen in measurements of the diffusion length of graphite. Those diffusion lengths measured with the graphite layups of 100 Area piles were three to six centimeters higher than the value obtained with the Hanford Standard Pile. The fact that the 100 Area structures of the order of 40 ft. X 40 ft. X 30 ft, not including reflector, approximated an infinite medium, whereas sigma piles are of the order of 8 ft. X 8ft. X 10 ft., suggested the possibility that the diffusion length obtained by mensuration of relative fluxes and application of the conventional equations depended in some way on the size of the medium. Therefore, in order to determine if such a dependency actually exists, it was proposed to erect a series of graphite stacks of different dimensions and to make diffusion length measurements in each.

Temperature calculations have been made to aid in planning a production test for low level irradiation of the thin rectangular uranium wafers. These uranium wafers, under irradiation in the outer fringe sone, are expected to have a maximum temperature which is less than 10 C above the local water temperature.

The purpose of this manual is to present available data which can be used to determine disintegration rates of radioactive samples from counting rates measured under given circumstances with routinely used laboratory instruments. There is also brief discussion on the methods by which the various factors have been determined with reference to the accuracy with which they are known and to what extent the finally quoted disintegration rate is affected by these errors. Emphasis has been placed on those isotopes of particular interest to Radiological Sciences programs and the manual is intended as a standard through the use of which comparable values can be reported from all units in the Department.

The purpose of this study has been to evaluate the chemical resistance of various bearing materials to solutions of nitric acid and uranyl nitrate hexahydrate with views toward selecting the best material to be used as bearings in Purex submerged rotating equipment.

The Hanford Remote Pipetter has developed into a very useful tool for routine pipetting by semi-skilled non-technical personnel. Radiation exposure to the operators has decreased to normal background levels as proper shielding exists between the sample and the operator. The results achieved by the pipetter have demonstrated its flexibility and simplicity of operation.

The feasibility of using Teflon bellows as the pulsing device for solvent extraction pulse columns has been previously demonstrated by life test of various sizes of Teflon bellows. This report describes a compact Teflon bellows pulse generator and drive assembly which was designed, built, and tested by the Chemical Development Unit. The pulse generator assembly is suitable for a number of applications where pulse generators are required to pulse solvent extraction columns.

Describes the current prototype model of a linear amplifier, two-channel pulse-height analyser, two-channel count-rate meter, and count-rate difference detector for a gamma-ray spectrometer monitor developed to approach the above design criteria.

Results of four experimental heats run at the end of the G-5 contract in the National Carbon Company Clarksburg production furnaces.