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.

The following report describes the process of the determination of nitrous oxide with the infrared spectrometer.

Abstract: This report gives the results of a radiochemical analysis of particles collected by electrostatic precipitation from ventilation air of the "B" plant at Hanford Works.

The following report covers the construction materials selected for laboratory corrosion studies and the determination of their corrosion rates in process solutions.

This report follows work that is meant to determine the settling rate and viscosity of Hanford Waste metal slurry as a function of prolonged agitation and shear, and to repeat these determinations on a synthetic incubated material similar to that used in the acidification studies, HW-18367, and to make a direct comparison between the genuine and simulated wastes.

Abstract: "This is the preliminary report of a radiological-ecological survey of the invertebrate fauna that inhabit the Columbia River within the confines of Hanford Works and downstream to the site of McNary Dam. The survey was carried out during the period of October, 1948 through February, 1950. Materials and methods are discussed and the results of extensive radioassays, qualitative and quantitative biological determinations, and hydrographic studies are given and analyzed. Twelve figures and twenty-three tables are included. All aquatic invertebrates were found to be concentrating radioactivity from the river water. A maximum activity density of 4.4-10-(-3) μc/g wet weight was found in the larvae of midges (Hydrobaeninae) collected near Hanford during September, 1949. Radioactive wastes were not found to be causing any apparent deleterious effects to the natural invertebrate fauna. Existing population variations are caused by biological and hydrographic conditions."

The following report calculates pile reactivity changes that result from different pile loadings where it is desirable to have available values of (flux)2 d(volume) for various flat zone radii. This information was found for a cylindrical pile having circular flat zones and an effective radius of 598 cm., by integrating over a cross sectional volume of one cm. thickness.

The following report provides the results of an accelerated corrosion test that was performed to compare the effect of two coagulants on the corrosion rates of aluminum slug jacket alloy and 72S. Additionally, some analytical data on the water from the two treatments were obtained and are presented in this report.

Objective: "Production Test 235-1 and an amendment, were written to outline the procedures for reducing the outgassing time and evaluating the effects of these reductions."

This report examines a uranium slug that has been produced by powder metallurgical methods and exposed in the 100-DR Pile and was deformed during pile exposure.

From introduction: "The following recommendations represent the best estimate, based on present knowledge, of the requirements for generally applicable or "universal" instrument for the continuous monitoring of radioactive process streams in terms of their gamma activity."

During an experiment involving alpha phase annealing (at 610 to 655 deg C for 5 and 10 min) of beta-quenched uranium, it was determined that the relatively coarse, irregular shaped grains (0.08 to 0.150 mm in diameter) in the beta-quenched structure, were replaced by fine equiaxed grains (0.04 to 0.09 mm in diameter).

A study was performed to determine the economic incentives associated with in-pile boiling, with the explicit assumption that this method of operation was technically feasible. A non-boiling reactor plant was used as a comparison, and the net electric generation was held constant at 400 Mw. The economic effect of variations in specific power from 47 to 32 kw/ft., and steam qualities of 10 to 60% were studied. The results showed that, under the conditions used, the unit power cost during single purpose operation would be in the range 5.9 to 6.1 mils/kw-hr at the generator bus-bar, compared to an estimated 6.6 mils/ kw-hr. for the non-boiling plant. These gains are realized under conditions of relatively high specific powers, greater than 32 kw/ft., relatively modest bulk outlet steam quality (greater than 20%), and high-pressure steam (1000 psia or higher) used directly in the turbines. During the dual market period, the power rate is about the same. An increase of 0.2 mils/kw-hr. is indicated when the specific power is lowered- Capital investment savings of perhaps four to five million dollars may be possible, but savings of this magnitude have little effect on the over-all power cost. The power cost savings stated above …

Experimental studies on continuous denitration performed in 321 Building resulted in the development of an agitated-through-type calciner. The performance of a paddle-agitated 4-in.-diameter by 44-in.-long reactor was sufficiently promising to warrant construction of a 16-in.-diameter by 8 ft.-long semi-plant scale model. This progress report summarizes the results of studies to date employing the semi-plant scale calciner.

A two-etchant surface preparation treatment has been found which insures good adhesion between the zirconium and the nickel or copper electroplate. The etching process requires 1 1/2 minutes.

The purpose of this investigation is to make a preliminary study and evaluation of the application of ultrasonic equipment and associated handling equipment to the problem of decontaminating reactor tube dummy pieces. Reactor Section is currently planning the construction of batch process nitric acid facilities for dummy decontamination. It was felt that use of ultrasonics together with a solution less corrosive than nitric acid might provide adequate decontamination at lower project cost than the presently proposed nitric acid facilities. This report gives the progress of the investigation to date.

A portable GM survey instrument was designed and developed which consists of a single transistor blocking-oscillator high voltage supply, a dual transistor multivibrator count-rate meter and a standard 30 mg/cm² glass-wall GM tube.

Among the safety considerations for the Purex plant is the question of flammability limits for the diluent-air system. The present note attempts to delineate the temperature regions of concern by utilizing hydrocarbon flammability data available together with information on the vapor pressures of the systems.

This twenty-fifth quarterly report of the research and development activities of the Radiological Sciences Department, Hanford Atomic Products operation, as before, includes some items charged to control but included for general interest. The previous report of this series was numbered: HW-39624, October 11, 1955. Progress is reported in the following studies: a radiobiological-ecological survey of the Columbia River; the toxic effects of continuous low-level exposure to I¹³¹ in pigs; Pu metabolism in miniature pigs and rats; the tissue distribution and retention of Ru¹⁰⁶ and Cs in rats and mice; the radiosensitivity of the intestine of rats; the pulmonary absorption of radioactive particles and the pathological effects of such particles in the lungs of mice; the uptake of I¹³¹ and other fission products from the soil and from air by plants; determinations of the relative biological effectiveness for yeast cells of Po²¹⁰ alpha particles and P³² beta particles; the development of chemical and radiological monitoring methods; the separation of fission products from waste streams; and improvements in instruments for monitoring and low-level radiation counting. The status of the research programs of the department is reviewed.

A general method is developed to allow calculation of the critical buckling of an assemblage of fissile regions coupled by neutron leakage. Consideration is given both to regions embedded in vacuum and in material media. Several cases of simple geometry are further developed to illustrate the theory.

This paper presents the results of a series of buckling measurements involving the use of enriched uranium rods (1.007% by weight U²³⁵) in light water. The effect of replacing a water reflector with one of uranyl nitrate solution of two different concentrations, 536 and 188 grams of U per liter of solution was investigated for the 0.925" rods with the 1.74 H₂O/U-volume ratio in the core. Some information was also obtained on the extrapolation length to be used in unreflected cases. The application of theory to these lattices, and others, is given in an appendix under separate title, "Buckling Calculations for One Per Cent Enriched Uranium-Water Rod Lattices."

The purpose of this document is to review the stud situation at Purex and make such recommendations as possible for use in any future canyon installations.

This report provides an overview of a gridded ionization chamber, instructions on how to operate the instrument, and then discusses the performance of the instrument so far.

The purpose of this report is to provide calculated liquid flow pressure drop data for the 1706-KER recirculation loops.