Preliminary studies were made of the relationship between the size of particles suspended in the lower atmosphere and the amount and nature of radionuclides they contain. Emphasis was placed on the distribution of strontium90. From a limited number of analyses, it was found that strontium-90 is associated primarily with particles below 0.1 micron in diameter. Preliminary studies were made of scavenging of particles by liquid water droplets. Studies are included of sticking probability and the effects of Brownian motion and water vapor diffusion. It was found that electrostatic effects are of primary importance for 1.9-micron (mean volume diameter) particles. Brownian motion and water vapor diffusion did not contribute to the scavenging. These results are based on known and new equations derived for various scavenging conditions. (auth)

Two alternate systems, acetic acid-nickel and acetic acid-cobalt, were examined for possible replacement of the corrosion system: ferric chloride-nickel which is being used in the current transpiration corrosion protection studies. Two Fluorox fluidized bed runs were made, of 9 and 58 hr duration, in which dry air and oxygen were used as oxidizing and fluidizing gases. Tests of the hydroclone classification of thoria indicated that more than 95% of the +0.5 micron particles can be removed from a sample if 50% recovery of the -0.5 micron particles is acceptable. Fluidized bed denitration of ThNT did not produce large dense ThO/sub 2/ particles, but flame denitration of mixed thorium-uranium- aluminum nitrates produced spherical particles. Three alternate batch Darex flowsheets gave chloride removal to less than 350 ppm with 61% nitric acid feed, while dissolution studies of APPR fuel elements showed that complete dissolution of braze metal in aqua regia may be difficult. Leaching studies of unirradiated UO/sub 2/ pellets showed that the most important variable effecting dissolution rate was the total nitrate content of the dissolvent. Delivery of tae SRE decanning equipment was scheduled for April 1, 1959. Temperatare increases in cylinders of solid radioactive waste were calculated for APPR fuel …

A brief summary, with reference literature for details, of pertinent and important process flowsheet conditions which are in use in the Purex Process is presented. (auth)

Studies concerned with the deposition of salts from simulated fuel solution under boiling conditions were continued. Additional deposition tests were carried out in loop L-2-23 in which the core section was heated. Several reagents were tested to determine their ability to dissolve stainless steel corrosion products. A simulated HRT fuel solution was stable with regard to U concentration when diluted to 23 ppm at 250 C; however, some Cu was lost from solution. Preliminary tests in a uranyl sulfate solution indicate that an 18-8 stainless steel alloyed with either small amounts of Pt or Cu is more corrosion resistant at low flow rates than a conventional 18-8 stainless steel; however, the addition of either Cu or Pt did not reduce the corrosion rate of 18stainless steel at high flow rates. A study was made to determine the susceptibility of off-specification type 347 stainless steel to intergranular attack by uranyl sulfate solutions. Continued testing with a single heat of cast type 347 stainless steel has confirmed previously reported data to the effect that the cast alloy is more resistant a stress-corrosion cracking than is the wrought alloy. Six commercial grades of Al/sub 2/O/sub 3/ suitable for use as check balls in …

The CUREBO code for the IBM 704 is described. The code is divided into three parts including the calculation of nuclear cross section of the various physical components of a reactor (WOX7), the solution of the multigroup diffusion equations in two-space dimensions in order to find neutron fluxes and sources for an operating reactor containing these components ( CURE), and the calculation of fuel and poison depletion as a result of operating this reactor under steady- state conditions (BO2). (auth)

The intermetallic compounds of the zirconium-irontin system (i.e., ZrFe/ sub 2/ and Zr/sub 4/Sn) were studied at 500 and 1100 C. The alloys were prepared from iodide zirconium and high-purity iron and tin by nonconsumableelectrode arc melting techniques under an inert atmospherc. Specimens were encapsulated in Vycor and annealed at the prescribed temperatures followed by a water quench. Data were gathered through the use of metallographic, x-ray diffraction, visible incipient melting, and magnetic susceptibility techniques. It was determined that Zr/sub 4/Sn (24.5 wt.% Sn) and (24.5 wt.% Sn and 7 to 8 wt.% Fe) are separate phases which are not in equilibrium with each other. ZrFe/sub 2/ was firmly established at its stoichiometric composition of 55 wt.% Fe, and it apparently has negligible solubility for tin. The specific magnetization of this ferromagnetic compound is of thc order of 55 cgs at room temperature. Its Curie temperature is about 355 C. (auth)

This report is the final in a series of preliminary reports that follow the studies of scavenging systems related to radioactive fallout. The project consisted of two phases: preliminary experiments to relate the sizes of particles in air to specific radioisotopes, and preliminary laboratory studies of scavenging of particles by liquid drops, including studies of sticking probability and effects of Brownian motion and water vapor diffusion.

The purpose of this report is to present the results of laboratory experiments in which coolant water flowed backwards through a ``C`` reactor process tube with operational charge-discharge front fittings under conditions of typical reactor rear header pressures and post-scram rear header water temperature and tube powers. This information is of value in planning and interpreting transient experiments investigating the consequences of the rupture of reactor front face piping to a single tube.

This test will determine approximately the relationship between the power rate of rise indicated by the power rate meter and the actual pile power, rising period, and power rate. The actual pile power and power rate cannot be measured accurately during rapidly changing conditions; it is the intent of this test primarily to demonstrate that rate of rise protection offered by the power rate meter an be calculated to the same order of accuracy as the measurements of actual conditions.