From abstract: "This report contains a summary of biological information on distribution, excretion, and toxicity of polonium; a comparison of results obtained when maximum permissible exposure rates for man are calculated from available data by different methods; and a critical evaluation of the present status of Po tolerance estimates."

The following document describes observations from tests on neptunium metal and their reactions to different room temperatures.

"The following is an evaluation of a modified Zircaloy-2 ingot melted at WAPD using the non-consumable electrode melting technique. The nominal composition of the alloy is 0.5% tin, 0.1% iron, 0.1% chromium, and 0.5% nickel."

Report discussing a study testing features of the absorption spectra of different oxidation states of neptunium and perchloric acid concentration's effects on the spectra. Data regarding a disproportionation reaction present in neptunium(V) solutions in concentrated acid is included.

From abstract: "The cross section of carbon for the n, y reaction was determined using samples of graphite, barium carbonate and carbon dioxide. The results were consistent only when samples were used which were enriched in C¹³."

The following report introduces the aquadag, a part of the stellarator with the purposes to prevent the non-uniform accumulation of electrostatic charges on the walls of the stellerator and to free the electrons of the stellerator and provide accelerations, achieving a uniform field distribution.

The following report provides data based off of the solubility of sodium uranyl acetate that was measured under a variety if conditions.

Introduction: "In the early operation of the WTR severe canal corrosion of dummy fuel assemblies and a beryllium A-piece caused a great deal of concern as to the possible effects of long-time canal storage on such elements. A short-term experimental program was started to determine the causes of this corrosion and to correct them before any irradiated fuel elements had to be stored in the canal. The results of this program are presented here."

Report discussing the effects of xenon-135 and samarium-149 on the reactivity of nuclear reactors. The findings are presented in a "general manner, so as to be applicable to both the Converter and PuP Reactors."

This report discusses details of the release of Xe¹³¹, Xe¹³⁵, Kr⁸⁵m and Kr⁸⁵ into the process water system of the MTR along with the development of high process water radioactivity. It is suggested that this release followed the fissioning of U²³⁵. Equations that produce the rate of release of fission products is given and approximate rate of release is represented in a graph.

Report discussing measurements of thermal conductivity and heat capacity for uranium-chromium and uranium-iron eutectic alloys at room temperature. The resulting values were intended for use in design calculations until more accurate data at other temperatures was obtained.

The following report analyzes experiments on urinary samples of personnel who were exposed to radioactive materials. This report describes the procedure employed for this assay, and data to show its performance and reasons for its present course are presented.

Report discussing calutron charge materials that can be used for the stable separation of isotopes.

Abstract: "The information contained in this report consists of personnel exposures to radioactive dust resulting from a thorium rolling operation."

From introduction: "This report summarizes the experimental data obtained at the San Pablo Laboratory on the corrosion of 5% Cr - 0.5% Mo steel by bismuth under conditions that allow mass transfer to occur. The bismuth is circulated through a temperature gradient by means of a thermosiphon loop."

Technical report on the geological investigation of the Green River desert area, Utah, studying uranium deposits in the area.

Conclusions from the study: "Radioactive dusts are carcinogenic, and can cause cancer of the lung. complete dose response curves have not yet been determined. All the parameters that render this demonstrably toxic material (radioactive dust) have not yet been evaluated. It is strongly suggested by the experimental data that duration of radiological insult to the lung is an important factor in eliciting lung cancer. The atmospheric tolerance concentrations now in use seem to afford little margin of safety."

Radioactive decay data are used to calculate the atomic masses of the heavy isotopes, A> 203. The four radioactive families are then connected by means of neutron binding energies known from reactions on various isotopes. Finally all the masses are collectively adjusted for the best fit with mass spectrographic information available in this region. The masses so calculated are presented. Differences between masses of isotopes are estimated to have an of (plus/minus) 0.00020 mas units or about 200 Kev; the position of the masses taken collectively is in doubt by about 1.5 Mev.

The thermal decomposition of the higher oxides of praseodymium and americium have been investigated.

A two-group approximation of the fission ratios and Pu production in an infinite hollow matrix is developed

This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).

The effects of oxidation and irradiation on the microsurface structure of pile graphite have been investigated by measuring the surface area and pore size distribution of several samples. The results obtained for both oxidized and irradiated graphite samples indicate that changes in surface characteristics which occur are determined by the flux, temperature of irradiation, and gaseous atmosphere in which the radiation takes place.

This report describes observations of a sample of Carbon-14, or radiocarbon, made using the method of mass spectrometry.

The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifications for which they were designed. Welding techniques for type 316 stainless steel are described. The specifications and operating conditions of the units are given along with instrumentation drawings showing test equipment design and arrangement.