From abstract: "The variation of the reactivity of a pile as a function of width of a transverse gap is obtained. The method involves first finding the boundary condition satisfied by the flux at the gap face. This, in principle, provides enough information for a complete solution of the pile equations. A method for calculating the reactivity change is presented. The calculated reactivity is compared with experiment and a brief discussion of the validity of the approximations is given."

From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher distribution coefficients than the corresponding esters, and the distribution coefficients increased with the number of such carbon to phosphorus bonds. Tributyl phosphine oxide (with three carbon to phosphorus bonds) showed high distribution coefficients with many salts, including uranyl nitrate, uranyl sulfate, uranyl chloride, thorium nitrate, plutonium (IV) nitrate and some of the fission products in nitrate solution. It is planned to study these and similar compounds further."

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."

Abstract: "The analysis of an immobilized plasma is here extended to the case where the geometry is cylindrical rather than Cartesian. (This report, UCRL-4439 (Rev, 4 constitutes Part II of the report series (UCRL-4466, Parts I, III, and IV) dealing with this general problem.)"

Abstract The phase diagram of the uranium-rhenium alloy system is presented along with a discussion on transformation kinetics of the uranium solid solutions. The phase diagram is of the double eutectic type with the intermediate phase having the composition URe2. This phase exhibits allotropy at 180°C and melts congruently at 2200°C. URe2 reacts sluggishly with the uranium solid solutions below 750°C to form the peritectoid compound U2Re. Eutectic reactions occur at 1105° and 2105°C at respective compositions of 10.5 and 65.5 wt. % Re. Eutectoid reactions occur at 643° and 681°C at compositions of 1.4 and 6 wt. % Re, respectively. The maximum solubility of rhenium in α uranium is about 0.4 wt. % at 643°C and in β uranium is 1.9 wt. % at 681°C. The solubility of rhenium in γ uranium is 6 wt. % at 681°C and increases to about 7 wt. % at 975°C. The solubility of uranium in rhenium is 0.6 wt. % at room temperature with little variation up to 2000°C. Alloys of β and γ uranium containing more than about 1.2 and 7 wt. % Re respectively, can be readily supercooled to room temperature. Rapid cooling of γ alloys containing less than about …

The following report on the nuclear synthesis of technetium is based on work performed under contract No. W-7405-eng-26 for the Atomic Energy Project at Oak Ridge National Laboratory.

The following report discusses the renewed element 43, or eka-manganese, whose discovery was heralded in 1925, but whose chemical properties remained unreported until the radiochemical investigations of Perrier and Segre."

Abstract: "A method of recovering the tuballoy from the trap washes of the high temperature salvage chlorinator is described."

From abstract: "A simple electronic circuit is described, the use of which greatly improves the temperature regulations obtainable with Beta equipment. The circuit utilizes the time derivative of the temperature to counteract oscillation and overshoot. No other changes are required in existing equipment for installation of the stabilizer."

Abstract: Twenty-two metallic oxides were refluxed with hexachloropropylene. The anhydrous chlorides or other products formed are described for each oxide. The reactions were particularly vigorous with higher valent oxides of the fifth and sixth group elements.

The following report measures a shield mockup in three regions: the first made almost entire of iron; the second, transition, region is made of various thicknesses of B4C; and the third region was borated water. The iron samples used in the experiments were made in the form of rectangular plates and place in the lid tank; however, the plates were not completely flat and created a water gap that was measured in this report.

An attempt to apply quantitatively the equation of state of a free electron gas to relatively low temperatures in order to emphasize correlation effects.

The following report describes the crystal structures of NpC and Pu2O3 identified by x-ray diffraction.

Abstract: The radiations of U²³⁷ have been studied using a magnetic lens beta ray spectrometer and scintillation spectrometers for betas and gammas singly and in coincidence. A beta with an end point energy of 245 keV was found along with evidence for the existence of lower energy components. Gammas of energy 27, 42, 49, 59, 166, 208, 269, 354, 431, and 467 keV were found, and probably a gamma of 102 keV. The decay scheme constructed gives a total decay energy for this isotope of 512 keV.

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.