Technical report. From Summary : "At the present time arsenazo appears to be widely used for the spectrophotometric determination of rare earths. Unfortunately, the method is not selective. The separation of rare earths and yttrium from interfering elements has been studied, and the following method has been proposed. Rare earths are precipitated as fluorides using fluorides using calcium fluoride as the carrier. Thorium and zirconium are removed by extraction with thenoyltrifluoroacetone (TTA) in xylene at pH 1.3. Small amounts of residual aluminum, iron, etc. are removed by extraction with 8-quinolinolchloroform at pH 4.5. Rare earths are separated from calcium by TTA extraction at the same pH, and they are then back-extracted into 1 M nitric acid. After evaporation of the solution, the rare earths are determined spectrophotometrically with arsenazo."

Research at the University of California Radiation Laboratory has been directed toward the development of processes designed to recover plutonium and uranium from neutron-irradiated uranium. This report has been prepared in answer to requests for information by interested workers in the Atomic Energy programs. The material discussed herein represents the efforts of a sizable research group over several years, and summarizes both the current status of the investigation and the future program now contemplated.

The use of thermally fissionable material in the lattice adds a distributed source of fast neutrons which must be considered in evaluating the problem.

From introduction: "The Boltzmann equation expressing conversation of particles in phase space is set up."

The general purpose of this report is to present the major characteristics and design of the Consolidated Edison Thorium Reactor (CETR) core

Abstract: This technical report elucidates principles of hazards evaluation. The concept of hazards potential is introduced and utilized to show how a reactor system perturbation will influence its nuclear safety. Literature relating to reactor safety is referenced to provide the sources of information required for hazards analysis and show how they influence a hazards evaluation. A checklist of items which should be considered in evaluating a change, test, or modification is presented.

The influence of the Doppler effect in the core disassembly process following a meltdown accident is examined with a Bethe-Tait type model in which the Doppler effect, as well as core disassembly, is considered in the reactor shutdown process. It is shown that a strong negative Doppler effect can radically reduce the explosive energy release in such an accident. (auth)

In connection with different seals for C & D equipment it appears advantageous that many parts could be made of rubber or other elastic polymers. However, data on the deterioration rate of these materials under irradiation are somewhat scant in the available literature. It appears that for neutrons and pure gamma radiation that a good grade of natural rubber stands up best in all the test reported and because the results of the neutron irradiation are so closely correlated with results from gamma it has been proposed that the principal source of damage is caused by secondary irradiation generated within the rubber by the neutrons.

This technical report presents "a theoretical study of the motion of gas bubbles in a rotating liquid" in order to "make comparison with experimental data from an investigation concerning the removal of gas bubbles from rotating liquids as descriped in ORNL-630." The report presents a literature review of "motion of gas bubbles in liquids" and provides a "summary of extensive experimental studies at the University of Tennessee." It also presents "an expression for the radial velocity of a gas bubble in a rotating liquid based on principles of mechanics." Finally, this report presents "a method for computing the steady state state [sic] gas hold-up in the HRE reactor core under power producing conditions." (From introduction)

Report summarizing strontium 90 analyses collected throughout the world in order to determine the relationship between precipitation and nuclear fallout.

Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.

Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).

Three graphs representing the four series of isotopes.

Critical review of the information on zirconium, with estimates of the uncertainty in the values.

This report discusses enhanced Hg202 as a source of monochromatic light in relation to the effects of the isotopic impurities.

Report describing the blood cultures of fifty-four dogs that were exposed mid-lethal whole body x-radiation.

From introduction: "Report describing the study of radiation damage in boron carbide with an integrated thermal neutron flux of 3x10^20 neutrons/cm² in the Materials Testing Reactor (MTR)."

Report regarding the chemical processing instrumentation designs and problems at the Idaho Chemical Processing Plant.

Technical report covering the Homogeneous Reactor Experiment (HRE) reactor physics and engineering, out-of-pile corrosion, in-pile studies, recombination of hydrogen and oxygen, HRE chemical studies, experimental programs for the HRE, and long-range studies. [From Summary]

The purpose of the test was to determine the temperature and pressure coefficients of reactivity at zero power. Data was obtained during this test which indicates a new temperature coefficient and a pressure coefficient corrected to station operating conditions of 500 F and 1785 PSIG.

The purpose of the test was to determine the level of the radiation field in the Turbine Plant during a significant power run. The initial power level survey had an average radiation level of 0.02 mr/hr. this survey showed and average radiation level of 0.03, which was considered background level. this radiation level was far below the maximum allowable level of 2 mr/hyr. No Neutrons were detected.

The purpose of the test was to determine the ability of the Control Air System to provide the necessary quantity and quality of clean, dry air to keep the rod drive mechanism stator and position indicator housings at about 3 PSIG in order to avoid low stator resistances resulting from condensation during plant cooldown. The Control Air System is capable of providing the quality of air specified in AEC letter SBO:JWF:100 dated November 17, 1958 of less than 44 grains of moisture per lb. of air in the control air line nearest the reactor chamber.

The purpose of the test was to determine the operating conditions of the rod drive mechanisms so that operating personnel may be informed concerning malfunctioning mechanisms. The results the this test favorably agree with previous results. The operating characteristics of the rod drive mechanisms checked in this test have not changed appreciably.

SNAP II is the designation for a 3 KW nuclear auxiliary power unit to be used in a satellite vehicle. The SNAP II system consists of a reactor heat source, a mercury Rankine engine and an alternator. A two stage, full admission, axial flow turbine was chose for the APU application. Design details and test results are presented in this report. This work was performed under a subcontract to to Atomics International as part of the Atomic Energy Commission Contract No. AT(11-1)-GEN-8.