The extraction of uranium, magnesium, cerium, zirconium, and niobium from bismuth with a molten mixture of sodium fluoride and zirconium fluoride was demonstrated. Comparative rates of extraction were obtained. The effects of high concentrations of magnesium and of hydrogen fluoride sparging on the extraction process were investigated. Tracer studies demonstrated that exchange occurs between zirconium dissolved in the bismuth and zirconium in the fused salt. The applicability of the fused fluoride extraction step to the processing of the Liquid Metal Fuel Reactor'' solution fuel is discussed. (auth)

In compliance with a request from Coolant Testing Operation, the Reactor Engineering Operation has made a study to determine the maximum operating pressure limits for the pertinent Zircaloy-2 process tubes. Since these tubes shall be used for testing NPR fuel elements, it is considered desirable that KER Loops 2 and 3 permit operation at temperatures of around 300{degrees}C while the NPR prototype facility permit operation at about 316{degrees}C in a manner such that there is minimum hazard to the KE-Reactor and to personnel.

Zirflex cladding waste is to be neutralized to pH 10 before transfer to waste storage tanks. This treatment causes the precipitation of zirconium oxide or hydroxide, which may lead to flow difficulties during transfer. The purpose of this investigation was to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selectin of satisfactory transfer equipment and storage conditions.

An investigation was made to determine the physical properties and flow characteristics of the neutralized slurry to assist in the selection of satisfactory transfer equipment and storage conditions. The neutralized Zirflex waste slurry contalns 20 vol.% rapidly settling solids. It can be transferred easily if the flow is in the turbulent condition, but agitation is needed during temporary storage. Pipe lines should be flushed with water after transfer of the waste slurry. (W.L.H.)

The purpose of the Analytical Laboratory Manual is to assemble the basic procedures to be used for the analyses of materials employed within the Fuels Preparation Department. The methods appear in detailed steps suitable for laboratory use. This document replaces the "Essential Material Analytical Manual, " HW-25375 and "Metal Preparation Analytical Manual," HW-30862.

An experiment was conducted in the SRE to measure temperatures and neutron flux levels in and near a boron-containing simulated control rod. The data are being used to check analytical methods developed for prediction of control rod heat generation rates and maximum temperatures in this type of control rod in the Hallam Nuclear Power Facility. The maximum observed temperatures with a reactor power level of 20 Mw were 1363 deg F for a boron-- nickel alloy ring having a 0.105-in. radial clearance with the thimble and 1100 deg F for a boron -nickel alloy ring having a 0.020-in. radial clearance. The maximum temperature difference between the coolant and the control rod was 473 deg F. It is concluded that the expected greater heat generation rates in the Hallam reactor would prohibit the use of boron-containing absorber materials in a combined a him-safety rod. (auth)

The radiation hazards associated with recycled nuclear reactor fuels will greatly complicate the handling and refabrication of these fuels. This problem is most serious with U/sup 233/ and Pu fuels where the presence of U/sup 232/ and thue heavier isotopes of Pu contribute energetic alpha, gamma, and neutron radiations at levels many times that from isotopically pure U/sup 233/ and Pu/sup 239/. Present knowledge of the radiation hazards associated with recycled fuel and the additional data needed to make a thorough evaluation of these hazards are summarized. (auth)

The radiation hazards associated with recycled nuclear reactor fuels will greatly complicate the handling and refabrication of these fuels. This problem is most serious with U-233 and plutonium fuels where the presence of U-232 and the heavier isotopes of plutonium contribute energetic alpha, gamma, and neutron radiations at levels many times that from isotopically pure U-233 and Pu-239. This report summarizes present knowledge of the radiation hazards associated with recycled fuel and the additional data needed to make a thorough evaluation of these hazards.

Some of the apparatus and techniques being used in order to simulate environmental conditions to test supersonic vehicle components are presented. Some specific tests along with plans for future tests are discussed. (W.L.H.)

The limitations of previously performed or suggested electrodynamic cutoff experiments are reviewed, and an electron-electron scattering experiment to be performed with storage rings to investigate further the limits of the validity of quantum electrodynamics is described. The foreseen experimental problems are discussed, and the results of the associated calculations are given. The parameters and status of the equipment are summarized. (D.C.W.)

None

The detonation of a contained or partially contained nuclear explosion is accompanied by the deposition of a large fraction of the energy in the form of high-temperature, high-pressure regions. The nature of the surrounding medium, the time-temperature history, and the time of cavity collapse or venting determine the extent to which undesirable nuclides such as Sr/sup 90/ and Cs/sup 137/ will appear outside a fused insoluble matrix and be available to ground water or to the atmosphere. The movement of these undesirable radioactivities relative to the ground water movement can be predicted on the basis of measured K/ sub D/'s (distribution coefficients) for the radioactivities in the medium. The induced radioactivities are a 20 to 25% contribution to the fission product radioactivity at times the order of one day, a 1% contribution at about 1 week, decreasing to 0. 1% at about 45 days, increasing to about 2% because of the Co/ sup 60/ for a period of 3 to 15 years. (auth)

A detailed description of fabrication methods used for TREAT fuel elements is presented. Photographs of equipment and assemblies are included along with tables and flowsheets. (J.R.D.)

A theoretical method of determining the time, temperature, and pressure required for pressure bonding was proposed and then evaluated experimentally. The analysis considered only the mechanical deformation of the bonding surfaces induced by the external pressure. It was postulated that such deformations obey the power law for steady creep. The applicaiion of the law to the closure of thick-walled aluminum cylinders under gas pressure was investigated. The behavior was compared with ihat predicted from creep data obtained from short- time torsion creep tests. Only fair agreement was establtshed. The creep law was then applied to the calculation of the closure of voids at the interface between bonding surfaces. It was assumed that the voids exist as isolated spherical or cylindrical holes. The law failed to predict the total closure which occurred. Apparently, the creep law does not hold in the almost microscopic domain of the interfacial voids, although the disagreement may have been due to the oversimplification of the geometric representation. Resolution of the ambiguities probably will be attained only when sufficient experimental data to establish an empirical relationship of closure with bonding conditions are available. (auth) l8092 To develop fatigue-design information for the ORNL reactor programs, a study was …

Abstract: "The cross section for the Be-9(n, t')Li-7*-->Li-7 + Y(0.477 Mev) reaction has been measured in the vicinity of 14 Mev by detecting the gamma-rays at scattering angles from 30 to 150 degrees. A time-of-flight technique was used to distinguish the gamma-rays from the high neutron background. The cross section drops from 20 mb at 13.6 Mev to 10 mb at 14.1 Mev and then rises to 30 mb at 14.7 Mev."

The cross section for the Be/sup 9/(n,t')Li/sup 7*/ -- Li/sup 7/ + gamma (0.477 Mev) reaction was measured in the vicixity of 14 Mev by detecting the gamma rays at scattering angles from 30 to 150 degrees. A time-of-flight technique was used to distinguish the gamma rays from the high neutron background. The cross section drops from 20 mb at 13.6 Mev to 10 mb at 14.1 Mev and then rises to 30 mb at 14.7 Mev. (auth)

The assumptions used to derive the total neutron yield per detected alpha particle (from the D-T reaction) which were derived in an earlier report are reexamined in the light of additional experimental information. It is concluded that for an alpha counter at 90 deg to the incident beam direction the assumptions introduce practically no difficulties. Therefore, for precise monitoring in the absence of certain target information it is recommended that this configuration be used. For counters at angles different from 90 deg , nonuniformity of target loading contributes the most serious error to the computed yield. (auth)

A solution to the problem of stresses in a pressure vessel with an ellipsoidal head has long been sought by pressure vessel designers. To meet this need the codes described in this report were written The codes are based on a finite-difference approximation to the LoveMeissner equations which are the basis of the bending theory of thin shells. (auth)

Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.

Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulfate media. Relative standard deviations of 0.43% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies. (auth)

In the reaction of silicon halides with graphite to form silicon carbide, thermodynamic conditions were determined for the formation of SiC, free of elemental silicon. The use of these conditions was designed to limit the rate of coating formation by the rate of diffusion of carbon through the coating, and render the operation independent of the vapor-flow factors which normally limit the uniformity of vapor-deposited coatings. Although a wide range of pressure- temperaturecomposition conditions was explored, it was not possible to duplicate the success previously obtained in applying the method to NbC, TaC, TiC, and ZrC coatings. Fundamental differences in the characteristics of the carbides which may account for the difference in behavior are the lack of a range of homogeneity in beta SiC crystal structure, and the fact that SiC undergoes a modification from the cubic beta to a hexagonal form at l900 to 2000 deg C.There remains the prospect of forming a uniform SiC ''sponge'' by the present process which can be subsequently impregnated with metallic silicon to form an oxidation-resistant cpating. (auth) l6200 Preliminary results were obtained on the value that commercially pure Pu (95% Pu/sub 235/ and 5% Pu/subp 240/) has when used as nuclear fuel. …

This document is the third in a series of progress report that records investigations of graphite bodies. Along with the report, two appendices are given to describe the different graphite bodies: "Synthetic Binders for Carbon and Graphite" and "High Temperature Physical Properties of Molded Graphites".

The Facilities Engineering Operation of the Chemical Processing Department prepared a process study scope design of a large thermal diffusion plant for xenon isotope separation. This scoping was done perforce on the basis of calculations made from exclusively theoretical considerations because actual design data are not available. The designers are of the opinion, however, that, such a basis is not adequate to justify the construction of the plant and have, therefore, requested that an appropriate supporting research and development program be carried out. This report presents an experimental plan for obtaining the data required. Anticipated results from the proposed experiments as outlined below, are expected to be useful for determining the correlation of thermal diffusion column theory with practice for this particular system of xenon isotopes. An interpretation of the data will permit the determination of the sensitivity of the column parameters to the change in operational and design variables over which the designer and operator have control. Basic observations made on the behavior of xenon may, in addition, be of general scientific and technological interest. Included in the report are estimates of the kind and quantity of data to be obtained, the analytical services required, and the total analytical …

This paper presents a scope design of two coaxial type thermal diffusion columns. These experimental columns are proposed to meet the requirements of the research and development program given in Part 2 of this report series. They would rearrange the isotopes of xenon from the Case II product of the Purex Gas Separations Facility to yield a product with a composite neutron absorption cross section of less than one barn. The theoretical basis for the design is given in Part 1. The auxiliary equipment necessary for the operation and control of the columns is described in Part 4. Major components of the columns and their functions are described in this part, The proposals for the materials of construction and the heating systems are not conclusive. Several possibilities for these requirements, however, are included. The design of two experimental thermal diffusion columns is given to meet the needs of a proposed research and development program for rearranging the isotopes of xenon. The proposed columns are six meters in length and have a maximum diameter of about five inches. They could be built at Hanford for an estimated cost of $10,000.