This report presents an analysis of rupture experience at C Reactor over the past two years. The purpose of the study was to provide a basis for revising, if necessary, the current metal performance level multipliers for C-II-N and C-II-E material.

C Reactor horizontal control rods were originally designed to have 32 feet of poison, made of 64 six inch ``cans`` each consisting of two concentric cylinders sealed at each end and the annular space between them filled with boron carbide powder. It was discovered before startup that under irradiation the neutron, alpha reaction in the boron could cause a pressure buildup and rupture of the sealed section. As an expediency cylinders wrapped with 72 miles thick cadmium metal were substituted for the boron ``cans`` and the pressure buildup problem was eliminated. However, since for a unit volume, natural cadmium contains fewer high cross-section nuclei than natural boron, the lifetime of one of these cadmium rods in Hanford flux levels is limited. Five of the original 15 cadmium rods were replaced in 1957 with boron rods of improved design. The primary purpose of this document is to present the results of a study to evaluate the extent of burnout in the remaining ten cadmium rods and their present rate of burnout so that replacement can be scheduled before these rods start losing significant reactivity poisoning effectiveness.

Solidification of intermediate-activity wastes is a major goal of the CPD Waste Management Program. Plans are to reduce the wastes, by evaporation, to salt cakes in existing tanks, thereby insuring safe, long-term storage of contained fission products regardless.of tank integrity. Initiation of these plans at an early date is necessary to offset the expected increase in tank failures and to provide space for future wastes. Major decisions of the program relate to selection of the evaporative method to be employed. The requirements of in-tank solidification were therefore reviewed to determine if the choice of evaporative systems can be made at this time. The relative potential of Bentube evaporation and submerged combustion for meeting these requirements were analyzed on the basis of available information, including actual performance of the Bentube facility at the Savannah River Plant (SRP).

This report discusses three natural uranium, X-8001 aluminum clad, I&E Hanford production fuel elements, which were irradiated in 3363-D as part of PT-IP-262-A, were selected for detailed examination in the Radiometallurgy Laboratory. The three pieces were from the same tube and each had lost about 15 grams of cladding during irradiation. Examination was requested to determine the extent of the corrosion and whether the attack was uniform or localized. Also, measurement of the uranium fuel was requested to reveal any change that occurred during irradiation. Corrosion was general rather than localized and occurred over approximately three-fourths of the surface. In each element. about one-fourth of the surface on one side was virtually unattacked and vas probably the area that lay between the ribs of the process tube during irradiation. In one element localized attack occurred beside two of the bumpers. External aluminum cladding thicknesses ranged from 0.020 to 0.043 inch. About 0.005 inch of the spire surface vas removed by corrosion. Both internal and external dimensions of the uranium increased. The average external diameter was 0.010 inch larger and the average internal diameter vas 0.011 inch larger than the average preirradiation diameter measurements. The growth vas not uniform as ellipticity …

Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.

A previous study described proposed facilities at B-Plant which integrate future fission product and waste calcination activities. However, in the reactivation of B-Plant in accordance with this study, heavy expenditures, above budgeted funds, would be required at an early date for Phase 1 process changes coupled with general rehabilitation work and facilities for updating of radiological control. Since waste calcination activities in B-Plant are not scheduled until Fiscal Year 1966, the expense of B-Plant rehabilitation items would be borne solely by the Fission Product Program. This report provides the Title I design of Phase 1 fission product facilities at B-Plant which can be provided vith minimum capital expenditures. The facility described in this report accomplishes the overall processing objectives of the facility, namely the recovery and storage of crude strontium-90 and rare-earth concentrates, although certain B-Plant improvements are deferred to later phases of the Fission Product and Waste Calcination Programs.

A reference design of a large high power density core has been established representing the available technology as of August, 1960. Reference core performance and cost should improve considerably after incorporation of improvements now under study.

"Evacuated electrical oscillating cavities frequently are found to exhibit a strong loading due to electron (or iron) multiplications, the so-called multipactor effect. This effect tends to prevent the buildup of dee voltage in cyclotrons. In conventional cyclotrons driven from external oscillators having their own resonant tank circuits the difficulties are usually slight, but in cyclotrons using a simple dee system as the tank circuit difficulties are encountered in getting the oscillator to break into full oscillation."

"Some of the important results obtained in investigations of capacities of plumbing stacks in test systems at the National Bureau of Standards and elsewhere are discussed. Data are shown from experiments on the flow of water and air in such systems, and analyses of certain flow phenomena are given. Methods are shown for applying the results of research in hydraulics and pneumatics to the preparation of loading tables (for drainage and vent stacks) suitable for use in plumbing codes" (p. 1).

From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."

Work has been progressing on the development of an extrusion process for I&E tubing. The ultimate object of this development project is to compare the extrusion process from a cost standpoint with, the presently used rolling-drilling process. Various experiments have been performed to determine the optimum billet I.D., the proper follower block technique, the proper tooling parameters for the process, and the proper metallurgical structure of the material for optimum results. This extrusion combines many of the past results as a further determination and refinement of the extrusion process to be used in the final semi-production optimization extrusion. The object of this extrusion was to evaluate the resulted of previous extrusion experiments to determine final process conditions prior to an optimization extrusion.

The spin of neodymium-141 was measured by the method of atomic beams and found to be 3/2. A lower limit placed on the hyperfine separation of the states with total angular momentum [formula] by second-order perturbation theory shows [formula]. A prerequisite for the determination of the nuclear spin from hyperfine-structure measurements is the knowledge of the electronic structure. The ground-state configuration of neodymium is known and the value is used throughout this work.

This study is part of an evaluation of the P&W NJ- 18A powerplant. The work presented here specifically estimates the pressure drop between the compressor discharge and the turbine inlet. Analysis was asked for two operating conditions. One was for sea level sprint at a Mach no. of 0.9, while the other was for a Mach no. of 0.9 at 35000 ft.

Studies are being made on the recovery of thorium (and uranium) from granitic rock, since this source represents a very large potential thorium reserve for the nuclear power industry. In preliminary leaching studies on 16 granite samples (containing 8-95 ppm thorium and 1.5-16 ppm uranium), maximum recoveries of thorium and uranium ranged 30-85% and 15-65% respectively, and sulfuric acid consumption was high (30-120 lbs H2SO4 per ton of granite). A relatively high acidity was needed to obtain rapid and efficient dissolution of the soluble thorium fraction. The cost of treating granite was estimated at $3.50-5.20 per ton, variations within this range being dependent primarily on differences in acid consumption for different granites. Estimated costs per pound of thorium plus uranium recovered ranged $30-500.