None

This report covers work done by the Physical Chemistry Group and the Pile Engineering Groups. Subjects covered are as follows: corrosion laboratory testing details; pile borescopic inspections; slug deformation details; Van Stone flange corrosion details; corrosion rate at elevated temperature; added control ink facility; borescope equipment and repair; water recirculation cooling tests; pile expansion; carbon dioxide experiment; special graphite measurements; graphite core sample; vertical thimble temperature; beta experiment; x-ray diffraction studies; thermal annealing; empty process tube temperatures; oxidation of graphite; thermal annealing -- interferometer measurements.

None

Side rupture data experienced to date for I and E fuel elements give rupture rate curves which do not differ significantly from those predicted on the basis of solid fuel elements experience.

None

This report addresses the control design review of P&W quarterly for July to September 1960.

This document consists of length and annealing data sheets.

The objective of this production tests is to irradiate N Reactor prototype and candidate fuel components and alternate products at simulated N-Reactor pressure and temperature conditions in KER Loops 1, 2, 3, and 4.

The FFTF Radioactive Waste System provides the equipment and facilities required for the routine collection, transfer, storage, and disposal of radioactive liquid and solid wastes. Radioactive solid wastes and radioactive liquid wastes not normally piped t o the Radioactive Waste System Receiving tanks, are packaged inappropriate containers by the systems generating the waste for collection and disposal by the Radioactive Waste System. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

The Heating and Ventilation System provides the atmospheric conditions in FFTF as required to assure that plant objectives can be met in a safe and practical manner. Included are functions and design requirements, a physical description of the system, safety considerations, principles of operation, and maintenance principles.

This document presents details about the status of irradiations performed by Fuel and Target Irradiation Technology for BNW as of November 30, 1969.

In this laboratory we have studied the macromolecular changes accompanying release of contact inhibition by using a method by means of which a large fraction of cells in a confluent monolayer are released from contact inhibition of growth and division. This is accomplished without chemical treatment of the cells, without change of medium and in such a way that most cells are provided with free growth area. The procedure involves growing the cells to confluence on surfaces uniformly covered with glass beads 200 {microns} in diameter. When confluence has been attained, contact inhibition ma be released by discarding the beads leaving behind numerous spaces, throughout the culture. Removal of the beads dislodges few if any of the cells. After release of contact inhibition by removing the beads, the cultures double in cell number following the first round of DNA replications, and continue to grow until they are again contact inhibited. Cell types used have included several cell lines and strains including both primary cell cultures of neonatal rat heart cells and established 3T3 and 3T6 mouse fibroblast cell lines.

An experiment designed primarily to define the problems associated with sampling the two-phase flow in a pipeline of geothermal brine is described. Analyses reported for 26 samples include chemical composition, oxidation potential, pH, density, and total solids. Changes in brine composition as the well operated during a four-week period are evaluated. The apparatus and techniques used for sampling are described and evaluated. (auth)

Eight mullite bodies of varied compositions and microstructures have been prepared and are being characterized. These compositions will be submersed in molten silicon to study the impurity and surface effects. These various mullite materials will be analyzed for use as substrates for Honeywell Contract No. 954356, silicon on ceramic program and for use as a container of molten silicon. Low cost processing methods are being developed and evaluated for manufacturing large mullite sheets and mullite containers. At present, a state-of-the-art roll compaction process has shown promising initial results for substrates. However, these 0.5mm x 10cm x 1m are extremely fragile. Slip casting or iso pressing are anticipated for containers.

An elaboration of the ISABELLE concept as the model for a high energy, high luminosity proton-proton facility is given. Its place in the total high energy physics program is discussed. Certain features of the ISABELLE design which have not been consolidated, in particular injection and modes of beam operation, are considered. A new scheme is reviewed, one which could provide quick beam turn-on after construction, one in which there is a high probability of reaching and perhaps even exceeding the design objectives, one which should provide comparatively more flexible and reliable operation for physics, and finally one whose presence opens up a window to a much higher energy region. The new system involves the use of a physically separate current accumulator, allowing, therefore, the optimal utilization of the superconducting structures. The fact that an obvious addition to the complex will permit pp collisions in the 4 TeV center-of-mass energy region, which corresponds to an equivalent lab energy of approximately 10/sup 16/ eV, i.e., cosmic ray energies, prompts the added structure to be referred to as the COSMICTRON. The facility operated in the ''new'' manner proposed is considered to be ''the best ISABELLE that can be built.''

Experimental results are presented on properties of major practical importance in the utilization of manganese-substituted ferrotitanium alloys as hydrogen storage media. Consideration is given to (1) pressure-composition-temperature characteristics, (2) particle attrition properties, (3) effects of long-term cycling on alloy stability, (4) ease of activation and reactivation, and (5) effects of contaminants on alloy activity. The performance of ternary alloys is compared with that of titanium iron as is the development of an optimum ternary alloy for use with a particular peak shaving operation, i.e., the regenerative H2-Cl system.

The purpose of this investigation was to determine the corrosion behavior of a high strength steel (ASTM A416-74 grade 270), typical of those used as tensioning tendons in prestressed concrete pressure vessels, in several corrosive environments and to demonstrate the protection afforded by coating the steel with either of two commercial petroleum-base greases or Portland Cement grout. In addition, the few reported incidents of prestressing steel failures in concrete pressure vessels used for containment of nuclear reactors are reviewed. The susceptibility of the steel to stress corrosion cracking and hydrogen embrittlement and its general corrosion rate were determined in several salt solutions. Wires coated with the greases and grout were soaked for long periods in the same solutions and changes in their mechanical properties were subsequently determined. All three coatings appeared to give essentially complete protection but small flaws in the grease coatings were detrimental; flaws or cracks less than 1 mm wide in the grout were without effect.

Most detailed fusion target design is done by numerical simulation using large computers. Although numerical simulation is briefly discussed, this lecture deals primarily with the way in which basic physical arguments, driver technology considerations and economical power production requirements are used to guide and augment the simulations. Physics topics discussed include target energetics, preheat, stability and symmetry. A specific design example is discussed.

None

This report describes the Collider Vacuum Requirements.

Progress since the last symposium on the study of H/sup -/ formation by charge transfer in alkaline-earth vapors is reported. High yields are obtained at low energies, in agreement with theoretical predictions.

None

Cascade is an inertial fusion reactor that uses circulating Li/sub 2/O pellets as a coolant and tritium breeding medium. The pellets flow through a horizontal rotating vessel, and they are held against the vessel wall by centrifugal force. Three wall designs were considered: a steel shell and a SiC shell prestressed by Al or steel cables. The nuclear heating, tritium breeding ration, afterheat, inhalation biological hazard potential, and shallow land burial index were calculated for each configuration. Tritium breeding is more than adequate (1.35). Spray cooling of the wall exterior will be required during operation, but thermal radiation heat removal will be sufficient after shutdown. Allowable release fractions during an accident are higher than in comparable designs. Disposal of activated components by shallow land burial is feasible. Hands-on maintenance of the SiC/Al wall will be possible if it is moved away from the reflector.

The need is discussed of a special purpose detector for the measurement of elastic scattering at the SSC. The detector would cover as small a solid angle as is practical. Two techniques are described briefly to measure total cross sections at hadron storage rings. The direct method is to measure the interaction rate in an IR of known luminosity - a method that gets more difficult increasing energy. A second method is to use the optical theorem. 6 refs., 1 fig. (LEW)