The corrosion rates of low-titanium zirconium alloys increased with titanmum content when exposed to water at 290 deg C or to 1 atm oxygen at 290, 350, 400, and 500 deg C. The scaling rate reached a maxmmum (approximately 3000 at 500 deg C and then decreased with increasing titanium content. Under the same conditions, pure zirconium and tmtanium had much lower weight gains, 10 and 4 mg/ dm/sup 2/ respectively. In oxygen at 500 deg C, the oxidation rate law was initially cubic or parabolic for alloys containing 3.75, 15.0, and 50.0 at.% Ti, and then changed to approximately a linear one. The transition times were 17, 7, and 54 min for the in the rate law and the rise in EMF and resistance appeared to be independent variables. The electrical changes were attributed to changes in defect structure, and the rate law ansitions were attributed to structural channges. The reilts provided an explanation for the maximum oxidation ite at 15 at.% Ti and for the differences in the influence of dditives on the corrosion rates of zirconium and titanium in high temperature water. Thc EMIF of the corrosion cell consisting of STAalloy /oxide! O/sup 2/! was a function …

BS>The approach taken in measurements on the AGS experimental magnets is discussed, and results of various measurements are examined. Application of information to calibration of beam lenses is also mentioned. Graphs of several magnet properties are included. (D.C.W.)

Pressure-drop measurements were made across a mockup of a Hallam prototype fuel element in a test section installed in the Hallam Hydraulic Loop. The flow channel was identical to an SRE fuel channel and included simulated upper and lower plenums. The fuel element mockup was equipped with a Hallam-type variable orifice at the channel exit and a fixed orifice in the strainer basket at the bottom of the element. Tests were performed to determine the optimum size for the fixed orifice and the temperature adjustment capability of the variable orifice using this optimum fixed orifice. To obtain the predicted 4.1 lb/sec sodium coolant requirement at a core pressure drop of 1.85 psi, a 3/4 in. fixed orifice was determined to be the optimum. With this fixed orifice size the variable orifice will be approximately 1 in. withdrawn during full-power operation. Adjusting the orifice over its entire range of 3 in. from fully inserted to fully withdrawn covers a temperature range from 875 to 1040 deg F which is approximately plus or minus 80'F about the normal outlet temperature of 960 deg F. Curves are presented for use in determination of operating characteristics of the element with other fixed orifice sizes …

This report talks about Analytical and preliminary design studies of nuclear rocket propulsion systems. Volume VI. Compilation of hydrogen properties,

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.

Runs on the zirconia-coated graphite established that the ultimate strength of this material is 30 to 100% greater than previously reported. This greater strength was apparently obtained because the gas bearings eliminate all bending moments in the specimens and the radiant heating provides more even and measurable temperatures. The ultimate strength of one pyrolytic graphite specimen was found to be over 33,600 psi at 4000 deg F. The performance of the resistance-heated furnace was very satisfactory. The gas bearings were dismounted, cleaned, plated, and are being reinstalled. Some limit switches were added to the load frame to provide protection from overtravel. (auth)

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Research areas include: reactor materials and components; alloy fuels; fission-gas release from refractory fuels; fuel-element development; gas-pressure bonding of ceramic, cermet, and dispersion fuel elements; development of uranium carbide; physical research; radioisotope and radiation applications; void- distribution and heattransfer studies; development of uranium mononitride; materials development and evaluation; coated-particle fuel materials; problems associated with recovery of spent fuel elements; pebble-bed reactor materials; development of fabrication processes for cold bonding of Zircaloy-2 to type 410 stninless steel; development and evaluation of fuel elements for MGCR; development studies for SM-2; gas-cooled reactor program; corrosion of thorium and uranium under storage conditions; and gas-pressure bonding of berylliumclad fuel elements. (For preceding period see BMI-1480.) (B.O.G.)

The condenser-discharge method of conducting molten metal- water reactions at high temperatures was refined. Two methods to measure energy input to specimen wires and, therefore, to compute initial metal temperatures were developed. Calculated metal temperatures were estimated to be accurate to within 100 deg C. Two reaction cells were designed, one for operation at atmospheric pressure with water at room temperature, and the other for operation at high pressure and with water at elevated temperature. Means were developed to determine the surface area of metal exposed to reaction and to determine the total extent of reaction. Pressure transducers were used to record the rate of reactions. The zirconium- water reaction was studied with initial metal temperatures from 1100 to 4000 deg C with 30 and 60-mil wires in room-temperature water. Initial pressures in these runs were the vapor pressures of water at room temperature (20-30 mm). Runs were made with 60-mil wires in water heated to 200 deg C (225 psi). Results in room-temperature water indicated that the reaction became explosive at an initial metal temperature of 2600 deg C. Below this temperature, 20% or less reaction occurred. At higher water temperatures, reaction ranged from 40 to 70%. Runs in …

Progress is reported on development studies on reactor materials and components, fuels, fuel elements, gaspressure bonding of ceramic fuel elements, uranium carbides, growth of UO/sub 2/ single crystals, radioisotope and radiation applications, materials evaluations, coated-particle fuel materials, corrosion in fiuoride-volatility processes, cold-bonding processes, radiation effects on MGCR fuel materials, radiation effects on SM-2 fuels, gas-cooled reactor program, and gas-pressure bonding of beryllium-clad fuel elements. (B.O.G.)

White Oak Lake, Oak Ridge, Tennessee, received lowlevel radioactive wastes from Oak Ridge National Laboratory for 12 years prior to draining in 1955. Studies on the insects inhabiting the vegetation on White Oak Lake bed revealed 401 species present during 1956 and 1957. Most numerous were members of the insect Orders Hymenoptera, Diptera, and Coleoptera. In the summer of 1956, the first summer following draining of the lake, there were relatively fewer species of insects represented by large numbers of individuals. In 1957, there were relatively more species of insects but fewer individuals were present. By the end of the summer of 1957, only two years after the lake was drained, the vegetation supported a rich and varied insect fauna. (C.H.)

A combination of chemical and electrolytic polishing was successful in the metallographic preparation of Zr--1% Cu and Zr--1.6% Cu alloys. Chemical polishing produced flat surfaces that were suitable for examination with polarized light but were not suitable for examination with bright-field illumination. Electrolytic polishing applied to ground or mechanically polished specimens produced surfaces that were well etched but often were pitted heavily. A chemical polish followed by a short electrolytic polish produced microstructures suitable for examination with both bright-field and polarized light at high or low magnifications. (auth)

This report includes a summary of materials research and engineering of the aircraft nuclear propulsion project.