None

Twenty charges each of low hydrogen dingot fuel and standard ingot fuel elements were irradiated at DR-reactor. Distortion data from 22 tubes are analyzed in this document. The dingot fuel elements are prone to greater tube filling capacity (TFC) and greater daimeter growths at both center and ends of the fuel elements (the growths at center are larger than at ends). The difference between average warp values for the two types of fuel elements is not statistically significant, indicating that the greater TFC values shown by th dingot fuel elements are due to their larger diameter growths at the slug center rather than to larger warp values.

Modifications to the 100-K water plant will be made, under Project CG-775, to increase total process water flow rates to 175,000 gpm or greater. Included in the modifications will be the installation of new pump impellers for the primary and secondary process water pumps located in the 190-K Buildings.

In the production of plutonium in a reactor, plutonium-238, 240, and 241 are formed as well as Pu{sup 239}. It is well known that the specific alpha activity of the plutonium varies as the percentages of these isotopes are changed. Kinderman, et al have worked out the relationship between isotopic content and MWD/ton exposure. Their findings are reported in this document.

The objective of this test is to permit irradiation of projection fuel elements to evaluate jacket corrosion in areas of projection, to examine the effect of well-aligned fuel elements on hot-spot incidence, and to evaluate problems associated with projection slug usage in ribbed process tubes.

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.

Report presenting an investigation of three cone-cylinder bodies to obtain boundary-layer-transition data at very low ratios of wall to local stream temperature. Surface finishes at several levels of roughness height were tested. Results regarding the smooth body and rough bodies are provided.

In a laboratory study of the factors involved in the influence of induction vacuum melting on 55ni-20cr-15co-4mo-3ti-3al heat resistant alloy, it was found that the major factor was the type of ceramic used as the crucible. The study concluded that trace amounts of boron or zirconium derived from reaction of the melt with the crucible refactories improved creep-rupture properties at 1,600 degrees F. Boron was most effective and, in addition, markedly improved hot-workability.

Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.

Memorandum presenting an investigation of the performance of a five-stage transonic research compressor with distorted inlet flow. Both overall performance and individual blade-row performance results over a range of compressor speeds and equivalent weight flows were obtained with three circumferential inlet flow-distortion patterns covering annular extents of 60, 120, and 180 degrees. Results regarding compressor-inlet conditions and overall performance and individual blade-row performance are provided.

Report presenting the results from 20 hours of service operational flying of an instrumented North American F-100A fighter airplane. Results regarding the altitude and Mach number, normal-load factor, airplane attitude, use of controls, rolling motions, pitching motions, yawing motions, vertical-tail loads, horizontal-tail loads, and a comparison with other airplanes are provided.

From Introduction: "This report presents data from measurements of the flow in a single-stage research compressor, which supports the model of reference 1. A calculated shock technique similar to that of reference 1 is incorporated with these experimental results. Another approach for estimating passage shock loss given a flow rate and blade geometry was reported in reference 2."

Memorandum presenting an investigation of a double-ramp cascade inlet at Mach number 3.05 in order to determine the penalties associated with decreasing the length of inlets by means of cascades. Total-pressure recovery and profile distortion of the cascade inlet were compared with a similar single-passage inlet that captured the same mass flow.

"A supplementary investigation has been conducted in the Langley 20-foot free-spinning tunnel on a l/24-scale model of the Grumman F11F-1 airplane to determine the spin and recovery characteristics with alternate nose configurations, the production version and the elongated APS-67 version, with and without empty and full wing tanks. When spins were obtained with either alternate nose configuration, they were oscillatory and recovery characteristics were considered unsatisfactory on the basis of the fact that very slow recoveries were indicated to be possible. The simultaneous extension of canards near the nose of the model with rudder reversal was effective in rapidly terminating the spin" (p. 1).

The General Electric Company is designing and building a 180,000 kilowatt nuclear power plant for the Commonwealth Edison Company at a site 47 miles southwest of Chicago. The construction permit was issued on May 4, 1956 but is subject to submittal to the Commission of a final hazards summary report and a finding by the Commission that the final design provides reasonable assurances that the health and safety of the public will not be endangered by operation of the reactor in accordance with the specified procedures.