The following report discusses a survey of seventy-seven interactions of K- mesons in flight in nuclear emulsion with seven decays in flight, and finding four inelastic scatterings.

Abstract: Experimentally measured promp-neutron decay constants for sub-critical systems are of considerable value as normalization data for calculations of prompt-neutron time constants. A method of measuring these decay constants with a pulsed neutron source, neutron detector and multi-channel time-delay analyzer has been developed and used on a number of fast-spectrum subcritical systems. An analysis of this method based on the one-energy group, one-delayed-neutron group reactor kinetic equations is presented and discussed. The curve of neutron flux versus time predicted by the kinetic equations is compared with the observed curve obtained with a 13.1-cm. diam. enriched-uranium sphere to indicate the application and limitations of the analysis.

From abstract: This bibliography consists of references pertaining to "Effects of Nuclear Radiation Upon Electronic and Electrical Components", and to "Electronic and Electrical Components for Critical Environments". References were compiled from the Classified and Unclassified report literature and the published literature. The following indexes and abstract journals were used: Weapons Data Index, AEC Card Catalog, Engineering Index (1950-55), and Office of Technical Services, Research Reports (1956-March '57).

Abstract: "The free energy (surface tension) of a liquid film can withstand atmospheric pressure across a maximum theoretical gap of 10-(-3) cm between solids if the liquid wets and bridges the sides of the gap continuously. The eutectic alloy of Ga, lm and Sm is used for this purpose. This alloy is molten at room temperature with surface tension > 500 dynes/cm, vapor pressure < 10-(-8) cm at 500 C and excellent wetting properties. This alloy can be utilized in valves, motion seals, flanged joints and for electrical contacts mounted in any position. Using ultrasonic soldering techniques without heat or flux this alloy is readily wetted on W, Mo, Ta, pyrex, quartz and certain ceramics. These materials will withstand the corrosive action of this alloy at at least 400 C. Some de-wetting has been observed with only the nonmetals at high temperatures. This de-wetting may be due to thermal decomposition of gallium oxide. Stainless steel is easily wetted, but is attacked at temperatures above 300 C. Copper and brass are attacked at room temperature."

The following report is based off of one of the author's lectures on the physics of plasma, or ionized gases, which was given on July 16, 1954.

From introduction: "The work described in this report was undertaken as part of an experimental study to determine the effectiveness of radiofrequency field in heating the ions of a hydrogen or deuterium plasma. The ultimate aim is to find a method of heating a deuterium plasma until an appreciable rate of nuclear reaction takes place."

Report discussing a study on casting techniques for the production of sound homogeneous extrusion blanks composed of aluminum-uranium alloys with 30 to 45 w/o uranium.

This report describes the design, construction, and application of an electrical analogue for solution of the steady state problem. Teledeltos paper (an electrically conductive paper) was used to construct this analogue, and although this and other sheet materials has been used for heat transfer analogues in several previous investigations, it is believed that the present work is unique in the application of Teledeltos paper to three dimensional problems of radial symmetry.

Second and third tests were conducted on an expansion bellows and Zircaloy-stainless steel transition joint assembly, duplicating that used in the core-pressure vessel assembly of the HRT. The assembly was exposed for 1140 hours in the second test and and 167 hours in the third to a solution containing 0.04m UO2SO4, 0.02m H2SO4, and 0.005m CuSO4 in a 100A dynamic corrosion loop under conditions simulating reactor startup, shutdown, and steady-state operation. Results indicated that the transition joint assembly as tested was mechanically sound and leak-tight. Pit-type corrosion continued on the expansion bellows where the upper retaining tangent contacts the bellows. Results are included of specimens exposed to the circulation solution during transition joint and bellows test.

A third test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel was completed. No additional mechanical deflections of the bellows were made, but 12 additional thermal cycles of the unit were carried out. . The joint and bellows functioned properly and were leak-tight. Corrosion of stainless steel in 0.04 m UO2SO4 containing equimolar beryllium sulfate was not greater at 10-15 fps and much less at 15-75 fps, than in HRT solution at 200 and 225 C. Increasing the beryllium sulfate concentration to 0.08 m increased corrosion at 225 C and resulted in an unstable solution at 300 C.

Data are presented for all toroid runs which circulated aqueous thorium oxide slurries between Aug, 1054, and October, 1956. In addition, a tabulation of the properties of numerous thoria preparations is presented.

The distillation method (Argonne Sampler) for the analysis of sodium oxide in NaK was used to calibrate a plug indicator. The description of the equipment, procedure, and experiences with the Argonne Samplers are presented in great detail to aid future users of this method. Although this method is not very precise, it has been thoroughly checked out and is recommended as a standard means for sampling and analysis for oxide in liquid metal systems. (auth)

The assembly of a second thorium oxide slurry corrosion test facility, loop BS, has been completed and 2010 hr of operation on slurry have been logged. This second test loop has proved satisfactory from an .operational standpoint. Corrosion data and operational observations are given for six thorium oxide slurry runs made at 300 C in 100A pump loops BS and CS. A new development model of the rotator for an in-pile slurry toroid is described.