Reproducibly high density UC-PuC pellets containing minor amounts of (U,Pu)/sub 2/C/sub 3/ were made with nickel sintering aid. Average densities of 95% and maximum densities of 96.6% of theoretical were obtained. High density, singlephase UC-PuC pellets were made by sintering at high temperatures. Densities of 94% of theoretical appear to be attainable. Improved identification of microstructural constituents was made by means of metallography, x-ray diffraction, and microprobe analysis. Development of specialized chemical analysis techniques continued. The post-irradiation examination of the UC specimens was completed. Mass spectrometer analysis showed that 0.4% of the fission gases was released. Metallographic examination of the UC did not reveal any channges in structure. Metallographic examination of the metal specimen parts that were in contact with UC was completed. No evidence for interaction with niobium and slight evidence for interaction with stainless steel was found. The latter was not deleterious. Perturbation factors were calculated for the UC- PuC experiments. Negotiations continued, in order to select the most suitable test reactor. (auth)

From abstract: "Electrical measurements have been made on CaB6, SrB6, BaB6, YB2, YB4, YB6, and YB12 for the purpose of testing models of the electronic structure of the boron atoms in the four boride types represented. The compounds CaB6, SrB6, and BaB6 were found to be semiconductors. The Hall coefficients of YB4 was also measured, but could not be interpreted because the free electron theory does not provide a theoretical value for comparison with experiment. The results are in agreement with the models proposed."

A large number of irradiation tests have been conducted with UO{sub 2} fuel elements to characterize the behavior of Zircaloy cladding when cooling water is allowed to penetrate the cladding to the fuel core. The test element, is designed so that cooling water will be in contact with the surface of the UO{sub 2} fuel core during irradiation. The irradiation behavior of the UO{sub 2} will be compared to the behavior of similarly irradiated, non-defected UO{sub 2} fuel-elements. Several characteristics are of particular interest: (1) Previous investigations have shown that fission fragments formed in UO{sub 2} fuel cores tend to migrate from their point of formation. The fission fragment distribution in this element will be compared with that observed in other irradiated UO{sub 2} fuel cores. (2) This test will provide a direct measure of fission products released from UO{sub 2} during irradiation. (3) Sintered UO{sub 2} is quite resistant to erosion and is, in general, chemically stable in a water environment. This test will provide data concerning the dissolution rate of UO{sub 2} in water during irradiation. (4) Since the coolant will be in direct contact with the fuel, the average temperature of the fuel will be comparatively low. …

A reinforced-concrete steel-plate-lined vault and steel vault door were exposed to a nuclear detonation (shot Priscilla, about 37 kt, balloon suspended, at 700 ft) at the predicted 75-psi peak incident pressure level (1150 ft from Ground Zero). The vault was designed by the ultimate-strength theory to utilize the additional strain energy available in the elastoplastic and plastic ranges. Flexural and thrust capacities were determined, and shear capacity was computed. It was established that above-ground structures can be designed and constructed to survive the pressure levels experienced by this structure. The vault and door provided adequate blast and thermal protection for normal usage, and the structure was adequate to resist overturning and excessive sliding under conditions of the test.

From introduction: "This brief paper deals with the subject of radial temperature differences for heat transfer to fluids flowing through concentric annuli under the following conditions and assumptions: a. constant heat flux; b. fully-established turbulent flow; c. heat transfer through inner wall only; d. physical properties independent of temperature."

A survey of the water requirements is presented for a hypothetical plant to process all the fuel from a 15,000Mwe nuclear economy. For each processing plant, specific requirements must be based on a detailed water survey which includes water quality, process requirements, and in-plant conservation plans. These considerations are discussed and the quantitative requirements are listed. (J.R.D.)