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BS>Graphs were prepared as basic inelastic neutron data requested for neutron age calculations to be made using the compositions NaF-ZrF/sub 4/, BeF/ sub 2/, LiF-BeF/sub 2/, and ZrH. Nuclear temperature as a function of incident neutron energy was obtained for F, Be, and Zr. (W.D.M.)

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The primary objective of this report is the monthly distribution of experimental data as acquired during that period in the course of engineering studies. Much of the data is of preliminary nature and, therefore, reasonable care should be exercised in its application. You are invited to contact the individual authors for substantiation.

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A series of neutron multiplication measurements were made on assemblies of Pu metal (density 15.8 g/cm/sup 3/) in order that a safe melting crucible could be designed for charges of 10 kg or more. Suitable ingot shapes and masses that could be rolled into sheets were determined. Final charge limits must be determined by making in situ measurements with the actual production furnace when the furnace and crucible are compieted. (H.G.G.)

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This report provides workable summary of the technical information developed to date for the Mark VIA fuel element. The report provides a satisfactory compilation of information for use as a basis for designing facilities for a production process.

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A new back-emf method for measuring the thermodynamic emf of molten salt cells of the type M/MCl/sub 2/ in molten salt solvent/Cl/sub 2/ is presented. Decomposition potentials are measured in the course of the thermodynamic emf determination. The systems PbCl/sub 2/-ZrCl/sub 2/, LiCl-KCl eutectic, LiCl-KCl- NdCl/sub 3/, MgCl/sub 2/ in LiClKCl and NaCl, SnCl/sub 2/, KCl, and PbCl/sub 2/, and ZnCl/sub 2/ in LiClKCl eutectic were studied. The thermodynamic emf's obtained by the back-emf method are in good agreement with values calculated from independent thermochemical data. Thus Raoult's law is thought to apply in these simple systems to within a factor of two in the activity coefficient. (auth)

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Burnout heat flux data were obtained under conditions of zero exit quality and bulk boiling at the exit of electrically heated test specimens. These specimens were long, narrow channels with various slot thicknesses, sunfaces, materials, and length-to-diameter ratios. Tests were run at 2000 psia and mass velocities from --0.2 x 10/sup 6/ to 3 x deg was also investigated. The rectangular channel burnout results are in reasonable agreement with data previously obtained for round tubes. A design equation is suggested which yields a conservative estimate of the burnout heat flux in the low subcooling and quality regions. A burnout loop and method of operation are described. (auth)

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Past experience has shown that the demand for increase separations plant capacity comes up very regularly. One of the variables which greatly affects plant capacity is cross-sectional area of the individual vessels. Larger areas permit greater flow rates as well as more space for the installation of heat transfer piping (shell and tube concentrators). Design considerations of the separations plants vessels have been based on both circular cylinder and slab geometries. A study has been made to determine other vessel geometries that will result in safe vessels from a nuclear safety standpoint and at the same time offer larger cross-sectional areas than right circular cylinders. Vessels of elliptic as well as annular cross sections have been considered. It is neither the intent of this study to discuss the effects of intersection, vessel piping, etc., nor the pros and cons of fabricating feasibility and structural strength of these different shaped vessels. The main purpose is to make comparisons of cross-sectional areas (capacity parameter) of safe vessels so that vessel shape may be evaluated as one of the parameters in any design study for separation plants.

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