Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.

From introduction: "The over-all objective of the present study was to determine the nature and extent of the present study was to determine the nature and extent of the corrosion of these materials under a variety of such storage conditions and to determine the ability of several potential protective coatings to retard this corrosion."

From Introduction: "The present report describes the condition of all of the porcelain enamels after exposure for 3 yr."

Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r2/r1, and in the study it was varied from 1.0 to 10.0."

Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.