From Introduction: "Information has been accumulated about the property changes produced, but there are essentially no reliable quantitative data correlating property changes with the magnitude and energy distribution of the neutron fluxes responsible for the changes. The design of the Basic Radiation Effects Reactor (BRER) presented herein stems from the two main requirements: 1. a fairly high-level, high-energy neutron flux with minimal thermal neutron and gamma-ray background is desired; 2. the peak of the neutron-energy spectrum should be variable within the approximate range from 10 to 1000 kev."

From Introduction: "To overcome the difficulties another investigation has been carried out wherein the rolling stock was subjected to step reduction and annealing treatments designed to develop a small, uniform grain size prior to the final rolling at room temperature. The results of metallographic, dilatometric, and X-ray diffraction studies of this material are given."

From Introduction: "The efficiency of the converter is computed with the least possible assumptions. Thermal emissivity and the interelectrode heat-transfer coefficient are varied, and the effect on efficiency is investigated."

From Abstract: "The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated."

From Summary: "The strains in the walls and ceiling of Cell No. 5 were recorded with 39 SR-4 strain gages strategically placed on reinforcing steel. Table I summarizes the comparative results without including correction for stress concentrations. The general pattern of cell behavior at 10 psig, as summarized in Table I, is shown in Figs. 10, 11, 12."

Report containing experiments regarding the slopes and deflections of different grid support structures for a nuclear reactor.

From Introduction: "The purpose of this study is to investigate some of the hydrodyamic aspects of two-phase heat transfer in the lower quality range. The results of this study should contribute to a better and more thorough understanding of the processes and mechanisms affecting two-phase heat transfer, and in this way help in improving its prediction."

Report discussing the "problem of obtaining a curve of the heat flux vs. temperature difference for boiling liquid metals" (p. 3). Contains discussions of a variety of heating techniques, though it focuses on electron-bombardment heating.

Report issued by the Argonne National Laboratory discussing the propagation velocity of pressure pulses in two-phase mixtures. As stated in the abstract, "in this study, a comprehensive analytical development of the propagation velocity of small pressure pulses is presented for bubble, annular, stratified, droplet, and slug-flow regimes. Particular attention is given to the influence of flow regime on the momentum transfer between phases" (p. 9). This report includes tables, illustrations, and a photograph.

Report describing the Argonaut Reactor located at the Argonne National Laboratory. Photographs and descriptive drawings of the reactor are included.

Report issued by the Argonne National Laboratory discussing two-phase flow studies that were conducted "to obtain empirical density relationships and pressure drop friction factors for two-phase mixtures" (p. 11). This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.

Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing single-phase water loop systems. As stated in the introduction, "the principal objective of this study was to determine the reliability of the calculations based upon numerical solutions of finite-difference energy and flow equations" (p. 9). This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing the Conference on the Toxicity of Carbon 14. At the outset of the meeting it was emphasized that the group was brought together to discuss work which had a bearing on the toxicity of C14 compounds used either clinically or industrially, and the hope was expressed that the group might be able to reach some conclusions on these matters. This report includes tables.

Report issued by the Argonne National Laboratory discussing a progress report on the Argonne-Oak Ridge digital computer. This report is an interim report, whose primary value is that it has forced those engaged in the work to give concrete expression to what they have been doing and thinking about up to this point. This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory discussing the progress and work completed between February and April, 1949. Descriptions of the studies conducted and progress made are presented. This report includes tables, illustrations, and photographs.

Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.

Ptolemy is an IBM/360 program for the computation of nuclear elastic and direct-reaction cross sections. It carries out both optical-model fits to elastic-scattering data at one or more energies, and DWBA calculations for nucleon-transfer reactions. Ptolemy has been specifically designed for heavy-ion calculations. It is fast and does not require large amounts of core. The input is exceptionally flexible and easy to use. This report outlines the types of calculation that Ptolemy can carry out, summarizes the formulas used, and gives a detailed description of its input.

A procedure is described for the dynamic analysis of a fast-reactor hexagonal subassembly. The internals of the fuel subassembly are treated by an axisymmetric hydrodynamic code REXCO-HT which, among other properties, possesses a model of an MFCI pressure source. The housing of the fuel subassembly is handled by the SADCAT code, which is based on a triangular finite element in three-dimensional space. The code is used to illustrate the discrepancies involved if the hexcan is modeled by a cylinder of the same thickness. A study is also made of the reduction of cylinder thickness such that the same final cylindrical deformation can be predicted. A discussion in arriving at such an equivalence is offered.

Various mechanisms that can induce flow instabilities in two-phase flow systems are reviewed and their relative importance discussed. In view of their practical importance, the density-wave instabilities have been analyzed in detail based on the one-dimensional two-phase flow formulation. The dynamic response of the system to the inlet flow perturbations has been derived from the model; thus the characteristic equation that predicts the onset of instabilities has been obtained. The effects of various system parameters, such as the heat flux, sub-cooling, pressure, inlet velocity, inlet orificing, and exit orificing on the stability boundary have been analyzed. In addition to numerical solutions, some simple stability criteria under particular conditions have been obtained. Both results have been compared with various experimental data, and a satisfactory agreement has been demonstrated.

The interim report presented describes a continuation of the work reported in ANL-7890, Interaction of Sodium with Molten Uranium dioxide and Stainless Steel Using a Dropping Mode of Contact. In the current study, sodium was injected into a pool of molten uranium dioxide. The experiment consistently produced vapor explosions, both with the injection nozzle above and beneath the surface of the uranium dioxide. Although the efficiency of the conversion of thermal to mechanical energy was small (due in part to very conservative data analysis and an inefficient geometry), the results did demonstrate that there is no intrinsic reason why reactor materials cannot produce a vapor explosion.

About 1200 Mark II driver-fuel elements were xenon-tagged to facilitate qualification for irradiation of Mark II fuel manufactured at ANL-West. Tagging equipment was designed and developed. In this equipment, the plenum in a fuel-element jacket was evacuated then filled with xenon to a predetermined pressure. The equipment design allows tagging and element fabrication to proceed normal rates for production of fuel elements. A Kr-85 tracer in the xenon-tag gas verified by gamma counting the adequate tagging of each element.