Whence came life on the surface of the earth? Whether or not a complete answer to this question may be found within the context, and content, of modern science, may be a moot question. It is our purpose to see how far we can devise an answer, and how satisfactory it may be, within that context. We trace a path from the primitive molecules of the primeval earth's atmosphere condensed from space through the random formation of more or less complex organic molecules, using the available energy sources of ultraviolet light, ionizing radiation or atmospheric electrical discharge, through the selective formation of complex organic molecules via autocatalysis, finally, to the informatiion-transmitting molecule which is capable of self-reproduction and variation. In addition, somewhere, either during the course of this Chemical Evolution, or perhaps succeeding it, a system has been evolved in which the concentration of the reaction materials was retained in a relatively small volume of space, leading to the formation of cellular structures. Man is about to send back into space some bits of the dust from whence it originally came, It is thus not only timely but more significant than ever before to ask again the question: What are …

A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.

From introduction: A project to use the immense energy concentrated in a nuclear device to construct an experimental deep-water harbor has been proposed by the Atomic Energy Commission and is referred to as Project Chariot; it is one phase of AEC Project Plowshare...During the field conference, Mr. Gerald Johnson of U. C. R. L. requested that the U. S. Geological Survey submit a report on the summer's investigation around the first of November 1958. This preliminary report is in response to Mr. Johnson's request.

From introduction: The papers comprising the various parts of this report contain the preliminary results of the U. S. Geological Survey investigations in the U12b.02 tunnel at the Nevada Test Site.

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Prior to the installation of improved charging machines and charging techniques serious gouging of the soft aluminum fuel element jackets was not infrequent. A certain amount of mechanical abrasion also occurs as the element is pushed over the tube ribs in the course of the loading operation. To eliminate or at least minimize mechanical damage there has been some experimentation with hard anodic coatings applied to the aluminum fuel element jackets. This report is an evaluation of thinner anodic coatings which should develop lower mechanical stresses within the oxide and should be less subject to cracking.

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As new designs, geometries, and procedures for fabricating experimental fuel elements are developed, it becomes necessary to determine how well each new product fills the need which prompted its development. While the criteria for satisfactoriness vary with the type of fuel element, there is one criterion that is common to all types designed for use in heterogeneous reactors: the elements must withstand irradiation in the reactor for the required period without jacket rupture or excessive change in dimensions. To learn whether a new type of element meets this and other requirements, a statistically significant number of representative samples must be subjected to, first, comprehensive screening tests designed to insure trouble-free performance in the reactor; next, a long-term irradiation exposure equivalent to or exceeding that which will be normal for that type of element; and finally, a thorough examination to determine the extent of quality loss resulting from the irradiation. This report discusses the application of the foregoing philosophy in the evaluation of two lots of experimental fuel elements fabricated by unconventional procedures.

The objective of the production test is detailed in this report is to obtain information about the behavior of Zircaloy-2 jacketed rod-and-tube fuel elements during irradiation at high coolant temperatures specifically, this test should provide information about fuel element dimensional stability, suitability of the rod and tube support system, and behavior of the uranium--Zircaloy-2 bond. Four co-extended Zircaloy-2 jacketed rod-and-tube elements, two with welded tube end closure and two with integrally extruded tube end closures, will be irradiated to 2500 MWD/T at jacket surface temperatures up to 270{degree}C in the KER loops. One Zircaloy-2 jacketed seven-rod cluster UO{sub 2} element will also be irradiated.

The feasibility of adding four ``corner`` rods to the K Reactor`s 20-rod HCR system is being investigated. It is necessary to compare the costs and production gains of this method for gaining additional reactivity and heat distribution control with other supplementary control systems. This document presents the results of an investigation of the production gains that could be made by adding four rods to the KE Reactor HCR system.

In the course of trying to predict the shape of NPR horizontal rod and process tube channels after several years of operation, data from 105-K were referred to. While looking at the 105-K data the following possible explanation of the ``K`` reactor distortion phenomenon occurred to me. It is written up in this document as a possible aid to those responsible for evaluating the stack distortion problem in the ``K`` reactors. Data and references to data are presented first and then an analysis of the data is presented. The author does not purport to be an expert on the ``K`` stack distortion or graphite technology but has written this analysis because it appears to be a plausible explanation of existing conditions.

The distribution of the heated effluents discharged by Hanford reactors to the Columbia River has been a matter of interest since the early design stage of the first reactors. The pattern of this distribution is a major factor in determining the extent to which a downstream reactor is affected by those upstream, as well as the localized effects on the ecology of the river. Pollutional characteristics of the effluents are three - heat load (or temperature increase), chemical contents and radioactivity. The latter has received the greatest attention in connection with potential personnel exposure and effects on river biota; it has been assumed however, and generally confirmed by sampling that the measure of distribution of any one of these characteristics in the saw an for the others. Observed distributions of radioactivity for various river and reactor flow rates are documented. Unfortunately, any extrapolation of those observed distributions to altered flow conditions of river regimes is of questionable validity. Mathematical models of the problem have been formulated but have been of little value due to the necessity of measuring certain parameters under the conditions for which a solution is desired. Even so, calculated distributions provide only general patterns and would not …

On occasion a rear pigtail of a reactor fails and is blown free from its connectors. The coolant water then discharges into the rear face area. This in itself is not a particularly hazardous condition and need not necessarily require a reactor shutdown. It would be desirable, then, to continue operating the reactor in this condition until a shutdown is convenient. A question which does arise, however, is whether the Panellit protection procedures are adequate to guard against the hazards of an accidental flow reduction to a tube operating in this manner. The result of a loss of a rear pigtail is an increase in coolant flow rate and, consequently, a reduced Panellit pressure. Furthermore, with the rear pigtail missing, the coolant flow no longer discharges through the Parker fitting on the rear header. Critical flow through this Parker fitting strongly influences the course of events following an accidental flow reduction to a normal ``O`` geometry tube. While it was strongly believed that the concepts developed and the Panellit procedures devised for a normal ``O`` geometry tube would apply to the case of a tube with a missing rear pigtail, evidence could only be obtained by transient experimentation. This document …

Abstract: In 1958 geologists of the U.S. Atomic Energy Commission and the Instituto de Investigaciones Geológicas de Chile made a reconnaissance for uranium in the Mamiña area, Province of Tarapacá in northern Chile.

This preliminary report discusses the qualities of uranium and zirconium as getters, describing the methods of incorporating the elements.

Introduction: This exploratory work was undertaken as a preliminary evaluation of the area's uranium potential, and was limited to reconnaissance for favorable geologic indications of uranium, which included visits to selected localities and mining districts.

This report details activities of the Fuels Development Operation for the months of July, August, and September 1958.

The September, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).

It is recommended that the following described I & E fuel element pair be evaluated for rupture rate improvement, and if significantly improved, recommended for C Reactor usage. Operating conditions are estimated.

Since the New Production Reactor is to have higher power density than the existing reactors, graphite contraction is a critical factor in its design. Ample data are available to describe graphite distortion in certain temperature ranges in the HAPO reactors. H Reactor exhibits three distinct and increasing contraction rates, corresponding to 3 levels of equilibrium power. A small temperature dependence may exist. There is no evidence of saturation of graphite contraction in the HAPO reactors. Extrapolation of the current trends are made. Programs are underway to further define graphite behavior and to solve problems associated with graphite distortion.

This is the monthly report for the Hanford Laboratories Operation, September, 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, biology operation, physics and instrumentation research, employee relations, 4000 program research and development, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation are discussed.

Attached is a draft of revisions being made to subject document, HW-53612. These revisions pertain to the moderators only, and will be incorporated in an overall revision of the technical criteria, which will be issued soon. Requirements, criterion, and data are included.

The purpose of this report is to summarize briefly the work which has been done to date and to acquaint the reader with the results of the ``Hot Spot Investigation Program `` as well as some of the problems encountered.