The status of development studies being conducted on a pebble bed power reactor is outlined. The items discussed are fuel element manufacture, stability, and reprocessing, and component development. (D.L.C.)

This report addresses the advanced energy sources and conversion techniques.

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The basic design and development concepts are presented on a six vane air motor intended for use at elevated temperatures. (auth)

A parameter survey was conducted on 19-rod fuel clusters using 3 and 10 wt.% Mo--U alloys. Graphs are included for the core diameter and initial conversion ratio for k/sub eff/= 1.064 as a function of moderator can size, and for the effect of the Mo resonance integral. (D. L.C.)

The basic information about the path of carbon in photosynthesis is reviewed together with the methods that were used to discover it. This has led to the knowledge of what is required of the photochemical reaction in the form of chemical species. Attention is then directed to the structure of the photochemical apparatus itself insofar as it is viewable by electron microscopy, and some principoles of ordered structure are devised for the types of molecules to be found in the chloroplasts. From the combination of these, a structure for the grana lamella is suggested and a mode of function proposed. Experimental test for this mode of function is underway; one method is to examine photoproduced unpaired electrons. This is discussed.

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The iodine species formed either by adding hypochlorite to a basic iodide solution or by adding triiodide to sodium hydroxide, was identified as hypoiodite ion. The absorption spectrum of IO{sup -} was investigated in the wavelength range from 450 m{micro} to 280 m{micro}. The kinetics of the reaction I{sup -} + ClO{sup -} = IO{sup -} + Cl{sup -} was studied spectrophotometrically in alkaline solution. The forward rate law was found to be d(IO{sup -})/dt = k(I{sup -})(ClO{sup -})/OH{sup -}. At 25 C and an ionic strength of 1.00 M, k is 61 {+-} 3 sec{sup -1}. It was found spectrophotometrically that for certain ratios of the initial iodide to hydroxide concentrations, there was evidence of the presence of I{sub 3}{sup -}, I{sub 2}OH{sup -}, and I{sub 2}O{sup 2-} along with IO{sup -}. The equilibrium constants between IO{sup -} and these three species were evaluated by a graphical method. The formal potential of the cell: Pt:H{sub 2}:1 M NaOH : 1M NaOH, KI, NaIO : Au was found to be 1.297 v at 25 C. The equilibrium constant, K{sub 2} = (I{sub 3}{sup -})(OH{sup -}){sup 2}/(IO{sup -})(I{sup -}){sup 2}, of the reaction IO{sup -} + 2I{sup -} + H{sub 2}O …

This report covers studies of the excretion and retention of 'tracer' and toxic doses of the 11.2-day Ra{sup 223} isotope, its acute toxicity (organ weight changes, gross and microscopic pathology, and Fe{sup 59} utilization by the bone marrow), and long-term histopathological changes and alterations in the hemogram.

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 …

As a result of a wide variety of studies on photosynthesis in living plants and plant fragments, together with the development of photosensitive, photovoltaic junctions in inorganic crystals and the discovery and exploration of semiconduction in organic molecular substances, a suggestion has been made that the primary quantum conversion process in photosynthetic tissues involves the creation and separation of charge to opposite sides of an asymmetrically-constructed lamina, followed by the trapping of both the electrons and the holes which then lead to their respective chemical processes, namely reduction of carbon dioxide and oxidation of the water to oxygen. This has led us to study model systems as semiconductors with a view to creating an organic photovoltaic junction.

A description of the new Weldon Spring Feed Preparation and Sampling Plant for uranium concentrates is given. Prior to the startup of this plant the auger to be later installed was used in an evaluation program to test reliability for representative sampling and uniformity both within drums and between drums of various concentrates. Results of this program were used as a reference for the sampling plant evaluation which involved successive auger and mechanical sampling of a series of lots of several concentrates, followed by moisture determinations, uranium assays, and statistical analyses of the data. From the final results conclusions are drawn concerning the suitability of the mechanical sampling system for the concentrates examined.

The flowsheet proposed by KAPL for the treatment of alkaline nitrate radiochemical processing waste has been modified to include an ion-exchange step for the decontamination of cesium, strontium, and other cationic fission products. In laboratory studies of the electrolysis steps in a nitrate reduction cell, synthetic alkaline waste, 0.55 to 4.83 M total electrolyte, was decontaminated from ruthenium by factors of > 210. The nitrate of 3.0 M waste was reduced to ammonia with current efficiencies of 100%. Power consumption was 4.7 kwh/lb of nitrate reduced. Significant factors affecting the rate of ruthenium decontamination were temperature, cathode area, cathode current density, and electrolyte concentration. Those affecting nitrate reduction current efficiencies were the cathode current density, electrolyte concentration, and stirring rate. In an acid-base membrane cell, reusable nitric acid as well as sodium hydroxide was regenerated. However, such a cell is less economical to construct and operate than the nitrate reduction cell. At least 5 kwh of power is required to transfer 1 lb of nitrate from ORNL type waste. In addition, the greater complexity of the acid-base cell makes it less adaptable for remote control.

One of the major factors restricting reactor power levels is the incidence of ruptured slugs. The primary purpose in studying ruptures is to determine how reactor operating variables affect rupture rates. With this knowledge reactor operating conditions may be adjusted or controlled in the manner that will optimize reactor production. In addition, knowledge of rupture rate relationships are useful in fuel element development and in overall economic studies of existing and proposed reactors and reactor processes. This report is a compendium of various types of rupture information largely developed during the past eighteen months. Plant rupture experience for CY-1957 is reviewed; rupture rate correlations with reactor variables for solid natural uranium material are presented; a comparison between solid and cored natural uranium material rupture rates is made; the basis for current discharging practice of rupture-prone metal lots is discussed. 11 figs., 2 tabs.

The General Electric Company has prepared in past years numerous documents for the Atomic Energy Commission outlining in some detail its current and proposed programs at Hanford. Last year, at the request of the commission, program types of information were consolidated into one document, the HAPO Five Year Program. That document was well received and useful to an extent that the General Electric Company was requested by the Commission to prepare another covering the fiscal years 1959 through 1963. In outlining the five year program for the Hanford Atomic Products Operation, the General Electric Company has made assumptions regarding the US Atomic Energy Commission`s current and future programs and Hanford`s relationship to these programs. Two major objectives of the Commission were considered basic for future planning: first, to provide adequate atomic weapons for national defense; and second, to encourage and assist in the development of atomic energy for peaceful uses. The Hanford contributions to these objectives are conceived to include the acquisition and potential application of new technology in support of: (1) Increased production of plutonium, as nitrate solution, buttons, and as current and future shapes. (2) A program that will provide the technological capability to implement broad changes in …

This document details activities of the Fuels Preparation Department during the month of March 1958.

Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of the fuel elements within the reactor process tube, worn tube ribs, etc., are believed to cause the high local jacket temperatures necessary for the occurrence of intergranular corrosion.

A knowledge of the effect of reactor irradiation on the properties of UO{sub 2} is relevant to the design and evaluation of UO{sub 2} fuel elements for the PRTR. Of particular interest is the effect of reactor irradiation on the thermal conductivity of sintered UO{sub 2} and the type, mechanism, and extent of radiation damage in sintered UO{sub 2}. In the latter case the study of fractured surfaces of irradiated UO{sub 2} specimens is a method of determining the extent of radiation damage. It is the purpose of this report to propose an irradiation test of a number of capsules containing UO{sub 2} thermal conductivity and fractography specimens.

This report describes the operation of the fuels preparation department for the month of January, 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

An enriched I & E fuel element failed during irradiation under Production Test IP-109-AC in December, 1957. Radiometallurgical examination of this slug was requested by the IPD Process Analysis Operation. This report presents the results of the examination work.

This document details activities of the Fuels Preparation Department during the month of December 1957.

This document consists of three photographs of ruptured fuel elements. The position, date charged, date failed, exposure, power, lot and failure type are given for tube 3655-KE, tube 4153-KE, and tube 3849-KE. (GHH)

This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.

We have prepared what we call a bonded segmented fuel element. This fuel element has characteristics which make it an attractive prospect for high specific power operation at relatively low uranium temperatures. The fuel slug is made up of six longitudinal segments; each segment being bonded to the aluminum webbing and tubing that encases it. The pertinent information for this irradiation is summarized along with fabrication details and hazards, thermal aspects and calculations, and figures.