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The purpose of this work was to investigate the possibilities of producing a plastic bonded explosive having greater mechanical strength than that of presently existing plastic bonded explosives. This interim report details activities and progress through July 15, 1957.

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A summary of the Cr data from the HRP in-pile corrosion program is examined in an effort to determine the Cr species present in such solutions under in-pile conddtions. Data from previous in-pile bomb and loop experiments pertinent to Cr behavior are tabulated, and correlations are offered to support a proposed model. It is pointed out that other interpretations of the same data are possible, and to obtain conclusive evidence as to the identity of Cr species in these solutions, especially designed experiments are necessary. (J.R.D.)

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This document has been written in part to answer questions concerning the feasibility and advisability of ``quickie`` discharge of ruptures at C Reactor. Justification of full pile operational charge-discharge (OC-D) is based in part on outage savings resulting from improved, rupture removal. Since a portion of the rupture removals might be accomplished within the scram recovery time (quickie) it is necessary to consider recovery time as a function of anticipated future power levels. In addition to answering the questions mentioned above, it was felt worthwhile at this time to discuss equilibrium control problems associated with OC-D which have been apparent during operation of prototype equipment, and on the basis of this information to consider reactor control with full pile OC-D.

The methods used to calculate the steady-state pressure and thermal stresses in the spherical portion or the HRT pressure vessel are presented, The stresses reported here were calculated using the methods considered most applicable st the present time. These methods yield stresses significantly greater than originally reported for the HRT because the calculated total heat generation rate in the vessel wall is greater, and its distribution is different. A comparison of tworegion (DP reflector) and single-region operation is made, showing very little difference between them insofar ss stresses are concerned. A limited amount of experimental heat balance data for the HRT vessel wall has been compared to the calculated values. Primarily on the bases of this comparison recommendations are made concerning further procurement of experimental data. (auth)

The intent of this manual is to present a description of the main process building, equipment, and auxiliary facilities as well as a process summary. Material is of a scope nature with more detail devoted to features unlike those of existing separations systems. An attempt is made to convey some of the basic design philosophy and the problems encountered in the development of design criteria. This information is written primarily for Separations Section supervision who have not had an opportunity to become conversant with the Purex Project. The manual may also be of assistance in orientation and training of personnel. In order to avoid repetition and duplication of effort, one line service diagrams, equipment sketches, tables, and detailed data are not a part of this manual.

Stainless steel-base fuel components of thin plate-typs construction and containing a dispersion of enriched UO/sub 2/ have been successfully employed in powering the Army package Power Reactor. The stationary fuel compcnent proposed for operation in the second core loading of the reactor is discussed. The component is designed for radioactive service in pressurized water at 4504DEF and consists of eighteen composite fuel plates joined into an Integral unit or assembly by brazing. Design specifications covering the material and dimensional requirements as well as the operating conditions are discussed. Step-by-step procedures developed and utilized in manufacturing the component are presented in detail. (auth)

The KPL No. 6, first-cycle Purex lA flow sheet is presented as an examaple of waste volume reduction through optimum solvent-extraction flow sheet design. Calculated on the basis of previous flow sheets, a 54 to 69% reduction of first-cycle waste storage volume is achieved by taming advantage of the extractability and reflux of nitric acid in TBP systems to provide adequate salting while minimizing the amount of acid going to waste. Although this report is concerned only with the first Purex cycle, the calculations are equally valid for the second U cycle, and the principles presented are applicable to similar nitnic acid-salted TBP systems. (auth)

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The objective of this program is to conduct a broad basic program of analytical and experimental research into the fundamental behavior of gas- lubricated bearings and to establish general design criteria for these bearings. The work to date has included both theoretical and experimental phases of hydrodynamic and hydrastatic lubrication phenomena, supplemented by a digital computer program. (W. L.H.)

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

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The toxicological properties of beryllium and compounds of beryllium are briefly reviewed, together with the historical developmert of the recommendations for maximum permissible beryllium air concentrations. The application of the enclosure technique for the control of beryllium hazards is described. Emphasis is placed on the design objectives of partial and total enclosures and the related function of auxiliary components. Monitoring procedures used to evaluate the performance of enclosures are discussed. (auth)

The scope of the study was primarily concerned with optimization of the geometrical and core-composition variables to achieve maximum flux in the loop region per unit core power without exceeding heat transfer and other engineering limitations. Centain other design questions are to be investigated. (A.C.)

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A total of 418 abstracts from this conference and the complete text of five plenary session papers, as well as 55 abstracts from as All-Union Conference on Radiation Chemistry, have been made available in translation in AEC-tr-2925. Almost all of these papers deal with the actual applications of tracers or radiation in the national economy. The papers presented were divided into three major sections: isotope production and high-intensity gamma systems, technical sciences and industrial uses of isotopes, and biology, medicine, and agriculture. A short summary of the papers as to groups is given. (W.D.M.)