An 80 Mw aqueous homogeneous burner reactor suitable for producing 20 Mw of electricity at a remote location is described. The reactor fuel consists of a light water uranyl sulfate solution which acts as its own moderator and coolant. The uranium is highly enriched (93% U/sup 235/). The primary considerstions for the design were simplicity and reliability of the components, automatic demand control and safe for any load change, full xenon override not required, possibility of construction within the immediate future, and economic operation not the cortrolling factor. Reasonably complete studies are presented for the reactor physics, safety, stability, chemistry, hent transfer, and operation of the system. (auth)

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This report, for July 1957 from the Chemical Processing Department at HAPO, discusses the following; Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

Equipment and procedures uscd in testing Army Package Power Reactor control rod drive mechanisms are described. Photographs of mechanism components taken before and after testing are included. (D.E.B.)

Direct alpha counting to determine fissile material in dilnte solutions of high total solids content is likely to be inaccurate due to the difficulty of preparing thin sources. This report describes a neutron-activation analysis method which eliminates this risk. Results obtained by the neutronactivation analysis for U/sup 238/ in solution are compared with results obtained from other methods. The standard deviation and sensitivity are shown. (auth)

This summarizes the work done to date on the development of an epoxy resin bonded explosive (HMX). The original target values have been satisfied and further investigations will be on a semi-pilot plant scale.

Primarily the studies have been devoted to a search for chemical reactions which are promoted by gamma radiation. The underlying purpose behind the studies has been to develop uses for the radiation available from waste fission prcducts. A brief description of all the reactions studied during the program is presented along with appropriate references to the original reports and publications. These give the detailed account of the work done on each reaction and the reader is referred to them for more complete information. (auth)

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An underground reinforced-concrete family shelter designed for six persons was tested at three anticipated nuclear blast overpressures: 30, 48, and 65 psi. The structures were calculated to sustain a 30-psi long-duration overpressure. Postshot examination of all shelters lndicated there was little or no deflection in the reinforced-concrete members. Although the actual blast load was of short duration, the natural period for the structures was also shortp therefore it is felt that the structures would withstand similar overpressures from long-duration blast loadings. The average attenuation factor for gamma radiation varied from 3000 to 4500. Permanent damage was confined to the exposed portions of the ventilation pipes, which were bent to a nearly horizontal position. The steel-plate door at the 65-psi level was dished inward about 1 1/4 in., but it opened and closed easily. (authl

This report describes the operation of the fuels preparation department for the month of July 1957. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.

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An optimum econonic design for a high temperature, helium cooled, central station reactor power plant of about 400 Mw of electric power was determined. The core consists of a randomly packed bed of unclad graphite spheres, approximately one in. in diameter, impregnated with U/sup 233/ and thorium such that a conversion ratio of near unity is achieved. The high temperature helium permits steam conditions, at the turbine throttle, of 1000 deg F and 1450 psia. (auth)

This document provides a summary of facilities, both proposed and constructed, and programs of the Hanford Atomic Products Operation. Budgets, by program, are also provided. (FI)

This document presents a summary of work and progress at the Hanford Engineer Works for July, 1957. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and separation sections. The Engineering Department`s section summarizes work for the Technical, Design, and Project sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services Departments have sections presenting their monthly statistics, work, progress, and summaries.

Valves for several purposes are listed and indexed, together with pertinent design and performance information and identifier numbers.

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A power unit comprised of a reciprocating hydraulic cylinder controlled by hydraulic, mechanical, and electrical elements was developed to drive pulse generators for solvent extraction columns in the Purex Hot Semiworks. Design bases included remote control of continuouslyvariable pulse amplitudes between 1/ 2 and 1/2 inches, and pulse frequency up to 120 cycles/min. Each of nine power units operated 30 to 60 million cycles without serious difficulty, although minor modifications and corrections were made during scheduled shutdowns of the Semiworks. Operational irregularities, such as erratic or drifting amplitudes, occurred with sufficient frequency to indicate deficiencies in the original design. The triangular pulse wave which is characteristic of the power unit was suspected on several occasions as having an adverse effect on extraction column performance. However, no correlation was found to show that column performance is adversely affected by the triangular pulse. (auth)

This report summarizes the work done to date on the development of an epoxy resin bonded explosive (HMX). The original target values have been satisfied and further investigations will be on a semi-pilot plant scale. The following characteristics have been determined on laboratory specimens. Compressive strength, 11-12,000 psi; sensitivity (50 % height) 31 cm; density, 1.81 gm/cc; vacuum stability (cc gas/gm/24 hrs at 100{degrees}C), .42 cc/gm.

This study has investigated the feasibility of installing a gas generator-free turbine type power plant in the R3Y aircraft, using a circulating fuel reactor as a power source. Two variations of the cycle were considered. The split flow cycle bleeds high temperature, high pressure air from the gas generator directly to the free turbine in the wing. The through flow cycle partially expands the high temperature, high pressure air through the compressor turbine of the gas generator then directs the compressor-turbine exhaust air to the free turbine in the wing. Design parameters of pressure ratio, radiator depth, radiation flow density, and hot gas duct size were optimized to give minimum weight per shaft horsepower of the complete power plant. The weight of a split flow power plant capable of supplying 22,000 shaft horsepower was found to be 116,600 pounds. The weight of a similar through flow power plant was found to be 119,900 pounds. The reactor power required in both cases was 70 megawatts. The nominal gross weight of the R3Y airplane is 175,000 pounds. With pay loads of approximately 20,000 pounds, either nuclear conversion will have a gross weight of 200,000 pounds. It was found that either cycle could …

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This document details activities of the irradiation processing department during the month of July, 1957. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations: Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

Preliminary investigation indicated that it was possible to prepare thoria-urania solid solutions by sintering in air a mixture of ThO/sub 2/ and U/ sub 3/O.sub 8/. The U/sub 3/O/sub 8/ on heatin g in air was found to disassociate, and when heated with ThO/sub 2/, the resultant body was essentially a ThO/sub 2/-UO/sub 2/ solid solution. The methods used in preparing and granulating the ThO/sub 2/ and U/sub 3/O/sub 8/ for the BORAX-IV loading are discussed in detail. This material was dry pressed using pressures from 13,000 to 15,000 psi. The pressed pellets were loaded into alumina crucibles and fired to a peak temperature of 1700 deg C to 1750 deg C. The fired ware was found to have an average ap parent density of 9.8 g/cc. The pellets were loaded into Al1 wt.% Ni tube plates and the annulus between the pellet and the tube was filled with lead. After closing the open end of the tube plates, the plates were spot welded into a subassembly. (auth)

Included in this system description are the most important miscellaneous services required in the reactor portion of the plant. (W.L.H.)