This annual report (1958) from the Hanford Atomic Products Operation. Various programs are briefly described including irradiation processing, fuels preparation, chemical processing, research and development, and supporting operations.

This is a progress report of the production reactors on the Hanford Reservation for the month of March 1953. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

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A series of critical experiments with blocks of 2% U/sup 235/--enriched UF/sub 4/-C/sub 25/sub 5/H/sub 52/ was initiated at the ORN L Critical Experiments Facility. Thus far assemblies with H:U/sup 235/ atomic ratios of 195 and 294 were built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres were determined to be 16.3 and 8.5 kg of U/sup 235/ for fuel mixtures with H:U atomic ratios of 195 and 294, respectively. The minimum critical masses for unreflected spheres of these two fuel mixtures are 24.3 and 12.7 kg of U/sup 235/ respsctively. (auth)

A controlled-temperature irradiation capsule was operated containing small fueled specimens at 160O to 1650 F. The design involved calculating the specimen heat-generation rate and designing an insulating gas gap around the specimens to achieve the desired temperature. Electric heaters were inserted to help control temperature. The thickness and composition of the gas gap were modified prior to operation on the basis of information on probable neutron flux obtained from a nuclear mock-ups and on the basis of information on the thermal resistance of various gas annuli obtained from a thermal mock-up. The desired irradiation temperature of 1625 F was achieved with a variation of sintering time 25 F. (auth)

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The tabulation of pipe lengths, with calculated surface areas and volumes, was assembled from physical measurements of the process piping, included also is a list of instrument lines, with their measured lengths and estimated volumes. (auth)

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This report discusses the corrosion of fuel element jackets and process tubes. A brief background in electrochemistry is presented, and the corrosion of aluminium, aluminium alloys and zirconium is summarized.

This document is a compilation of obsolete security codes, convenience codes and local jargon in use, or previously used, at Hanford Works. It is compiled to aid readers in understanding the Hanford report literature, particularly that originated in the early years of the Project.

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The Reactor Safeguard Committee formula for the allowable minimum distance between a reactor and the public domain is expressed as: r = 0.01{radical}P, where r = radius from reactor in miles, and P = reactor power level in kilowatts. The six plates in this report illustrates the application of this formula for Hanford Works, both for individual reactors and all reactors in an area.