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The report summarizes Hanford`s operation in 1953. The 38% increase in separated plutonium over the 1952 level was one measure of achievement. 1953`s output was more than seven times that of 1947, the first full year of General Electric`s operation of Hanford. Although much of this gain resulted from new reactors, some was due to improved safety devices, and much was due to increased knowledge of the controlling factors which permitted more efficient operation of old piles and better design of new ones. Year-by-year reductions in the cost of converting uranium to plutonium tell the real story of progress at Hanford. The annual production gains could have been made by building many 1944 model piles, though at fantastic cost. Contrasted with this is the actual case--a few new, improved piles plus more production from the old ones.

This document details activities of the Hanford Atomic Products Operation (HAPO) during 1954.

A method is developed for the calculation of the effect of Doppler broadening of the absorption of the neutrons by a resonance absorber. Numerical values are given for the correction factors required in the interpretation of transmission experiments and self-indication experiments and for the self-shielding factors for slabs, spheres, cylinders, and homogeneous mixtures. (auth)

At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.

This memorandum concerns the relative activities of Argon 41 and Nitrogen 16 in the pile gas composed of 95 percent carbon dioxide and 5 percent air. The memorandum is dated November 16, 1950. (JL)

During the course of the ZPE-2 experimental program additional measurements were performed under the Alco Products Research and Development program. Included in this program were the evaluation of various absorber section compositions and reactivity studies designed to facilitate analytical techniques. The results of these measurements are presented. (auth)

A concpept for an advanced enineering test reactor is described. Thpe results of various investigations with regard to alternative design possibilitipes are presented. Retailed information is given rearding the nuclear and enineering calculations. (W.D.M.)

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The development of a matrix method of solving multigroup diffusion equations in nonmultiplying regions is described. The method is applied to a three-region shielding problem, and comparison is made with experimental results. Equations obtained by this technique can be solved with a desk calculator. (auth)

The expected maximum contamination of the HNPF cold traps and primary sodium pumps was determined along with the maximum dose rates from these components during removal and shipping. Suitable shielding for casks to be used in the removal operation and for shipping these components away from the reactor site is specified. Access to an unshielded cold trap is limited by high dose rates, i.e., 100 mr/hr at 120 ft, after 180 days decay time. A handling cask providing a radial shield of 3 in. of lead will provide adequate personnel protection for the removal operation, if 180 days decay time is allowed before the trap is removed. An additional 2.4 in. of lead is required for offsite shipment of the cask. This additional shielding can be added after the trap is removed from the reactor building. Dose rates from the cold trap after the shield plug is removed from the access hole are shown. If direct line-ofsight exposure is avoided, dose rates to personnel will be below 100 mr/hr at any position, and below 10 mr/hr at distances greater than 20 ft from the access hole. Dose rates from the cask during its travel away from the hole, will be …

The hazards associnted with the use of magnesium capsules in a CO/sub 2/- cooled reactor system have been analyzed, and consideration has been given to incidents which could lead to excessive temperature excursions and factors which could significantly reduce the ignition temperature of magnesium alloys. Methods of reducing the hazards associated with the Calder Hall type of reactor are discussed, and an experimental approach with which to define more aaccurately conditions that would lead to ignition is suggested. (auth)

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.)

This quarterly report details activities in analytical research by the Applied Research Unit of the Nucleonics Division during the months of April, May, and June 1952.

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.)

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A compilation of 290 references on gas bearings is presented. In most cases an English resume' of each reference is included a translation being made when required. The references are arranged alphabetically by first author. Indexes included are the year of origin corporate author, subject, patent number, and country of origin. (J.R.D.)

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