During the spring 1952 atomic weapons tests a nationwide network of weather stations, supplemented by 16 foreign stations, collected samples of settled and airborne dust which were counted radiologically. The data are reported as bases for estimating possible health hazards.

At the present time, production commitments require that each of the two dissolvers used at the Redox Plant be charged with 4.95 tons of irradiated metal every other day. After the aluminum jackets are removed from the slugs, the uranium is dissolved in three ``outs`` of 1.65 tons each. Because meteorological conditions often limit the time when the radioactive dissolver off gases may be emitted without contamination of the surrounding area, the dissolving requirements are frequently too great to maintain the required dissolver charging schedule. Unless the dissolving time cycles (or the meteorological limitations) can be reduced to assure that charging every other day can be maintained, phase 2 rates cannot be met even after activation of the third (spare) dissolver. As a means of reducing the dissolver time cycle and enabling the charging of each dissolver on alternate days throughout the year, a proposal was submitted that each dissolver charge be dissolved in two cuts of 2.475 tons each. This report presents the results of the plant test to determine the operational feasibility and relative merits of this proposal. Moreover, the information obtained may be used on a supplemental basis for the design of the Purex Plant dissolvers. 3 …

This paper summarizes the proposed construction of the Priest Rapids Dam on the Columbia River by the Atomic Energy Commission. Power generation to the Hanford Works and flood control for the surrounding area is the main goal for the construction of the dam. The summary covers the feasibility of the dam from its design, operation, benefits, security, drawbacks, etc.

The increase in process tube outlet water temperature to 90{degree}C resulted in increased emergency water flow requirements as indicated by recently approved curves which establish minimum crossheader pressure requirements for the first three minutes following an electrical power failure. To determine whether 190 Building secondary process water pump capacities are adequate for current minimum reactor water pressure requirements, process water pump trip-cut tests are being conducted at all reactors by the Process Unit in accordance with recommendations of the Reactor Process Committee. The results obtained to data in these tests, as well as current plans for the remaining tests, are presented in this document.

This document presents a summary of work and progress at the Hanford Engineer Works for December 1952. 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.

Experiments are described in which the change in thermal conductivity of U-impregnated graphite under neutron irradiation was measured. Thermal resistivities relative to the thermal resistivity of undamaged impregnated graphite are reorted as functions of exposure. From applications of the expermental results to the North American Aviation low-power research reactor the peak tem. of the core is determined for a given reactor power and time of operation.

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