This document presents a summary of work and progress at the Hanford Engineer Works for August 1955. 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 Sciences, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

Six types of instruments are being considered for the metering of flow and/or density in high temperature (300 deg C) and pressure (2000 psi) slurry flow systems. Three of these meters yield readings that depend only on the flow rate or the density, one (the Double Rotameter) yields two readings from which both the flow and the density may be determined while another (the venturi) yields a reading that depends on both the flow rate and the density and thus may be either a density-meter or a flowmeter depending on which variable is the unknown. The remaining instrument (the ultrasonic meter) may yield a signal dependent solely on the flowrate or the density depending on the physical setup. This memo briefly describes these instruments, listing their particular advantages, the difficulties that may arise in their use and the state of development of each. (auth)

One of the specifications for the final plutonium product is a maximum neutron emissivity (neutrons per gram-second). The major source of neutrons in plutonium is the spontaneous fission of the 240 isotopes. The concentration of the 240 isotope is a function principally of the total pile exposure and, to a lesser extent of pile operating parameters; in particular, the moderator temperature. The objectives of this production test were: to establish with greater accuracy and precision, empirical relationships between the neutron emissivity, the plutonium isotope 240 concentration, and the pile exposure; and to determine if the isolated plutonium nitrate solution could be used as a control point for neutron emissivity prior to final fabrication. Accomplishment of these objectives would permit setting of pile exposure goals at the maximum possible level for greatest economy while still maintaining product quality within specifications.

Calculations were performed to determine the behavior of the TBR under certain conditions involving interruption of normal operation. The situations considered are sudden stoppage of circulation in the core circuit, sudden cessation of heat removal in the heat exchanger, and circulating pump failure. The first two situations result in a rapid, hazardous temperature rise; no danger appears in the third condition. (D.E.B.)

Topics discussed include procedures for the determination of Po in urine, feces, and blood; the determination of Be in biological materials; application of statistical methods to bio-assay; techniques for low-level alpha counting and pulse-height analysis; the toxicology of plutonium; the metabolism and toxic effects of fission products; methods for the radiometric determination of I/sup 131/ and Sr/sup 90/ in urine; procedures for the radiochemical analysis of Sr and Ba in human urine; and the design and performance of a wholebody gamma counter. (See also NLCO-595.) (C.H.)

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Experiments are proposed to studp the effects of reactor radiation at elevated temperatures on the stability and corrosive properties of aqueous fuel systems. A general description of the experiment, its hazards, and safeguards is given. (M.H.R.)

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