Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)

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This document contains information on special filter samples of Hanford Process Effluent Gases. The filters are identified by code numbers only. Included in this paper are tables explaining the sample code numbers, sampling locations, and process conditions during sampling. Also included, is a copy of the monthly and quarterly average results for Regional Monitoring's routine stack program for the fourth quarter of 1956.

Abstract: "The mechanical properties and corrosion resistance of induction-melted, zirconium-tin alloys have been determined. The alloys investigated contained from zero to five per cent tin and up to 0.3% carbon. The zirconium used was United States Bureau of Mines sponge zirconium. The mechanical properties investigated include the tensile, hot-hardness, and impact properties."

From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."

Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium."

This is the final report on the progress, "A Wide-Range Neutron Detector and Monitoring Instrument," ARF 1118-6. This report covers activities from May 8, 1958 to May 8, 1959. This report describes the basic design principles of a proportional counter that has been constructed whose cathode diameter increases towards one end.

This report discusses methods for preparing thin films of plutonium on metallic disks, which are used for alpha energy analysis, fission counting, and preparation of geometry standards in ordinary counting. Various methods of preparation were tested and analyzed, but electrodeposition was the most effective method. Deposition was then tested, but the yields were "somewhat erratic".

This report follows the study of the oxidation of plutonium III and IV to the plutonyl state.

The following report follows the inspections of a number of eddy-current instrument procedures. The objectives of these tests were to detect both weld defects and lack of integrity of the body of the fuel elements.

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This report discusses preliminary results acquired from investigations made on the ultrasonic properties of uranium, such as sonic vibrations in the megacycle frequency range.

The following report proposes various methods in injecting and heating in mirror machines, using high-energy ion beams.

From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.

Abstract: "The measurement of large, high-frequency, short-pulse currents--ordinarily complicated by inductance, stray magnetic fields, and magnetic forces that tend to disassemble the measuring device--is simplified and made with an average error of 2-1/2% by the use of a specially developed noninductive radial shunt in conjuntion with an oscilloscope. The skin-effect correction is derived theoretically and the accuracy of the method is demonstrated."

The following report provides the results of an accelerated corrosion test that was performed to compare the effect of two coagulants on the corrosion rates of aluminum slug jacket alloy and 72S. Additionally, some analytical data on the water from the two treatments were obtained and are presented in this report.

From introduction: "The following recommendations represent the best estimate, based on present knowledge, of the requirements for generally applicable or "universal" instrument for the continuous monitoring of radioactive process streams in terms of their gamma activity."

The following report describes two methods of extrusion cladding of uranium fuel plates that were investigated and evaluated.

This document presents a summary of work and progress at the Hanford Engineer Works for December 1953. 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 summaries 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.

This is a progress report of the production reactors on the Hanford Reservation for the month of December 1951. 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.

This document presents a summary of work and progress at the Hanford Engineer Works for May 1954. 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 summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Science, 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.

Present methods for monitoring Ru{sup 103}, Ru{sup 106}, and I{sup 131} in stack gases involve sampling by filtration and scrubbing and analysis by chemical separation and counting or by gamma spectrometry. Filtered samples, which are ordinarily collected over a complete day, are analyzed for total ruthenium and iodine by gamma spectrometry and for the individual isotopes by chemical separation and counting. The present scrubber monitors the sampler gas for total activity. As an aid to Radiological Sciences evaluation of stack gas hazards and to operations control of radioactive gas emission, Methods and Instrument Development collaborated on the planning of a continuous monitoring system. This memorandum has the purpose of outlining the plan, reviewing progress since conception in October, 1953, and reporting work still to be done.

This report, dated March 22, 1954 details work procedures for the 200- West Area at HAPO. Topics discussed include emergency procedures, safety and housekeeping practices, policies and procedures, instruments and equipment located at the 622 tower, instruments and equipment located offsite, observational procedures, form entries, and card punching, and weather forecasting.

chemical Research and Development Operation was contacted by R. Nilson of Irradiation Processing Department in order to obtain an analysis from a chemical viewpoint of the worst credible accident to a full E-N reactor loading. This analysis would be used to present to the ACRS directly or would be abstracted to prepare a supplementary report. The primary purpose of this report is to present an analysis of the chemical behavior of an E-N loading in the event of the sudden loss of coolant to the entire reactor, with, however, normal operation of the control devices such that the reactor is initially driven sub-critical. We are here concerned wit the effect of a rising temperature upon the E-N load, the rise in temperature being primarily caused by the release of fission product energy.