This procedure is intended to be used as: 1. An instruction and guide for operation of the KER loops. 2. To aid in familiarization and understanding of the general operation of the loops. 3. To prevent lost time due to errors in loop operation. The procedure is not meant to be completely comprehensive in all details of loop operation.

An abrasive cutoff machine design, based upon a previous model, (1) was undertaken to provide for the sampling of radioactive material. the design objective was; first, to provide samples for metallographic examination, second, to provide samples for physical and mechanical property testing, and, third, to meet the following design requirements: 1. Remote operation. 2. Airborne contamination control. 3. Radioactive waste collection. 4. Remote maintenance.

This report provides an overview of a gridded ionization chamber, instructions on how to operate the instrument, and then discusses the performance of the instrument so far.

Report detailing an analysis of the deposition of I-131 on vegetation. Analysis was necessary to determine the potential hazards of the gases from the dissolution of the metal on vegetation.

Report detailing the refractive index of solutions of uranyl nitrate, nitric acid and aluminum nitrate. This report builds upon preliminary data and a brief discussion that from a previous report. This report covers more accurate and detailed data that had be accumulated following the initial report.

A report describing a the results of a fluorimetric and volumetric method for the determination of fluoride. This method was developed for the determination of ionizable fluorine in gases in the range of 1-500ppm. This method was chosen because the determination depends on the generation of a color rather than the bleaching effect or on a change of color.

Automatic sample changer developed to increase the number of samples that can be handled daily.

By radiation dosimetry, we will mean the determination of the energy deposited per unit mass of irradiated material by ionizing radiation. Usually the material of interest in tissue and the results are to be applied to a radiobiological experiment, a radiotherapy treatment, or the protection of personnel from radiation hazards. The same methods, however, are applied to such engineering problems as the production of heat by reactor radiations, the use of radiation in chemical reactions or food processing, etc.

The purpose of this report is to provide calculated liquid flow pressure drop data for the 1706-KER recirculation loops.

From summary: "The methods of calibrating the 305 pile for impurities and density differences in graphite are reviewed and calibration constants are calculated theoretically."

The Biology Operation, Hanford Laboratories, required plutonium dioxide particles in five different micron and sub-micron size ranges. These were to be supplied as a water suspension in small containers. It was necessary to design equipment, suitable for hood operation, which would give a satisfactory separation of these particles.

Abstract: This report gives the results of a radiochemical analysis of particles collected by electrostatic precipitation from ventilation air of the "B" plant at Hanford Works.

This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.

The solids in Purex lww were first observed during flowsheet tests for recovery of fission products from plant wastes. Since the nature of this solid was not apparent from the flowsheet composition of lww, some work was performed to characterize this material. Although this work has been conducted over a period of about one year, it has been subordinate to the main one of testing flowsheets for fission product recovery. The solids have been observed in each of about six samples of plant lww that have been studied, and the centrifuged volume of solids has been about four percent in each case.

Experimental studies on continuous denitration performed in 321 Building resulted in the development of an agitated-through-type calciner. The performance of a paddle-agitated 4-in.-diameter by 44-in.-long reactor was sufficiently promising to warrant construction of a 16-in.-diameter by 8 ft.-long semi-plant scale model. This progress report summarizes the results of studies to date employing the semi-plant scale calciner.

In some engineering applications it has become necessary to operate equipment containing small diameter rods or tubes oriented parallel to flow stream. In the case of several nuclear reactors such as the Plutonium Recycle Test Reactor and the S. S. Savannah Maritime Reactor, bundles of small diameter rods are used as the fuel elements. The situation also has application to heat exchangers. A method for accurately predicting the pressure drop characteristics of various bundle configurations would be helpful in the design and selection of equipment. Some progress has been made toward gaining a greater knowledge of the bundle characteristics under low temperature conditions. This report includes the development of relationship for the effect of temperature on pressure drop.

Feasibility of conversion of uranyl nitrate to uranium trioxide by the continuous addition of concentrated uranyl nitrate solution to hot, agitated UO3 powder.

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.

The following report covers the construction materials selected for laboratory corrosion studies and the determination of their corrosion rates in process solutions.

The discharge of cooling water from the Hanford reactors introduce radioactive contaminants to the Columbia River. These materials may subsequently bring about exposure to human populations either through the direct use of the water for sanitary purposes or transfers of the radioisotopes into the food chains. It is therefore desirable to keep to a minimum the amounts of radioisotopes released to the river.

Considerable work has been done on decontamination procedures for both corrosion products and fission products. Testing of promising procedures under typical rupture conditions is an important phase of this work. The Irradiated Rupture Prototype (IRP) has been used since August in this evaluation work. This document is one of a series reporting these data.

This report describes the design, construction, and application of an electrical analogue for solution of the steady state problem. Teledeltos paper (an electrically conductive paper) was used to construct this analogue, and although this and other sheet materials has been used for heat transfer analogues in several previous investigations, it is believed that the present work is unique in the application of Teledeltos paper to three dimensional problems of radial symmetry.

The following report describes the process of the determination of nitrous oxide with the infrared spectrometer.

The chemical processing industry relies heavily on the use of rotary pumps to move massive quantities of liquids. The rotating elements of these pumps, generally of the deep-well turbine type, are submerged in the solution being pumped. This singular factor sometimes imposes a severe limitation on the choice bearings because the liquids are frequently corrosive and have poor lubricity. At the Hanford Atomic Products Operation a further complication arises from the effects of radioactivity in the solutions being transferred. Radiation and temperature can and will cause physical damage to many substances, including certain potential bearing materials such as plastics. These factors, coupled with the economics of remote operation and maintenance, have lead to the need for a test program to screen and evaluate potential bearing and journal materials.