This document details activities of the irradiation processing department during the month of September 1956. A general summary is included at the start of the report, after which the report is divided into the following sections: research and engineering operations; production and reactor operations; facilities engineering operation; employee relations operations; and financial operation.

In a previous study it was determined experimentally that heat deterioration, or burnout, of the shield masonite is more severe than radiation damage under existing and proposed operating conditions. Higher shield temperatures, which are expected to result from increased power levels, fringe enrichment, and higher graphite temperatures, will markedly increase the rate at which the masonite burns out. The laminated iron-masonite biological shield will lose, as a result of burnout, the hydrogen and oxygen necessary to attenuate and moderate neutrons. The purpose of this production test has been to obtain experimental data from which future shield leakage rates could be estimated. The attenuation data reported here were obtained in the DR pile bulk shield facility from experiments using various void spacings to simulate burnout conditions. From these data it was hoped to determine (1) the resultant attenuation properties of the shields, and (2) the exposure rates due to radiation penetrating the shield.

None

Experimental investigations were undertaken at Columbia University to determine the heat transfer and fluid flow characteristics of fuel elements for the Savannah River reactors. Primarily the tests simulated quatrefoil operation, but a number of tests directly applicable to the operation of extended surface fuel elements were performed. Data books were published in which the experimental data are tabulated.

Sodium dichromate has been tested for use as a process water corrosion inhibitor at a concentration of 0.5 ppm. The test was conducted by operating one half of D Reactor with 0.5 ppm while the other half operated at the normal concentration of 2 ppm sodium dichromate. A concentration of 0.5 ppm was found to be as effective a corrosion inhibitor as the normal concentration of 2 ppm except under one very important set of circumstances. If the reactor process tube ribs were previously worn or corroded down, so that the water in the between-rib annulus became excessively hot; 0.5 ppm sodium dichromate was found to be non-effective in stopping corrosion at this location. From five to ten times as many slug ruptures and tube leaks occurred from this accelerated between-rib corrosion if the sodium dichromate concentration was 0.5 ppm rather than 2 ppm.

None

None

A brief description of the process is given, and details of work over a three-year period are summarized. The continuous production of Re metal by low- temperature fused salt electrolysis into a continuously circulating Hg cathcde has been demonstrated. The product is amenable to direct hot pressing or to powder preparation by distilling off the Hg. The production of pure BeCl/sub 2/ in good yield by direct chlorination of BeO has been demonstrated. The production of pure BeCl/sub 2/ in good yield by direct chlorination of beryl has been studied. The status of this work is not sufficiently advanced to permit valid conclusions as to ultimate success. The electrolytic cell and associated equipment and the chlorination equipment are described in detail. Operating procedures and representative results are given. The course for continued work is indicated. (auth)

None

None

None

None

None

None

None

This report and three appendixes were issued separately, but are cataloged as a unit. The necessity for treatment of hot laundry and decontamination room wastes prior to disposal at the out, and means for accomplishing this are discussed. A feasible procedure suggested consists of an adsorptionflocculation treatment with supernate disposal by dilution, pass through an evaporator, transfer to surge and decay tanks, with final sludge concentration in drums for retention and burial at sea. (T.R.H.)

This document presents a summary of work and progress at the Hanford Engineer Works for July, 1956. 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.

None

None

None

This report lists some physical properties data of aqueous homogenous reactor materials.