The Technical Division was asked recently to consider designs for new reactors that would add 8000 MW capacity to the Savannah River Plant. One modification of the existing SRP design that would enable a higher power rating, and therefore require fewer new reactors, is an increase in the maximum pressure in the D{sub 2}O system. The existing reactors at SRP are designed for a maximum pressure in the gas plenum of only 5 psig. Higher pressures enable higher D{sub 2} temperatures and higher sheath temperatures without local boiling or burnout. The requirements in reactor cooling facilities at any given power level would therefore be reduced by pressurizing.

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

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A research and development program in the field of thorium chemistry and metallurgy was conducted. Most of this activity was directed toward the development of techniques for the production of metal by fused salt electrolytic approaches, little effort being proportioned to the preparation of an electrolyte for the process. An aqueous method for the preparation of an anhydrous cell feed was set up and operated for several months. Relatively high operating expense and difficulties with materials of construction prompted the development of a more direct approach for the production of electrolytic cell feed. The system established for cell feed preparation converts thoriumn nitrate to a basic carbonate via the reaction between the nitrate and sodium carbonate, this precipitation being quantitative. Following a suitable filtration and drying operation, the thorium oxycarbonate is converted directly to the chloride by reaction with carbon and chlorine, forming a cell feed containing between 40 and 45% thorium in a molten matrix of sodium and potassium chlorides. The preparation of cell feed by the descrihed process was carried out on a small- tonnage basis, in 1,000-pound batches. The entire process is capable of heing operated on a continuous or semi-continuous basis and presents a commercially feasible …

The described plant will produce reactor grade Th at a price of 07 per pound. The plant operation is based on the preparation of electrolytic cell feed by fused salt chlorination techniques and converting the feed to high quality metal by high temperature electrolysis. (D.E.B.)

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Results indicate that corrosion of the metal is accelerated to a small extent during irradiation. A summary of the results from in-pile loops and in- pile autoclaves is given. (L.M.T.)

The food irradiation facility described consists of: a fully enriched light-water-cooled and -moderated heterogeneous reactor core surrounded by a blanket of indium sulfate aqueous solution; an indium solution system which includes the reactor blanket and the gamma radiators; primary and auxiliary cooling water systems for removal of reactor heat; radiator cubicles into which the food is conveyed for irradiation; and buildings for housing the reactor, radiators, and operations personnel. (auth)

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The critical parameters of aqueous UO/sub 2/F/sub 2/ solutions enriched to 90% U/sup 235/ in various arrays of interacting slab geometries have been determined for a single concentration. Critical solution heights for various configurations of three nominally 3-in. thick Al slab vessels and one 6-in. Al slab vessel were determined. (T.R.H.)

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The reference letter documented the plutonium concentration flowsheet in use at that time and proposed that this flowsheet be used for the scope design basis of replacement equipment. A study of the application of the reference flowsheet to the proposed remote package design (1) indicated that attainment of a plant capacity factor of four would be doubtful. This letter outlines a flowsheet reconciling process and equipment limitations and capable of a capacity factor of four.

This document is a copy of a memo dated October 30, 1956. Since the start-up of the Purex Plant, numerous process and equipment difficulties have been encountered in the concentration of plutonium in the L Cell Package. A summary of these problems and their resolutions was being documented by the Purex Technology Operation. One of the proposed remedial measures for improving on the present plutonium concentration equipment in the Purex Plant was to install new equipment constructed of more corrosion resistant materials and of a design simplified for contact maintenance.

This report is a compilation of brief abstracts of the Preliminary Reports n work done in the laboratories of the Ananlytical Chemistry Division at the X-10 Site during the months of January through June, 1956.

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The applicability of the gas centrifuge to the separation of the isotopes of the elements from Ti through U was examined. The suitable elsments were determined, and their effects on required centrifuge characteristics were surveyed. The performance of cascades of various aires with different gages was explored, and the cost of a pilot plant program to develop basic separation data was estimated. (F.S.)