"An apparatus using a silica Bourdon gage is described for the measurement of vapor pressures or dissociation pressures with an accuracy of 0.1 mm and 0.1 deg C up to maximum pressures of atmospheric or beyond and maximum temperatures of 650 to 1250 deg C. The method is applicable to corrosive substances, to substances whose vapor pressure is sensitive to slight changes in composition, and to substances difficult to purify of volatile contaminants which affect the vapor pressure."

"Expressions are found to relate DELTA gamma to the n-errors.'' It is demonstrated that the integral n-value concept'' is of no use in the present case. A modification of integrated n-value'' is suggested."

The general Wigner-Eisenbud theory is used to develop a method of analysis for the cross sections of fissionable nuclei. The method is employed in giving a reasonable description of the low energy cross sections in U/sup 235/. The single level fit for U/sup 235/ is known to be unreasonable. Many level expressions for the cross sections are derived--the only approximation to the general theory being the neglect of all but a small group of resonances. It is shown that regardless of the number or definition of the fission channels the many-level expressions require few level parameters: the E/sub lambda /, GAMMA / sub lambda n/, GAMMA /sub lambda gamma / and GAMMA /sub lambda F/ of the single level theory for each resonance and a few additional parameters pertinent to the interference between levels. The interference terms are described and shown to be important. The shape and size of the U/sup 235/ cross sections below 2 ev are fitied to within one per cent using (a) only one negative energy resonance of smaller size than in the single level fits (b) no additional levels to fit the shape other than the observed levels at positive energies (c) three interference parameters …

This technical report described the formulation of a set of two-group neutron diffusion equations and the solution for the critical fuel cross section in a one-dimensional, multi-region spherical reactor. A subsequent report will describe the ORACLE code developed for survey calculations using this method.

The dose of ionizing radiation received by passengers and crew members traveling on commercial airlines which transport radioisotopes is of interest to all persons who travel the airways frequently. Tariff regulations permit the air transport of 40 units of radioactive materials where one unit represents a quantity of radioisotopes which when packaged delivers a dose rate of one mr/hr at a distance of one meter from the center of the package. Using five different types of commercial aircraft, shipments of radioisotopes were simulated and dose levels determined at various locations in the aircraft under conditions normal to commercial travel. The survey indicates that the tariff regulations should be amended giving consideration to the type of aircraft involved.

An order of magnitude estimate was made to determine a minimum cost for 10% pure oxygen-17 when produced by a chemical exchange process. the calculations were based on separations factors of 1.03, 1.01, and 1.003. the cost of product was found to vary from $23 per gram for the large factor to $165 per gram for the smaller.

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1956, activities, finances, organizational leadership, and other information about scouting programs.

Recent measurements on the long counter efficiency in which comparisons were made with the (n, p) scattering cross section, additional variations in efficiency were found which varied slowly with neutron energy but were still correlated with the total neutron cross section of carbon. Because of these variations in efficiency there are errors in the fission cross sections reported in LA-1714. Corrections to these data have been given here.

The Dumbo space propulsion reactor design concept is described, and the theoretical principles upon which the design is based are developed.

This report addresses the summary report of the Chemical Engineering Division.

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The excellent decontamination performance of the present Purex organic-continuous 2D Column has given impetus to the concept of a two cycle Purex Plant. It is now believed that installation of an organic-continuous HA Column plus certain flow sheet improvements, will put the two cycle process well within our grasp. The increased capacity, flexibility, and lower unit costs furnish the incentive for an early Phase II conversion. This study flowsheet has been prepared for comment, preliminary equipment design studies, and to point out areas requiring further laboratory and cold semiworks testing.

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A simple method is described for producing parabolic mirrors by revolving a horizontal pan of liquid plastic and allowing it to harden into the parabolic shape which has been assumed by the liquid platic. This surface can be plated without further polishing into a mirror of a quality suited to various laboratory and industrial applications.

This section of the Engineering-and Design History presents a comprehensive account of the planning and extensive evaluation of the problems involved in reaching basic decisions for the design and installation of power facilities at the Savannah River Plant. The problems were complicated by the urgency of Pro. viding early start-up of facilities at a time when critical material shortages were acute, combined with basic requirements for reliable operation and unusual degrees of flexibility to meet a variety of production demands. Part I describes in detail the steam and water facilities, alternative schemes, and other considerations which were evaluated as a prelude to the final design of equipment and facilities. Included are discussions relating to steam boiler installations, electric power generation, diesel engine plants, mater supply for cooling, process and domestic use, and the numerous water treatment procedures employed for specific application. A comprehensive description of the development and design of electric power facilities is presented in Part II of this volume.

This bibliography is a compilation of reports on production tests performed in the 300 Area from May 1944 to February 1957. It includes all tests covering engineering and physics experiments in the Hanford Test Reactor development; fabrication and subsequent irradiation of fuel elements and melt plant (slug fabrication) procedures. Subject, author and report number indexes are included. Addendum 1 gives the reactor production test number under which the fuel elements were irradiated.

The description and development, selection and descriptions of processes, design, and specialized design problems are presented for the 400-D Area at the Savannah River Plant. These facilities were used for the production of high purity heavy water for use as a moderator and coolant in the 100 Areas. Also, deuterium gas and hydrogen sulfide were produced here.

This report discusses five Reactor (100) Areas constructed at SRP. They were designated as 100-C, K, L, P and R. A minimum distance of two miles separated any two of the areas which were laid out in the form of a semi-circle, Each area contained approximately 40 permanent buildings and facilities for a total of 200 buildings for all of the 100 Areas. Construction was started on the R Area first and this was the first area to be completed and accepted by Operations. Construction of the other areas was started and completed in the following sequence: P, L, K and C. The difference in the design and construction of the various facilities in these areas is noted under the individual building discussion on the following pages of this section of the Construction History and also in the du Pont Engineering and Design History. In the series of manufacturing operations the separation of fissionable materials produced in the 100 Areas is accomplished by chemical and physical means in the 200 Areas These are the 200-F and 200-H Areas which have duplicate facilities in the process phase. However, a central laboratory, area shops, laundry, metallurgical and storage magazine buildings were constructed …

The primary function of the 300 Area is the production and preparation of the fuel and target elements required for the 100 Area production reactors. Uranium slugs and lithium-aluminium alloy control and blanket rods are prepared in separate structures. Other facilities include a test pile, a physics assembly laboratory, an office and change house, an electrical substation, and various service facilities such as rail lines, roads, sewers, steam and water distribution lines, etc. The 700 Area contains housing and facilities for plant management, general plant services, and certain technical activities. The technical buildings include the Main Technical Laboratory, the Waste Concentration Building, the Health Physics Headquarters, and the Health Physics Calibration building. Sections of this report describe the following: development of the 300-M Area; selection and description of process; design of main facilities of the 300 Area; development of the 700-A Area; design of the main facilities of the 700 Area; and general services and facilities, including transportation, plant protection, waste disposal and drainage, site work, pilot plants, storage, and furniture and fixtures.

This volume provides an engineering and design history of the 100 area of the Savannah River Plant. This site consisted of five separate production reactor sites, 100-R, P, L, K, and C. The document summarizes work on design of the reactors, support facilities, buildings, siting, etc. for these areas.

Results of experimental programs indicate that it might be desirable in the future to modify the existing reactors by replacing the aluminum process tubes with tubes made of a zirconium alloy. The zirconium tubes would be more corrosion resistant than the aluminum ones and would also be stronger at higher temperatures. These new tubes would have the same outer diameter as the present tubes (for ease of handling and in order to provide adequate graphite cooling) but would have a thinner wall (since zirconium alloy is both stronger and more expensive than aluminum). The inner diameter of the new tubes would, therefore, be greater than in the present tubes. In addition to the tube change, it might also be desirable to replace the existing solid fuel elements with those known as ``I&E`` alements. These pieces would be similar to the present elements except for a longitudinal hole which would allow the passage of cooling vater through the center. The element would then be Internally and Externally cooled, and would have a more uniform temperature distribution. The combination of the larger tube inside diameter and the central hole in the fuel element would result in reduced friction loss for the reactor …

Since the issuance of the Purex Phase II flowsheet a number of improvements have been suggested and additional information has been obtained. The purpose of this document is to summarize the more recent information and to bring the two-cycle chemical flowsheet up to date. Later changes will be similarly documented. The Phase II terminology has been dropped as the primary objective of the two-cycle conversion is economy rather than capacity. As mentioned in reference (1), the flowsheet has been designed to best use existing equipment and does not necessarily represent the optimum flowsheet for new plant construction.

This report is written to provide information concerning the status of the Hot Semiworks facility as it is placed in stand-by on July 1, 1957. The plant was constructed in 1951 and early 1952. It vas operated on Redox type investigations until the last of 1953. The plant was then converted to the Purex flowsheet under Project CA 513 D. Operations on the Purex type investigations were started in early 1955 and continued until early in 1956. At that time a maintenance program for plant improvement and repair was initiated. This program was completed on July 1, 1957. Statements are contained in this report which pertain to the present status of physical equipment and facilities and the adequacy, operating experience, recommendations for improvement, previous work, and future considerations of the plant. However, the primary intent of the report is to provide pertinent information to personnel associated with a future start-up. For this reason, certain parts of the report are quite detailed. Only statements concerning the existing or previous state of the facility and equipment are factual. Others are opinions or experiences of plant operating personnel. Emphasis has also been placed on the faults encountered rather than the good features of …