Several theories of metal creep and radiation damage are studied, in order to determine whether creep rates under various conditions of irradiation can be predicted theoretically. It is found that if the creep is of the recovery type, and if the diffusion coefficient for radiationinduced vacancies is large enough, creep rates may be increased within a limited temperature range. Otherwise, radiation has no effect on creep rates. (T.F.H.)

Geologic and radiometric investigations of the CuzcoAyaviri region in southern Peru were made in a search for geologic features or structures which might be favorable for the occurrence of uranium. Outcrops consist of Lower Paleozoic sedimentary and metamorphic rocks; Permian to Carboniferous volcanic flows, tuffs, breccia and agglomerate, together with sedimentary rocks; and Cretaceous and sedimentary rocks. Cretaceous to Tertiary igneous rocks are acidic intrusives and extrusive rhyolite, dacite and trachyte. Tertiary to Quaternary volcanic tuffs, breccias and agglomerates are also present. Although no anomalous radioactivity was observed, favorable geologic features for the occurrence of uranium were noted at two localities. (auth)

In 1957 a radiometric examination of rock outcrops in the Ayabaca and Huancabamba areas of northwestern Peru was made in conjunction with a geologic search for structures favorable for the occurrence of uranium minerals. No anomalous radioactivity was detected, and the geologic setting is believed to be generally unfavorable for uranium mineralization. (auth)

From abstract: This report describes a conceptual design for an Advanced Engineering Test Reactor. The reactor is a large graphite assembly penetrated by parallel Zircaloy tubes through which flow as heavy water solution of uranyl sulfate. Reactor power is 220 megawatts.

Data were obtained to evaluate the attenuation of photons, emitted from a fallout field, due to the surface roughness of the terrain. A study was made to determine the effect of the shot tower on the fallout material. Particles for comparison were collected from two detonations of equal scaled height, one tower supported and the other balloon supported. Data on time-dependent phenomena were recorded, as were physical characteristics of the fallout material. The use of small balloons as instrument platforms and a new fallout collector were evaluated for field use. No conclusions or recommendations can be made at this time.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: The liability of the Dallas County Hospital District for negligent acts of its employees and the authority to purchase public liability insurance.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: In building projects which are designed by the Board for Texas State Hospitals and Special Schools, is the exclusive authority and duty to enter into the building contract on behalf of the State vested in the Hospital Board or in the Board of Control? And related questions.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Would it be illegal for a College Cafeteria to buy milk from a member of the Legislature who owns Dairy?

Report discussing interactions of 420-Mev/c K- mesons incident on a nuclear emulsion stack. Information on the differential scattering, elastic scattering, absorption events, and inelastic scattering of the mesons is provided. Additionally, the ratio of Λ to Σ hyperons produced in the primary interaction is calculated.

"An experimental study has been made regarding the passage of a beam of 100-kV ions (H⁺ and H₂⁺) across a magnetic field by means of a crossed electric field." This experiment was designed to answer the following questions: "(1) Is there a limit to the current that will traverse a magnetic field by the action of a crossed electric field? If so, what is the limit? (2) Do difficulties arise in maintaining the electric field? (3) For the source employed, what is the angular divergence and current density of the beam?"

Abstract: "Experimental evidence is given which indicates that electronic bombardment is responsible for damage and failure of insulating material subjected to intense corona attack. The experimental revolts are further supported by some theoretical considerations of the energy-time properties of corona discharges."

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 …

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.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority of the office of the Secretary of State to accept and file the charter of a proposed corporation containing a stated purpose clause.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Authority to pay travel expenses to persons assigned to the Board of Insurance Commissioners to attend courses offered by the International Business Machines Company.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Taxability under the Texas Unemployment Compensation Act of payments into or from Supplemental Unemployment Benefit Plan Funds of the Ford Motor Company - UAW-CIO type.

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 …

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

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

To estimate the distribution of temperature in the proposed nuclear reactor, one must determine a coefficient of eddy diffusivity and devise a suitable method of computing the heat transfer. Measurements of diffusion in a model of a blanket element for the proposed reactor indicated a gross eddy diffusion coefficient of about 0.002 (? .0005) ft{sup 2}/sec. Thus, the apparent eddy diffusion for the test conditions is about 200 times the molecular diffusivity of water and about. twice that of the liquid sodium. Even approximate methods of applying this result require an elaborate calculation if the primary characteristics of the flow system are to be taken into account. The dispersion of dye in flowing water provided an indication of the diffusion in the model tests. The presence and arrangement of the rods, the effect on the flow?of the spiral wire spacers, and the existence of a comparatively large area on which a laminar sub-layer develops made it impossible to get simple turbulence criteria like those obtained downstream from a screen. Although the results are consequently somewhat unsystematic, they do establish reliably the approximate magnitude of the coefficient of eddy diffusivity. The data were obtained from both line and sectional traverses, the …

Losses have been determined for flow through models of various proposed core sub-assemblies as part of a study of the elements of a nuclear reactor. Six core sections and two? axial blanket sub-assemblies have been compared on the basis of drop in piezometric. head or pressure drop. The core sub-assemblies are composed of an entrance nozzle, a lower axial blanket section, the core section, an upper axial blanket section, and a short section for the handling lug. The four parts of the sub-assembly other than the core section are designated as the axial blanket sub-assembly. In each core section there are 144 rods within a container which has a square cross-section. The primary differences between one core section and another are the means qf supporting and spacing the rods. Bars or wires wrapped in spirals around the rods were used as well as a series of grids made up of wires and supported at the four corners. Also, in one core an, inner wall was used to provide an annular flow passage which helps to reduce the difference in temperature at the inner and outer walls of the core. The two axial blanket sub-assemblies tested are similar except ?that the …

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 …