This report contains a description of the reactor plant portion of the Enrico Fermi Atomic Power Plant, with emphasis on the reactor system. Since this plant contains a developmental reactor, emphasis has been placed on reactor safety and on achieving reliable operation. The design is conservative and is flexible enough to permit incorporation of the results of developmental programs, which include nonnuclear, full-scale component test facility operations, and nuclear experiments, such as critical experiments.

Introduction: The purpose of this report is to describe in further detail the control systems that interconnect the SRE with the steam plant.

Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.

The following report is meant to review the characteristics of airborne particulate contamination matter, which sets it apart from other phases of the radiation control program and make it necessary to apply to it different concepts, analytical procedures, and control measures.

Introduction: The Ambrosia Lake area includes all of T. 14 N., R. 10 W., and portions of adjacent townships in McKinley County, approximately 20 miles north of Grants, New Mexico (fig. 1). Uranium was discovered in April, 1955, and extensive exploration drilling followed.

Abstract: In the event of a massive nuclear attack, the combined fallout from quantities of surface-burst nuclear weapons must be considered as a serious hazard over an extended area. This report presents one method for rapidly estimating the fallout from such an attack.

Progress report includes reports on (1) The isolation of pyrimidine deoxynucleotides from the acid-soluble fraction of thymus; (2) Non-specific protective effect of small lead shields against the lethal effects of whole body irradiation in the rat; (3) Strain differences in response to whole body irradiation and shielding procedures in the rat; (4) Renal clearance procedures in an evaluation of the effects of X-irradiation on renal function in a rat. A preliminary report; (5) The plasma erythropoietic stimulating factor. Observations on circulation erythrocytes and bone marrow of rats receiving protein-free extracts of rabbit plasma; (6)Additional observations on the plasma erythropoietic stimulating factor; (7) Studies on Trichinella Spiralia, VI-IX. (8) Effect of gamma radiation on infectivity of ascaris eggs. (9) Preliminary report of studies on taeniasis. (10) Studies on the role of labile humoral factors in irradiation injury. (11) Services of the Radiation Physics Unit. (12) Biological and physical effects of low energy monochromatic X-rays.

A simple mechanical calculator has been developed for solving the transmission line equations when the characteristic impedance is a variable. The speed of computation is some two orders of magnitude faster than analytical methods. The theoretical basis is described and also the way in which it can be used. Some representative problems, which have benefited by us of the calculator, are discussed.

A circuit had been constructed which supplied timing pulses for the various operating components of the UCLA F.M. cyclotron as well as counter gating pulses of variable widths and adjustable positions on the cyclotron duty cycle. The pulses are timed relative to a master pulse generated when the cyclotron oscillator passes through a specified frequency in the direction of decreasing frequency, thus giving only one master pulse per duty cycle. Overall stability of the timing circuit is about one mu sec.

The purpose of this manual is to help an engineer or scientist to design a practical shield by making available to them the techniques and data developed by the Naval Reactors Program and Pressurized Water Reactor Program.

The following quarterly report is the third in a series that discusses the investigation on the production of purified graphite through the use of self-purifying raw materials, covering the period of January, February and March of 1952.

Abstract: "A process for the extraction and depoisoning of uranium in strong phosphoric acid solution with tributyl phostphate (TBP) is described. The formation of a complex between uranyl and phosphate ions necessities the use of a salting agent which is capable of destroying this complex and releasing the uranyl ion into an organic extractable species. Of various salting agents tried, ferric nitrate was the most successful. It not only provides nitrate ion for the formation of uranyl nitrate but also forms a very stable ferric-phosphate complex, thus completely tying up the phosphate ion when added in equi-molar quantities. Stripping of the enriched solvent is accomplished with phosphoric acid."

A report about the experimental facilities and equipment belonging to A.E.C. and on the property of Great Lakes Carbon Corporation at Morton Grove, Illinois which have been reconditioned and repaired.

Instruction book for the DR Dolly. "The DR Dolly is a unit which is designed to perform various mechanical operations which a man would otherwise perform if he were able to work safely in the area where the Dolly is to operate. It consists of six mechanical components mounted on a steel car which in turn runs back and forth on rails. The car simply forms a movable platform for the following components, which are: a 36" mirror, a mechanical arm and various hands, two valve turners, a ram, and a nozzle remover."

This report follows a procedure for the tests on oxidized fractional precipitation process on "unreduced" uravan acid leach "A" liquors.

Abstract: "A method has been developed for observing the "fine structure" of neutron flux distribution. Difference in neutron flux in regions a half a millimeter apart have been measured. Examples in which this resolution has been useful are given. In the case of a polythene ball, three-fourths of an inch in diameter, in the center of the Little Eva reactor, the effective neutron flux varies 75% of the unperturbed value between two readings a tenth of an inch apart."

Report discussing methods for recovering hafnium-free zirconium from irradiated fuel elements. Two methods are discussed: the fluoride method and the Zircex method. Experimental procedures to evaluate these methods and their results are presented.

From introduction: "The study's objectives were to determine the approximate rate of general corrosion so as to reveal; any abnormal corrosion occurring during processing operations; to determine the suitability of a large variety of alloys and plastics as materials of construction; and to ascertain process conditions which would minimize corrosion."

Abstract: "The development of a portable battery-operated instrument capable of detecting a short-circuit four or more inches from the hot junction of a five-foot-long thermocouple is described. The accuracy of measurement is inversely proportional to the length of the thermocouple and is not affected by changes in thermocouple temperature. A signal having a wave length much greater than the electrical length of the thermocouple is used to measure thermocouple inductance. The instrument consists of a radio-frequency ocillator, a bridge, five stages of amplification, and a director. Theoretical considerations are presented in support of a radio-frequency measurement."

The following report describes a method used to obtain hydrogen content of uranium metal.

Abstract: "The initial product formed on relatively oxide-free uranium has been shown by electron diffraction to be the alpha or low temperature form of uranium hydride. Such as oxide-free surface has been prepared by polishing the metal within the electron diffraction unit while maintaining a vacuum of 10^-7 mm Hg. Uranium dioxide lines appear later and grow in intensity. Electron diffraction studies are reported on vacuum annealed metal."

Abstract: "Thorium is separated from uranium, titanium and tungsten by precipitation as fluoride. The precipitate is ignited to oxide, dissolved in nitric acid, evaporated with perchloric acid, neutralized to a pH between 2.0 and 2.5 and titrated with the disodium salt of ethylene-ddiamine tetrascetic acid, using Eriochrome Cyanide as indicator. If less than 30 milligrams of thorium is present, lanthanum is added as a carrier."

The following report describes a critical metal assembly that has a cylindrical core of uranium with an average U-235 concentration of 16-1/4% and a 3 inch reflector of natural uranium.

Abstract: "Uranium monocarbide-Zircaloy II alloy cermets were developed and tested for chemical and physical properties. It was determined that pure uranium monocarbide can be prepared by vacuum are melting techniques. Following melting, the combination, hot pressing, and corrosion behavior of dense monocarbide has been studied. The preparation of uranium monocarbide-Zircaloy II cermet bodies was investigated by means of hot pressing, cold pressing and sintering, warm pressing, extrusion, and hot rolling. The corrosion resistance of the cermets was related to such variables as composition, preparation technique, and powder size. 01 per cent uranium monocarbide, 70 per cent zircaloy II cermets withstood corrosion tests in 680 F water. Cermets having above 30 weight per cent uranium monocarbide were not corrosion resistant."