Report on the atomic bomb injuries in Hiroshima City.

From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."

Abstract: Reconnaissance of Red Rock Valley was begun on December 10, 1953, and completed on February 11, 1954. The mines in the region were investigated and all exposures of Salt Wash were walked. Paleostream directions and alterations of the sandstones were observed and recorded on a base map. No important new mineralization was discovered-and the area is considered to be of no commercial significance if judged by the outcrops alone. However, a vast amount of Salt Wash lies at slight depth directly to the east of the investigated area.

From introduction: During the summer of 1951, Navajos conducted John W. Chester, Russell C. Cutter, and E. V. Reinhardt, Grand Junction Exploration Branch, U. S. Atomic Energy Commission, to a copper deposit in Copper Canyon. Little radioactivity was noted, and no further work was done in the area at that time. In October 1951, the same group of Navajos reported the discovery of uranium ore in another portion of the same area. The site was visited by Cutter who noted that an excavation made by the Navajos had disclosed a 3-foot thickness of low-grade uranium ore. In November 1951, Cutter again visited the area and observed that the Navajos had opened a 5-foot face of good ore.

Abstract: Ten days were spent during June 1955, examining the sedimentary rocks along the San Juan and Colorado Rivers between Mexican Hat, Utah, and Lee's Ferry, Arizona. The most favorable area for uranium deposits occurs in the Shinarump member of the Chinle formation between Clay Hills Crossing and Spencer Camp along the San Juan River. Mineralization is spotty and deposits are small and almost all below ore-grade. Only one small mine, the Whirlwind, is currently producing ore. Gray-green alteration of the underlying Moenkopi is moderately developed in the vicinity of the Whirlwind mine; elsewhere alteration is weakly developed.

From introduction: This report details the results of the post-irradiation examination of a test involving one defected rod and one undefected rod.

Abstract: The technical feasibility and economic potential of fast breeder power reactor systems cooled with boiling mercury have been investigated by American-Standard under the United States Atomic Energy Commission's New Reactor Concepts Evaluation Program.

From abstract: This paper presents temperature-entropy and Mollier charts for sodium, and describes briefly the method used for their construction, based upon data from the literature.

Introduction: Reconnaissance for uranium in central and southwestern Arkansas was carried out as a joint project of the U.S. Atomic energy Commission and the U.S. Geological Survey during March and May 1954. The project was planned as an investigation of several areas of known abnormal radioactivity, and as a search for others, by airborne and ground radiometric reconnaissance.

Report discussing the distribution of mass in the spontaneous fission of Cm²⁴², which was investigated by a radiochemical determination of the fission yields of twenty-one nuclides ranging in mass from 91 to 140. "Corrections for absorption, scattering, geometry, decay, and fractional saturation were applied to obtain saturation disintegration rates, which, with the known fission rate of the source, give the fission yields."

Report discussing a procedure for the preparation of anhydrous vanadium trifluoride. From abstract: "By selecting proper operating conditions and equipment, a method of preparation was devised such that anhydrous vanadium trifluoride of high purity was produced reliably in five pound batches." The method of preparation involves manipulating the starting material, vanadium pentoxide.

The following report describes the process of the determination of hydrogen in magnesium, lithium, and magnesium alloys, including methods of analyzing magnesium-lithium alloys for hydrogen, and the tin-fusion method used for determining the hydrogen content of pure magnesium that can also be used to analyze pure lithium for hydrogen.

Report discussing the progress made on the Experimental Breeder Project during the period from March 1, 1949 to January 31, 1950.

From abstract: "This report outlines a method for selecting materials including alloys for use as a structural member in a neutron flux based on its thermal neutron absorption properties."

Report exploring qualities of tapered pile cooling streams and replying to suggestions on the arrangement of pile cooling streams.

This report will summarize what has been done and present the interpretations made at this stage of the program.

Gamma plutonium is found to be orthorhombic with eight atoms in a unit cell of dimension (1t 235 degree C) [formula]. The calculated density is [formula]. The space group is Fddd and the positions of the eight atoms are: [formula]. Each plutonium atom is bonded to ten others at an aver distance of [formula], four being at [formula], two at [formula] and found at [formula]. The mean linear coefficients of thermal expansion are found to be [formula].

Data which determine points on the Hugoniot curves of fourteen solids are given in the technical report.

Calculations are developed which indicate the Pu production is an infinite lattice

A complete investigation was made of the r-f field in the 1/10-scale Materials Testing Accelerator (Mark I) cavity

Abstract: A survey of the problem of reactor system contamination by radioactive material and methods that have been employed to remove the material was carried out. Following this survey, an investigation of chemical solutions was undertaken to find one which might be successfully employed in the decontamination of a stainless steel steam generator. From a preliminary screening, the most promising chemical method from the view point of minimum corrosion and maximum decontamination is a caustic permanganate treatment followed by and acid rinse.

Abstract: A decontamination procedure for a stainless steel steam generator similar to the APPR-1 using a fill-flush application of a caustic permanganate-citrate combination solution is recommended. The isolation of the steam generator is to be accomplished by means of specially designed plugs at the reactor vessel outlet and at the primary coolant pumps. Anticipated results, including corrosion rates and decontamination factors, are presented.

Technical report describing results on work which cannot be ascribed to one reactor program. Outlines the results of miscellaneous corrosion testing, the development of new shielding materials, the testing of irradiated plastics, and general heat transfer investigation. [From Preface]

Processing of Florida leached zone material for the recovery of alumina.