Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Radioactive debris from nuclear detonations may fall out over an extensive area. A rapid evaluation of the distribution of such surface contamination cam be obtained by an aircraft mounted detector. The gamma field measured in the aircraft can be related to the intensity on the ground. The HASL Top Hat'' system measures the radiation intensity, in an aircraft, at any altitude up to 1500 feet. The data are continuously compensated to the reading that would be obtained if the measurements were taken at three feet from thc ground surface. It will record the ground radiation field intensities from 0.01 mr/hr to 1000 r/hr. The Telepulse Coding Unit converts this information to a signal suitable for transmission to a plotting center via a standard voice radio transmitter. The transmitted signal is decoded by a Telepulse Receiving Unit and is automatically recorded on a strip chart. The radiation data must be correlated with the aircraft position to determine the location amd intensity distribution of the contaminated area.

From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."

Summary: A study has been made of possible processes for the production of hafnium-free zirconium of a grade suitable to meet AEC specifications.

From to the files: The Shinarump-Moenkopi contact on Oljetoh Mesa in the Monument Valley district, Arizona-Utah, was examined from November 5 to 15, 1951, to determine the location of and the mineralization in Shinarump channels. Twenty-seven distinct channel outcrops were located and examined. Three of these channel outcrops are mineralized and the remaining 24 are barren. Plate I shows the distribution of the Shinarump, the Moenkopi, and the DeChelly member of the Cutler formation; the location of the Shinarmp channel outcrops; the channel trend where there is good evidence for such a trend. The Hoskinrnini tongue of the Cutler was mapped with the Moenkopi as it is not a good mappable unit in this area. The three mineralized outcrops are indicated by the letters A, G, and AA while the barren outcrops bear the letters B to F and H to Z.

From introduction: The purpose of an airborne radioactivity survey is to locate ground areas of higher than normal radioactivity which might lead to discovery of uranium mineralization. For this type of survey, gamma-ray detection equipment employing either a geiger counter or a scintillation counter can be mounted in a fixed wing aircraft or a helicopter.

From operational program: This final report includes a general geologic description of the area, including descriptions of the various geologic units and correlates the airborne data to the geologic units as provided by the geologic maps. Also included is a frequency distribution study of the data as a function of the geologic units encountered over the NTMS area including the tie line data.

From introduction: This is the final report on uranium carbide studies sponsored by the United States Atomic Energy Commission and performed by United Nuclear Corporation at its New Haven Research Laboratories during the period from May 1959 to January 1964. The work was part of the Commission's Fuel Cycle Development Program aimed at lowering the cost of nuclear power by improving fuel cycle technology. At the inception of this program in 1959, some work was in progress on uranium carbide. Little was known of making a satisfactory fuel in quantity or of how it would perform either in-pile or out-of-pile. The United Nuclear program was designed with no specific reactor in mind and was aimed at furnishing information over a broad spectrum.

From operational program: This final report includes a general geologic description of the area, including descriptions of the various geologic units and correlates the airborne data to the geologic units as provided by the geologic maps. Also included is a frequency distribution study of the data as a function of the geologic units encountered over the NTMS area including the tie line data. This report also consists of a discussion of the area surveyed and includes all single record reduced data and averaged record data listings on microfiche.

"An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure at a higher temperature resulted in an increase in the thermal conductivity. The converse was also observed. Within the precision of measurement there was no difference in effed between temperature changes produced by varying the fission rate in the samples and changes produced by varying the power in an external heater."

Abstract: "Two transistor plug-in decade counters are described, one of which operates over the SCS-7 temperature range. A transistor digital scanner with storage and parallel readout is described. It utilizes one of the plug-in decades. A simple design procedure for flip-flops is presented."

From abstract: The PT-750 is designed to be used in conjunction with a production tester which requires automatic recording of test data. This manual provides a source of procedures and reference material necessary in automatic recording and in use of the PT-750.

Data collected as part of the Douglas Quadrangle in Arizona including laboratory and field data on waters and sediments.

Data collected as part of the hydrogeological and stream sediment reconnaissance for the Sherman NTMS quadrangle including laboratory data on well water and stream sediments as well as field data.

This report discusses the problem of obtaining thermonuclear temperatures as part of reaching a controlled fusion reaction for fusion power. Tables covering radiation losses and thermonuclear reaction rates are included. Talk before JCAEC in Washington, D. C.

Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."

From abstract: Results of a reconnaissance geochemical survey of the Lincoln Quadrangle are reported. Field and laboratory data are presented for 577 groundwater and 754 stream sediment samples. Statistical and areal distributions of uranium and possible uranium-related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed.

Abstract: Field and laboratory data are presented for 161 water samples and 235 sediment samples from the Douglas Quadrangle, Arizona; New Mexico. Uranium values have been reported by Los Alamos National Laboratory in Report GJBX-69(78). The samples were collected by Los Alamos National Laboratory; laboratory analysis and data reporting were performed by Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

Abstract: Results of a reconnaissance geochemical survey of the Sherman Quadrangle, Texas; Oklahoma are reported. Field and laboratory data are presented for 718 groundwater and 715 stream sediment samples. Statistical and areal distributions of uranium and possible uranium related variables are displayed. A generalized geologic map of the survey area is provided, and pertinent geologic factors which may be of significance in evaluating the potential for uranium mineralization are briefly discussed.

Abstract: This discussion concerns the operation, construction, and servicing of an alpha rate meter of medium sensitivity (30,000 alpha particles full scale per minute) and good stability. The instrument is equipped with an oscillator which increases both in frequency and loudness as the alpha activity is increased. The oscillator circuit includes an anticipator which causes a change in frequency depending directly upon the rate of change of alpha activity. Maximum sensitivity is approximately 100 millivolts full scale. Grid current varies from 1 to 5 x 10^-14 amperes. A general discussion of time constants and accuracy is included. Tables of stopping power, ionization and alpha activity are appended.

Data listings from the area surveyed in a report on Winnemucca in Nevada including single record reduced data listings.

Abstract: The experimentally determined exponential dependence of spontaneous fission rate on Z^2/A has been used to derive an expression for the dependence of the fission activation energy on Z^2/A. This expression has been used to calculate the activation energy for slow neutron induced fission and photofission. The correlation with the experimental data on these types of fission seems to be quite good.

The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.