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.

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

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.

Data collected as part of a hydrogeochemical and stream sediment reconnaissance for the Lincoln NTMS quadrangle in Kansas and Nebraska including laboratory data on well water and stream sediments as well as field data.

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.

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.

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.

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.

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

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

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 introduction: "Cytological examinations of the irradiated and some unirradiated populations in the radioactive sediments of White Oak Creek and the Clinch River were made."

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.

Abstract This technical report covers the thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss of flow transient results indicate DNBR's above 1.5, insuring that the core is safe from burnout. Bulk boiling was noted in the hot channels and lattice passage at scram power condition.

"The influence of compressive creep on the self-diffusivity of α-iron has been measured in the temperature range of 742-885°C. the diffusivity is enchanced in proportion to the strain rate, but this dependence decreases with increasing temperature. The magnitude of the strain is relatively unimportant in this connection. Strain rates from 0 to -2 x 10¯³ sec¯¹ were investigated with a corresponding increase in diffusivity up to 3 x 10³ times. The results are analyzed in terms of vacancy diffusion and the excess vacancies introduced during deformation. It is concluded that grain boundaries are the main vacancy sinks in polycrystalline iron and that the vacancy lifetime is therefore dependent on the grain size."

Report documenting results of a study of the cause of failure at the SPERT III reactor facility.

Abstract: This technical report presents design criteria to prevent the brittle fracture of ferritic reactor vessels that cold occur as a result of the rise in NDT caused by fast neutron irradiation. The criteria require that maximum principal stress in the vessel does not exceed 18 percent of yield stress at temperatures below NDT + 60 degree F. Under certain conditions the allowable stress may be based on the irradiated yield stress. A discussion of brittle fracture and an explanation of the criteria are included.

"The purposes of the program being conducted under the present contract are: 1) To determine the feasibility of cladding zirconium on uranium by a direct casting process. 2) To investigate the diffusion of liquid metals in the fusion zone."

From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."

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.

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."

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.

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.

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."