Abstract: This report presents steam cycle optimization studies for large sodium graphite nuclear power generating stations.

Abstract: Pressure stress-rupture specimens of thin walled Type 304 stainless steel tubing have been tested at temperatures to 1300°F in the presence of an internal diffusion limited carbon source.

From abstract: The development, acceptance, and qualification tests performed on the SNAP-10A Ejectable Heat Shield and components, the results of those tests, and the conclusions drawn from the results are presented in this report.

From abstract: The fuel element assembly was successfully irradiated in the SRE to a maximum burnup of 5300 Mwd/MTU, at a peak fission rate of approximately 1.5 x 10E13 fissions/cm3-sec and a maximum central temperature near 1200F.

From abstract: A series of three multi-compartmented experiments was designed to investigate the irradiation behavior uranium carbide fuels, as a function of composition, temperature, and burn-up; and the mechanical properties of Type 304 stainless steel, as a function of temperature and integrated thermal neutron flux.

Data collected as part of a report on the Sheridan Wyoming Quadrangle including laboratory data on waters (pp. 1-22) and sediments (pp. 23-52) as well as field data (pp. 53-115).

Data collected as part of a report on the Kateel River, Alaska quadrangle including both laboratory data (pp. 1-24) and field data (pp. 25-60).

Data collected as part of a report on the Alliance Quadrangle in Nebraska and South Dakota including laboratory data on well water and stream sediments as well as field data.

Data collected as part of a report on the Raton New Mexico quadrangle including laboratory and field data on waters and sediments.

Data collected as part of a report on the Roundup Quadrangle in Montana including laboratory data on waters (pp. 1-46) and sediments (pp. 47-100) as well as field data (pp. 101-223).

This is the thirty-seventh progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress during the period of June 1, 1955 through August 31, 1955 is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) Elementary particle scattering group, (6) neutron physics group, (7) ONR generator group, (8) Radioactivity group, (9) Cyclotron group, (10) Synchrotron group, (11) Theoretical group, (12) Personnel listing.

From introduction: This report details the extensive modifications to the SRE heat transfer systems required to accomplish increased capacity objectives.

Abstract: Field and laboratory data are presented for 1,263 water samples and 961 sediment samples from the Roundup Quadrangle, Montana. The samples were collected by Los Alamos National Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

Abstract: Field and laboratory data are presented for 582 water samples and 526 sediment from the Sheridan Quadrangle, Wyoming. The samples were collected and uranium analysis performed by Los Alamos National Laboratory; multielement analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

Abstract: Field and laboratory data are presented for 776 water samples and 1,333 sediment samples from the Raton Quadrangle, New Mexico. Uranium values have been reported by Los Alamos National Laboratory in Report GJBX-138(78). The samples were collected by Los Alamos National Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

Abstract: Field and laboratory data are presented for 616 water samples from the Kateel River Quadrangle, Alaska. The samples were collected by Los Alamos National Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee.

From abstract: Results of a reconnaissance geochemical survey of the Alliance Quadrangle are reported. Field and laboratory data are presented for 543 groundwater and 523 stream sediment samples.

From abstract: Results of a reconnaissance geochemical survey of the Lubbock Quadrangle, Texas are reported. Field and laboratory data are presented for 994 groundwater and 602 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.

"In the following report, a new technology is discussed which was first proposed in 1959, but which has been developed mainly since 1964; the in situ production of oil from shale by large underground retorts created by nuclear explosives. The first part of the present report describes this new process; the second part gives an analysis of the United States and the world endowments with crude oil resources and oil shale deposits and finally, the third part deals with expected cost estimates of this new technology as compared with present crude oil prices and potential costs of conventional shale oil production."

Summary: "Water containing 1.8% D2O was distributed between the two liquid phases formed with triethylamine at 20 and 35 C. The triethylamine was removed from each phase by aseotropic distillation with benzene before analyzing the water by determining its density with a quartz float. The ratios of the concentrations of the D2O in the water layer to that in the amino layer were 1.007 and 1.004 at 20 and 35, respectfully. The differences from unity are about the same as the errors of analysis."

Final report on research and development on fabrication of pin and lid detectors and the dry run interface system.

Annual report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the 1965-66 fiscal year.

The purpose of this experiment is to study the quantitative adsorption characteristics of a carbon adsorber bed receiving a radioactive inert gas in a helium stream. An objective of the experiment is to measure the equilibrium transmission of the radio-active gas through a carbon adsorber in order to determine if radio-active decay of the adsorbed gas permits additional adsorption.

Tests were conducted to determine the friction factor of randomly packed beds of 3/4-inch diameter spheres in 8-inch and 15-1/4-inch diameter beds, and of 1-1/2-inch diameter spheres in 15-1/4-inch diameter bed. The bed depths were varied in an attempt to isolate the effects of entrance and exit losses. The bed Reynolds number, base on sphere diameter, was varied from 5,000 to 50,000.