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Progress Report Pebble Bed Reactor Program: June 1, 1959-October 31, 1960

Description: From abstract: This report describes analytical and development work in connection with the Pebble Bed Reactor concept. The principle involved in the reactor is the heating of graphite pebbles by the fission of contained uranium and transfer of the heat generated to helium which is circulated through the permeable bed.
Date: July 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)

Description: "An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date: July 30, 1961
Creator: Gehman, William G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrogeochemical Reconnaissance for Uranium in the Stanley Area, South-Central Idaho

Description: Introduction: The purpose of this project was to: (1) investigate the applicability of hydrogrochemical techniques to uranium exploration in the Stanley area; and (2) make a hydrogeochemical reconnaissance survey of the Basin Creek mining district and surrounding area as a step toward evaluation of the uranium potential.
Date: July 1961
Creator: Illsley, Charles T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Test of Buried Structural-Plate Pipes Subjected to Blast Loading

Description: From abstract: Two 20-ft-long 7-ft-diameter 10-gauge structural-plate pipes, having longitudinal joints with eight bolts per foot, were buried and tested in the Smoky event of Operation Plumbbob at predicted pressure levels of 195 and 265 psi. The depth of burial was 10 ft over the crown of the pipe.
Date: July 28, 1961
Creator: Williamson, R. A. & Huff, P. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Internal Conversion Coefficients of the 2+-0+, E2 Transitions in Even-Even Sm152[over]90 and Gd152[over]88

Description: From abstract: "To investigate the deviation of the internal conversion coefficients of E2 transitions from theoretical computations and their dependence on nuclear deformation, the total internal conversion coefficient of the 121.8-kev 2+-0+ transition in ellipsoidal Sm152[over]90 was measured to be 1.135 ± 0.010 with a high accuracy coincidence-sum method. The K-shell to total internal conversion ratio was determined to be 0.588 ± 0.003 with a [beta] spectrometer...The experiment revealed no … more
Date: July 17, 1961
Creator: Lu, D. C. & Schupp, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1961 - June 1, 1961

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Extrusion of Uranium Tubes

Description: Technical report. From Abstract : "Several hundred long, thin-walled uranium tubes were extruded to close dimensional tolerance by a potentially low cost fabrication process in commercial facilities. The principal process steps were; forging uranium ingots, machining the forged ingots into billets, and extruding the billets into tubes. Some 750 tubes (maximum dimensions: 3.5 inches in diameter and 15 feet long) were fabricated by this process. Dimensional control was excellent in that 88% of th… more
Date: July 1961
Creator: Fisher, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Precipitation of Neptunium Peroxide

Description: Technical report. From Abstract : "Optimum conditions were determined for the precipitation of neptunium (IV) peroxide from nitric acid solutions. The results indicate that the precipitation could be applied successfully on a plant scale. ... Two crystalline modifications of the peroxide were prepared; these two crystalline structures were similar to structures previously reported for plutonium peroxide."
Date: July 1961
Creator: Burney, Glenn A. & Dukes, Ernest K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fabrication of Fuel Rods by Tandem Rolling

Description: From introduction: "The purpose of this report is to present the details of the exploratory and developmental work on tandem rolling, and the subsequent fabrication of tandem rolled fuel rods for irradiation testing in the Vallecitos Boiling Water Reactor."
Date: July 1961
Creator: Lingafelter, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Description: Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-2 Full Scale Flow Studies Termination Report

Description: Abstract: Hydrodynamic flow studies were conducted on a full scale model of the SM-2 reactor vessel and core. Test fluid was water at 200 psi and 200 degree F. Test facilities, model, and instrumentation design are discussed. Flow distribution in the stationary fuel elements, lattices, and control rods of the second pass was investigated. Pressure losses through the various core components were measured and are compared with calculated values. Observed over-all pressure drop was 71 feet of wate… more
Date: July 30, 1961
Creator: Christenson, J. A.; Richards, W. M. S. & Davidson, S. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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