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Program Study Report Plutonium Fuel Cycle

Description: From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Radiation Measurements in Conventional Structures: Part 1, Radiation Measurements in Two Two-Story and Three One-Story Typical Residential Structures Before and After Modification

Description: Report discussing the methods, data, and analysis of results for "An experimental study designed to provide a basis for estimating protection against fallout radiation " (p. v) using one- and two-story structures with basements.
Date: July 1966
Creator: Burson, Z. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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
open access

Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments

Description: From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date: July 1963
Creator: Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sample Collector and Counter

Description: From abstract: "An apparatus is described which automatically separates a flow of drops into a series of equal samples."
Date: July 27, 1954
Creator: Deal, James B., Jr. & Buchen, John F.
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

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gas-Cooled Reactor Project Semiannual Progress Report: March 1964

Description: Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project. From summary: "A study was made of the effect of the energy of extraneous source neutrons on the amplitudes of higher modes in the flux distribution of a subcritical reactor."
Date: July 1964
Creator: Oak Ridge National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A

Description: Abstract: The most adverse power distribution and power peaking factors have been developed for Type 3 replacement cores for SM-1, SM-1A, and PM-2A. Also included is the 37 element Type 3 core for SM-1, which is known as SM-1 Core III and is a prototype of a Type 3 core for PM-2A. The power distributions were compared with measured distributions obtained on type 3 fuel elements in SM-1, SM-1A and PM-2A core configurations. Using the measured data as a standard, correction factors were obtained … more
Date: July 25, 1962
Creator: Oggerino, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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