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Metallurgy Division Annual Progress Report, July 1, 1960

Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: September 30, 1960
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Partner: UNT Libraries Government Documents Department
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Solid State Division Quarterly Progress Report: August 1952

Description: This quarterly progress report discusses the ongoing work within the Solid State Division at the Oak Ridge National Laboratory for the period ending August 10, 1952. Projects discussed include radiation metallurgy, engineering properties, fused salts, crystal physics, and solid state reactions.
Date: January 30, 1959
Creator: Billington, D. S. (Douglas S.) & Howe, J. T.
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951

Description: This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.
Date: September 30, 1951
Creator: Lind, Samuel C., (Samuel Colville), 1879-1965; Boyd, G. E. & Bredig, M. A.
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Quarterly Progress Report for the Period Ending January 31, 1951

Description: Technical report outlining the construction progress of the Oak Ridge digital computer at Argonne. Included is the schedule of events for the Mathematical panel and programs during the presentation of contributed papers for the Biometric Society [From Summary]
Date: March 30, 1951
Creator: Householder, A. S.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Experiment Quarterly Progress Report for Period Ending November 30, 1950

Description: Technical report acting as a detailed progress report on all homogeneous-reactor-motivated work at the Oak Ridge National Laboratory (ORNL). Includes work of the Homogeneous Reactor Experiment, the long range research programs associated with aqueous-fluid fuel systems. [From Foreword]
Date: January 30, 1951
Creator: Winters, C. E. & Secoy, C. H.
Partner: UNT Libraries Government Documents Department
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The Shielding of Mobile Reactors - [Part] 2

Description: From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, ar… more
Date: June 30, 1952
Creator: Blizard, E. P. & Welton, T. A.
Partner: UNT Libraries Government Documents Department
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Second and Third Operating Test of HRT Core Vessel Transition Joint and Expansion Bellows Mockup

Description: Second and third tests were conducted on an expansion bellows and Zircaloy-stainless steel transition joint assembly, duplicating that used in the core-pressure vessel assembly of the HRT. The assembly was exposed for 1140 hours in the second test and and 167 hours in the third to a solution containing 0.04m UO2SO4, 0.02m H2SO4, and 0.005m CuSO4 in a 100A dynamic corrosion loop under conditions simulating reactor startup, shutdown, and steady-state operation. Results indicated that the transiti… more
Date: April 30, 1957
Creator: Greeley, R. S.; Ulrich, W. C.; Savage, H. C.; Griess, J. C. & Mauney, T. H.
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Corrosion Group for the Period Ending April 30, 1957

Description: A third test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel was completed. No additional mechanical deflections of the bellows were made, but 12 additional thermal cycles of the unit were carried out. . The joint and bellows functioned properly and were leak-tight. Corrosion of stainless steel in 0.04 m UO2SO4 containing equimolar beryllium sulfate was not greater at 10-15 fps and much less at 15-75 fps, than in HRT solution at 200 and 225 C. … more
Date: April 30, 1957
Creator: Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Partner: UNT Libraries Government Documents Department
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Heat Transfer in Septafoil Geometries by Mass-Transfer Measurements

Description: In conjunction with Gas-Cooled Reactor heat-transfer studies, local and mean heat-transfer factors are predicted from the heat transfer-mass transfer analogy using subliming naphthalene in air. Experimentation was conducted on 1-in.-dis septafoil rods in a 4-in. -dis flow channel with rod center-to center spacings of 1.10, 1.25, and 1.40 in. at a Reynolds modulus of approximately 60,000. Ratios of local mass transfer to mean mass transfer for a given rod vary as much as from 0.7 to 1.3 (outer r… more
Date: June 30, 1959
Creator: Wantland, J. L. & Miller, R. L.
Partner: UNT Libraries Government Documents Department
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Ion Energy Distribution, Energy Degradation, and Exponentiation Criteria in a Plasma Formed by Beam Trapping and Charge Transfer

Description: An approximation is derived for the time constant which characterizes the rate of energy loss of fast ions moving through a plasma. Using particle and energy-balance equations a simple approximate criterion is derived for the estimation of the importance of energy degradation during plasma buildup in a DCX type machine. Next, there is derived the steady-state ion energy distribution for a case in which energy losses are to electrons at a given temperature and particle losses are by charge excha… more
Date: September 30, 1960
Creator: Rose, D. J.
Partner: UNT Libraries Government Documents Department
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Radioactivation Analysis

Description: The development of nuclear reactors and other nuclear particle sources has given the analyst a new analysis method which can be successfully applied to the determination of microgram and submicrogram quantities of many elements. Known as "radioactivation analysis", this method is one in which an "activation" by some type of nuclear reaction is used to produce a radioactive isotope of the element to be determined. Since this radioisotope decays with its own characteristic radiations and half-lif… more
Date: November 30, 1960
Creator: Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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Steady-State Radial and Axial Temperature Profiles of an E. G. C. R. 5 1/2" O. D. Through Tube During 1500 KW Operation - Part II

Description: The steady-state radial and axial temperature profiles of an E. G. C. R. 5 1/2" O. D. through tube are determined for the test condition of an attemperated fuel assembly operating at 1500 KW in the loop. The profiles are determined for the case of the central control rod fully inserted and bank insertion to 62 inches (Δk = 0.025). The data are presented in the form of tables and curves.
Date: December 30, 1960
Creator: Noggle, L. W.
Partner: UNT Libraries Government Documents Department
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Status Report on the Pneumatic Temperature Measuring system Studies for the EGCR

Description: The pneumatic temperature probe (PIM) is a device for measuring gas temperatures by utilizing the dependency of the flow of gases through a restriction on the temperature and pressure conditions. The determination is made by measuring critical mass flow across a restrictive element such as a nozzle and by knowing the upstream pressure and other variables pertinent to the critical flow equation, computing the temperature at the entrance to the restrictive element. In practice it has been found u… more
Date: December 30, 1960
Creator: Hochreiter, H. M.
Partner: UNT Libraries Government Documents Department
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