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A Preliminary Survey of Radioactive Constituents in Rainwater at ORNL

Description: Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]
Date: December 4, 1950
Creator: Booksbank, W. A., Jr.; Emmons, A. H.; Gost, J. W. & Reynolds, S. A.
Partner: UNT Libraries Government Documents Department
open access

Core Levitation in the EOCR in Case of Main Coolant Pipe Failure

Description: This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will pr… more
Date: August 4, 1959
Creator: Fontana, M. H.
Partner: UNT Libraries Government Documents Department
open access

Unit Operations Section Monthly Progress Report June 1959

Description: The addition of a surface active agent to an aqeous-organic interface produced a resistance to mass transfer equivalent to slightly more than 1 cm of water. Five semicontinuous Druhm runs were made with 1/2in. thick MgO liners and terminated due to either failures of the UFe nozzle or a top gasket leak. In preliminary scale-up tests of the flame calcination equipment, a maximum feed rate equivalent to 720 g oxides/hr was achieved using a 3-in. i.d. magnesia reflector with an outside wall temper… more
Date: September 4, 1959
Creator: Bresee, J. C.; Haas, P. A.; Watson, C. D.; Whatley, M. E. & Horton, R. W.
Partner: UNT Libraries Government Documents Department
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Declassified Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cramer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
open access

Closed-Loop Level Indicator for Corrosive Liquids Operating at High Temperatures

Description: Report issued by the Oak Ridge National Laboratory discussing the development of a closed-loop control system. As stated in the statement, "the purpose of this thesis was to design and build a closed-loop control system to be used as an indicator of the level of high temperature liquids contained in a tank" (p. 1). This report includes tables, illustrations, and photographs.
Date: June 4, 1956
Creator: Southern, A. L.
Partner: UNT Libraries Government Documents Department
open access

Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090

Description: Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Date: December 4, 1962
Creator: Garrett, M. W.
Partner: UNT Libraries Government Documents Department
open access

Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program, Semiannual Report for Period July 1 - December 31, 1962

Description: This technical report describes development work done on zonal centrifuge systems at the Oak Ridge National Laboratory and the Oak Ridge Gaseous Diffusion Plant during the period July 1 to December 31, 1962 under the Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program. A basic purpose of this project is to develop new methods for isolating virus particles associated with cancerous cells and tissues. Three classes of rotor systems capable of separati… more
Date: March 4, 1963
Creator: Anderson, N. G.
Partner: UNT Libraries Government Documents Department
open access

The Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending August 31, 1950

Description: Technical report outlining various experiments that took place in the Oak Ridge Area Critical Mass Laboratory until August 31, 1950. Experiments took place in categories of critical experiments, experimental engineering, heat transfer, radiation damage, nuclear measurements, reactor physics, ARE reactor design, circulating fuel reactors, and circulating moderator reactors. [From Summary]
Date: December 4, 1950
Creator: Ellis, C. B. & Thompson, W. E.
Partner: UNT Libraries Government Documents Department
open access

A Cost Analysis of the Idaho Chemical Processing Plant

Description: A capital cost breakdown of the Idaho Chemical Processing Plant, a directly maintained remotely operated plant for processing spent enriched uranium fuel assemblies from reactors, is presented. The capital investment in the plant, including design, construction, training, and preoperational costs, an estimate of the direct costs incurred by the Atomic Energy Commission, and a proportional part of the costs of Central Facilities, including the value of the land and improvements theorem when acqu… more
Date: January 4, 1955
Creator: Robertson, P. L. & Stockdale, W. G.
Partner: UNT Libraries Government Documents Department
open access

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Secret Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cromer, S. J.; Miller, A. J. & Savelainen, A. W.
Partner: UNT Libraries Government Documents Department
open access

Description of the Ibm-704 Code for the Calculation of Concentration Transients in the HRT

Description: The calculation of concentration transients caused by mixing in the interconnected three-body system of the fuel dump tanks, core and blanket has been coded for the IBM-704. The system of equations includes material balances, the dependence of critical temperature on core and blanket concentrations, and the effect of temperature (density) changes on flow rates. The controllable flow rates, the fuel dump tank weight and the initial conditions are input variables. Outputs include core and blanket… more
Date: October 4, 1960
Creator: Piper, H. B. & Haubenreich, P. N.
Partner: UNT Libraries Government Documents Department
open access

Fundamental Studies in Heat Transfer and Fluid Mechanics, Status Report July 1, 1959- Feb 29, 1960

Description: Experimental determination of heat-transfer coefficients, burnout heat fluxes, and friction factors have been made for swirl flow of low-and moderate-pressure water through electrically heated aluminum, nickel, and copper tubes containing full-length Inconel twisted tapes. For nonboiling conditions, swirl-flow heat-transfer coefficient were successfully correlated with both the Froude modulus (the ratio of inertial to centrifugal forces) and a grouping of the Grashof and Reynolds moduli (ratio … more
Date: October 4, 1960
Creator: Hoffman, H. W.; Gambill, W. R.; Keyes, J. J., Jr. & Kidd, G. J., Jr.
Partner: UNT Libraries Government Documents Department
open access

A Statistical Model of Nuclear Level Spacings

Description: A generalization of Wigner's simple model for the distribution of nuclear level spacings is studied. It is based on a stochastic process which reproduces the correct joing probability distribution of N enerfy levels for small spacings. The case N=3, which includes the effect of the correlation between adjacent spacings, is discussed in detail. The resulting distribution and the correlation coefficient are compared with experimental data. No definite conclusion can be drawn except to say that th… more
Date: December 4, 1960
Creator: Dresner, L. & Inönü, E.
Partner: UNT Libraries Government Documents Department
open access

Effect of HRT Core Sample Holder Upon Core Flow Pattern and Pressure Drop

Description: The measured pressure drop across the reactor core, with the sample holder in place, is 6.9 psi, more than twice the estimated value. Better estimates, based on more rigorous mathematical analysis, should be possible for future problems of this type. The 2% density difference which produced the relatively high velocity of approximately 1 fps, in this experiment, will result from a temperature difference of about 8 C. It is concluded that the bulk fluid temperature near the sample holder will be… more
Date: February 4, 1957
Creator: Hannaford, B. A.
Partner: UNT Libraries Government Documents Department
open access

Compilation of Requests for Nuclear Cross Section Measurements

Description: This report is a working document of the UB AEC Nuclear Cross Sections Advisory Group and is issued about twice a year for the purpose of stimulating important cross section measurements. The requests listed in this report have originated from various Atomic Energy Commission contractors, the Advisory Committee on Reactor Physics, and the Nuclear Cross Sections Advisory Group. The distribution is limited to members of the US Nuclear Cross Sections Advisory Group (NCSAG), the US Advisory Committ… more
Date: November 4, 1960
Creator: Harvey, John A.
Partner: UNT Libraries Government Documents Department
open access

Experimental Determination of an Adequate Fission Chamber Location in the ORR Pool

Description: An experiment was performed at the ORR in order to find a good fission chamber location. Two locations on the pool side of the reactor tank were explored with a one inch diameter fission chamber. The thermal neutron flux attention was found to vary nearly exponentially with distance, and no shadowing effect could be seen during a reactor startup. The fission products high gamma flux could be discriminated without difficulties. Both positions seem to be adequate to locate a reactor control fissi… more
Date: November 4, 1960
Creator: Roux, D. P. & Colomb, A. L.
Partner: UNT Libraries Government Documents Department
open access

APPR-1 Type Absorber Rod Irradiation Test -- Irradiation Request ORNL MTR-29

Description: In order to evaluate the behavior of an APPR type absorber rod, an irradiation test program has been established. Approximately 21 more samples are planned for testing under this request. The request proposes testing a full size APPR-1 type control rod in the MTR. The objective of the test is to better evaluate the neutron absorbing material proposed for the APPR-1 control rod.
Date: January 4, 1957
Creator: Gross, E. E. & Schaffter, L. D.
Partner: UNT Libraries Government Documents Department
open access

High Pressure Recombination Loop Progress Report

Description: The operation and design of a high pressure recombination loop for the recombination of H2, D2, and O2 produced by the radiolytic decomposition of water which is used a solvent for fuel in the homogeneous reactors are presented.
Date: January 4, 1957
Creator: Harley, P. H.
Partner: UNT Libraries Government Documents Department
open access

Observed Net Heat Loss from the HRT High-Pressure System

Description: An estimate has been obtained of the heat that should be generated in the HRT core in order to hold the system at operating temperature under no-load conditions. This estimate was made by measuring the feed-water rate to the package boiler during an oxygenated water rung. Results are summarized.
Date: June 4, 1957
Creator: Van Winkle, R. & Wiethaup, R. R.
Partner: UNT Libraries Government Documents Department
open access

ORR Startup Accident and Cooling Flow Coastdown Analog Analysis

Description: Startup accident and pump run-down on the ORR have been simulated on the Reactor Controls Analog Facility. At full flow the 150% level scram (45 Mv) easily terminates the startup accident before the metal temperature gets above 180°F. For very low flows typical of criticality runs, temperature coefficients turn the excursion before it reaches 150% of full power, and temperatures climb to boiling, a potentially hazardous condition. (This same behavior can occur at full flow is the power is incr… more
Date: January 4, 1961
Creator: Stone, R. S. & Colomb, A. L.
Partner: UNT Libraries Government Documents Department
open access

Testing of Adsorptive Capacity of Charcoal Beds : HRT Test No II-A 10 b

Description: During the pre-startup phase of the HRT operations, moisture was accidentally introduced into the charcoal bed adsorbers in the off-gas system. Tests have been made to determine the effect of wetting upon the adsorptive properties of the charcoal. The work was divided into two phases, testing of fresh charcoal in the laboratory and testing of the HRT charcoal beds in situ. It is recommended that the beds be dried by heating them to about 40 C and purging each with one to two liters/min of dry i… more
Date: June 4, 1957
Creator: Van Winkle, R. & Wiethaup, R.R.
Partner: UNT Libraries Government Documents Department
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