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Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber (open access)

Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
System: The UNT Digital Library
Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation (open access)

Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation

Technical report covering work completed on the removal of radioisotopes from water using a calcium phosphate floc as a carrier. This research was performed as part of the Health Physics Waste Disposal Research Section work on the removal of small quantities of radioactivity from large volumes of water. [From Abstract]
Date: January 23, 1951
Creator: Lauderdale, Robert A., Jr.
System: The UNT Digital Library
A Manual of HRE Control and Instrumentation (open access)

A Manual of HRE Control and Instrumentation

Technical reports outlining the controls for the Homogeneous Reactor Experiment (HRE); controls are divided into three principal groups. 1. Reactor. 2. Process or auxiliary. 3. Power generation. These are the classifications designating the primary functions of the controls. [From Introduction]
Date: January 23, 1952
Creator: Quarles, L. R. & Walker, W. P.
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

This quarterly progress details ongoing research at the Oak Ridge National Laboratory as a part of the Aircraft Nuclear Propulsion Project. Topics discussed include reactor theory and design, [part two is not included], materials research, and appendixes with information on analytical chemical studies.
Date: October 23, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, William B.
System: The UNT Digital Library
Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955 (open access)

Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955

The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million moles of effluent solvent under laboratory conditions. The vapor pressure of BF3 over the complex rises sharply as the temperature is increased. At 0°C the pressure is 150 mm Hg, and at 40°C the pressure has risen to 1800 mm Hg. From vapor-pressure measurements, an approximate upper limit of ΔH= -12kcal per mole of complex was calculated for the reaction [equation not transcribed]. Qualitative tests indicate good resistance of anisole to decomposition by BF3 under plant conditions. The uncatalyzed exchange of boron between BF3 and BCl3 was found to be too slow to be exploited in a countercurrent system. The single-stage, equilibrium separation factor for the Nitrox system is a function of acid concentration. At 26°C the factor ranges from 1.064 with 1 M acid …
Date: February 23, 1956
Creator: Clewett, G. H. & Drury, J. S.
System: The UNT Digital Library
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution (open access)

Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
System: The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: March 1963 (open access)

Gas-Cooled Reactor Project Semiannual Progress Report: March 1963

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date: July 23, 1963
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor (open access)

Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor

Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date: December 23, 1960
Creator: Wick, E. A. & Heestand, R. L.
System: The UNT Digital Library
A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor (open access)

A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estimated and F the fuel rod in which the neutron originated, then flight path P results in an intercepted length whose reflection in the plane is L. On the other hand flight path P' intercepts R' with length L'. R' is not the region to be studied, but a translation of the flight path P' to F' would result in the neutron intercepting R. The origin in P was arbitrary. For each neutron originating in P another could, with equal probability, have originated in P' with parallel paths. Hence consulting L' in R' towards the total flux is equivalent to starting a neutron at P'. Thus consideration of all regions symmetric to R with respect to …
Date: February 23, 1955
Creator: Moshman, Jack
System: The UNT Digital Library