61 Matching Results

This system will be undergoing maintenance May 12th between 9:00AM and 12:00PM CDT.

Search Results

Results: 1 - 24 next
open access

Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Partner: UNT Libraries Government Documents Department
open access

A Further Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: This report presents the results of plant optimization studies and cost estimates of the reference design for a natural uranium, graphite moderated, gas-cooled reactor and power plant which was described in NAA-SR-1833.
Date: June 28, 1957
Creator: Banks, William F.
Partner: UNT Libraries Government Documents Department
open access

An Evaluation of the Calder Hall Type of Nuclear Power Plant

Description: Abstract: Presented herein is the preliminary design of a natural uranium, graphite moderated, CO2-cooled reactor and power plant similar to, but larger than, the British Calder Hall plant, with a net electrical output of 130 MWE.
Date: January 18, 1957
Creator: Banks, William F.; Schneider, G. A.; Morgan, William T. & Ash, E. B.
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry, Quarterly Progress Report, April-June 1954

Description: "Scale-up experiments on high temperature fuel recovery processes have included the dummy run phase on the handling of 1-kologram samples of molten, non-irradiated uranium in the hot cell. The next step involves the use of spent X-10 fuel slugs. Small scale experiments with X-10 uranium on the extaction of Pu with Mg show that as much as 80 per cent of the Pu can be removed in pone pass. Treatment of uranium with fused fluorides can remove at least 90 per cent of the Pu in one pass. Oxide sc… more
Date: October 1, 1954
Creator: Bareis, David W.; Cubicciotti, Daniel D. & Motta, E. E.
Partner: UNT Libraries Government Documents Department
open access

A Pebble-Bed Reactor for Stationary Power Plants

Description: A preliminary study has been made of a solid homogeneous reactor for stationary power plant application. The core consists of graphite spheres impregnated with uranium and thorium, and the coolant is bismuth. This concept possible offers advantages over other solid fuel reactor systems with respect to simplification of core structure, fuel fabrication and fuel handling, and reduction of fuel inventory external to the reactor. From the results of this preliminary study, it appears that the pot… more
Date: May 15, 1954
Creator: Beeley, R. J.
Partner: UNT Libraries Government Documents Department
open access

A Reversing Logarithmic DC Amplifier

Description: Purpose: Automatic recording equipment was designed for use with a high temperature Sykes experiment in which calorimetric measurements were to be made to temperatures approaching 2000* C. At such high temperatures, radiation becomes the dominant mechanism for heat transfer. The temperature differences which are used to determine the magnitude of this transfer no longer are directly proportional to it, but must be related by the Stefan-Boltzman law of radiation.
Date: January 1, 1954
Creator: Carter, R. L.
Partner: UNT Libraries Government Documents Department
open access

General Chemistry, Quarterly Progress Report, April-June 1954

Description: "General Chemistry investigations reported herein includes: (1) the Organic Coolant-Moderator Program, (2) investigations on zirconium hydride, and (3) analytical chemistry."
Date: December 15, 1954
Creator: Colichman, Eugene L.
Partner: UNT Libraries Government Documents Department
open access

Sodium Reactor Experiment Pump Development

Description: Design and operational techniques are described for a freeze seal type centifugal pump for use in the Sodium Reactor Experiment.
Date: January 1, 1957
Creator: Cygan, R.
Partner: UNT Libraries Government Documents Department
open access

Effect of Reactor Irradiation on the Thermal Conductivity of Uranium Impregnated Graphite at Elevated Temperatures

Description: "An experiment to determine the effect of reactor irradiation on the thermal conductivity of uranium-impregnated graphite at elevated temperatures as described. The results show a decrease in the thermal conductivity saturating at [approximately] 60 percent at a temperature of 700 degrees C; at [approximately] 50 percent at a temperature of 1000 degrees C; and at [approximately] 25 percent at a temperature of 1300 degrees C. It was found that after irradiation at a given temperature, exposure… more
Date: April 29, 1954
Creator: Durand, Richard E.; Klein, David J. & Nykiel, Harry H.
Partner: UNT Libraries Government Documents Department
open access

Neutron Leakage from the 30 Megawatt SGR-P4 Reactor

Description: Abstract: The fast and thermal neutron leakage from the 30 megawatt SGR-P4 reactor has been studied by three independent methods.
Date: August 21, 1953
Creator: Fillmore, F. L.
Partner: UNT Libraries Government Documents Department
open access

Organic Reactor Waste Gas Analyzer

Description: The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
Date: October 15, 1958
Creator: Gilroy, H. M. & Edwards, R. J.
Partner: UNT Libraries Government Documents Department
open access

Reference Design for an OMR-Powered 38,000-DWT Tanker

Description: Abstract: This report presents a reference design of an organic moderated and cooled reactor for the propulsion of a 38,000-dwt tanker.
Date: March 18, 1957
Creator: Gimera, R. J. & Stanbridge, R. E.
Partner: UNT Libraries Government Documents Department
open access

SRE Instrumentation and Control

Description: Introduction: This memo gives a general description of the components and equipment affecting the control of the SRE, and the equipment associated with all reactor services.
Date: May 21, 1956
Creator: Hall, R. J.
Partner: UNT Libraries Government Documents Department
open access

Heat Generation in Thermal Shields

Description: "Heat production resulting from the absorption of gamma ray photons in thermal shields and the leakage of neutrons and photons from ferritic thermal shields are investigated. The gamma rays considered arise from three types of reactor radiation -- thermal neutrons, fast neutrons, and core and reflector gammas. The energy spectra of the fast neutron leakage and absorption have been investigated in some detail because of the significant contribution of fast neutrons to the heating of the concre… more
Date: August 15, 1954
Creator: Heisler, M. & Wetch, J.
Partner: UNT Libraries Government Documents Department
open access

A Conceptual Design of a Thorium-Uranium (233) Power Breeder Reactor

Description: From abstract: A conceptual design study has been performed for a sodium cooled, graphite moderated, thermal power-breeder reactor utilizing the Thorium-Uranium 233 breeding cycle. Several aspects of the design of the system are considered but no attempt has been made to supply all the details. It appears that the design presented is feasible and will allow the production of economic power as well as full utilization of thorium resources.
Date: February 1, 1954
Creator: Henrie, J. O. & Weisner, E. F.
Partner: UNT Libraries Government Documents Department
open access

OMR Control-Safety Rod Component Development Tests

Description: Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date: September 15, 1959
Creator: Howell, J. D.
Partner: UNT Libraries Government Documents Department
open access

Reactor Safety, Quarterly Progress Report, February-April 1954

Description: "The composition of the solder for the solder plug has been set as the tin-silver eutectic. Final tests on this solder show that life expectancies much longer than 6 months are probable with the current design. The design of the heater tube to contain the solder plug has been settled. This consists of a copper tube impregnated with U235O2. Arrangements have been made to have test specimens fabricated by powder metallurgy techniques. The equipment for the MTR in-pile test of trigger element r… more
Date: October 1, 1954
Creator: Huston, Norman E.
Partner: UNT Libraries Government Documents Department
open access

Thermodynamic Diagrams for Sodium

Description: From abstract: This paper presents temperature-entropy and Mollier charts for sodium, and describes briefly the method used for their construction, based upon data from the literature.
Date: July 13, 1950
Creator: Inatomi, T. H. & Parrish, W. C.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen