66 Matching Results

Search Results

Results: 1 - 24 next
open access

Numerical Computation of Neutron Distribution and Critical Size

Description: Report presenting a numerical calculation, by diffusion theory, of the critical size of a nuclear reactor, and of the time dependent distribution of neutrons in the reactor as a function of position (one-dimensional space) and neutron energy. The mathematical development of the numerical method, properties of the equations, and procedure are discussed in the report, along with a numerical example.
Date: February 15, 1950
Creator: Thompson, A. Stanley
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Uranium Production Reactor (UPR) Quarterly Progress Report, May-July, 1953

Description: "Measurements of the intra-cell neutron flux distributing for a proposed Uranium Production Reactor have been made using a mock-up of a portion of the reactor core. Thermal neutron and thorium resonance neutron flux-distributions were investigated. As a result of the experimental measurements on the first mock-up, a decrease in thorium content appeared necessary in the reactor design studies. Experiments are now in progress on a second mock-up in which this change has been made."
Date: March 15, 1954
Creator: Laubenstein, R. A.; Houghton, W. J. & Martin, D. H.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Reactor Physics, Quarterly Progress Report, November, 1953 - January 1954

Description: "A series of thermal neutron diffusion length measurements has been made on non-multiplying lattice of lead-cadmium alloy rods in D2O. One-inch diameter rods in square lattice spacing of 4, 9, 6, 9, and 12 inches were used. Excellent agreement was found between theoretical and experimental values of the diffusion length. The analysis o the diffusion length measurement required a correction for the epithermal neutrons entering the exponential tank. These epithermal neutrons provided a distri… more
Date: May 15, 1954
Creator: Laubenstein, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical Development, Quarterly Progress Report, October-December 1953.

Description: Introduction - The work of the Chemical Development Group has included studies on the thermal and radiation stability of organic materials suitable for reactor coolants, the thermal and radiation stability of zirconium hydride, reactor safety devices involving chemical systems, and general analytical development.
Date: June 15, 1954
Creator: Loftness, R. L.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Distribution of Tracer Plutonium and Fission Products Between Molten Uranium and Solid Uranium Oxide, Carbide, and Nitride

Description: "A study has been made of the distribution of tracer fission products and plutonium between small samples of molten uranium and solid uranium oxide, carbine, and nitride. The distribution showed the same behavior i general for all three materials: 1. The rare earth elements, Cs, Ba, and Sr were extracted primarily into the solid scrub phase. 2. Zirconium and Nb partially concentrated in the scrub phase. 3. Plutonium, Mo, and Ru tended to remain completely in the metal phase. The distribution… more
Date: September 15, 1954
Creator: Keneshea, F. J.; Saul, A. M. & Young, C. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Improved Method for Numerically Solving Multi-Group Reactor Equations

Description: "A method for solving multi-group reactor equations which arise in the diffusion approximation is outlined. Considerable work has been done on this problem at KAPL and ORNL. Their approach is to replace the differential equations by difference equations. Complications arise in this method where more than one slowing down medium is present since the fluxes are discontinuous at the interfaces. The primary purpose of this article is to develop an exact integral expression for the neutron flux w… more
Date: September 15, 1954
Creator: Lehman, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Sodium Cooled, Graphite Moderated, Low Enrichment Uranium Reactor for the Production of Useful Power

Description: "A design study is presented for a sodium cooked, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam genera… more
Date: September 15, 1954
Creator: Weisner, Edward F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A Remotely Controlled Welding Device for Joining Stainless Steel Tubes

Description: Abstract: The design and testing of experimental equipment for remotely joining stainless steel tubing by heliarc welding is described. This apparatus consists of a modified heliarc welding torch which is hydraulically controlled to maintain constant arc voltage. A suitable arc voltage sensing and control amplifier circuit was developed for this application.
Date: November 15, 1954
Creator: Mueller, Martin & Hecker, Eugene
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Proton Irradiation Effects in Thorium

Description: "Iodide-processed thorium foils were irradiated with 9-Mev protons at temperatures below -140 degrees C. the recover of electrical resistance upon annealing was studied in the range 0 degrees to 75 degrees where tempering curves showed rapid changes taking place. Determinations of the activation energy associated with this process were made and the mean value obtained was 1.22 ev. Correlations of this result have been made with those found previously for copper. From these comparisons, a tenta… more
Date: December 15, 1954
Creator: Meechan, Charles J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry Quarterly Progress Report: July-September 1954

Description: Quarterly progress report of North American Aviation's Chemical Technology Group discussing the activities of the separations chemistry research and development program, which is chiefly concerned with the application of high temperature methods to the extraction of fissionable materials and fission products from reactor fuels and fertile methods. (Introduction)
Date: April 15, 1955
Creator: Motta, E. E.; Cubicciotti, Daniel D. & Bareis, David W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry Quarterly Progress Report: October-December 1954

Description: Quarterly progress report of North American Aviation's Chemical Technology Group discussing the activities of the separations chemistry research and development program, which is chiefly concerned with the application of high temperature methods to the extraction of fissionable materials and fission products from reactor fuels and fertile methods. (Introduction)
Date: July 15, 1955
Creator: Motta, E. E.; Cubicciotti, Daniel D. & Bareis, David W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

North American Aviation General Chemistry Quarterly Progress Report: April-June 1955

Description: Quarterly progress report discussing activities of main efforts in the General Chemistry division of North American Aviation including the Organic Coolant-Moderator Program and the Analytical Chemistry-Methods Development and Analytical Services.
Date: March 15, 1956
Creator: Colichman, Eugene L. & Motta, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

North American Aviation General Chemistry Quarterly Progress Reports: October 1954/January 1955

Description: Quarterly progress report discussing activities of main efforts in the General Chemistry division of North American Aviation including The Organic Coolant-Moderator Program, the Analytical Chemistry-Methods-Development and Analytical Services, and the papers presented by the General Chemistry Group.
Date: March 15, 1956
Creator: Colichman, Eugene L. & Motta, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry Quarterly Progress Report: October-December 1955

Description: Quarterly progress report of North American Aviation's Chemical Technology Group discussing the activities of the separations chemistry research and development program, which is chiefly concerned with the application of high temperature methods to the extraction of fissionable materials and fission products from reactor fuels and fertile methods. (Introduction)
Date: July 15, 1956
Creator: Motta, E.; Buyers, A.; Yosim, S. & Foltz, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Separations Chemistry Quarterly Progress Report: April-June 1956

Description: Quarterly progress report of North American Aviation's Chemical Technology Group discussing the activities of the separations chemistry research and development program, which is chiefly concerned with the application of high temperature methods to the extraction of fissionable materials and fission products from reactor fuels and fertile methods. (Introduction)
Date: December 15, 1956
Creator: Buyers, A. G.; Gardner, W. J.; Motta, E. E. & Brand, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956

Description: Report describing technical progress on the design and construction of an Organic Moderated Reactor Experiment (OMRE), to be operated at the National Reactor Testing Station in Arco, Idaho. "This is the first report of the series and coves the period from the initiation of the project to July 31, 1956. Also included as an appendix to the report is a detailed description of the OMRE facility" (p. 3).
Date: March 15, 1957
Creator: Trilling, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen