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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

Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Item Type: Refine your search to only Report
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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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