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Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors

Description: From abstract: In this report a consistent set of U-235 partial cross sections for use in the analysis of thermal or intermediate reactor systems has been provided.
Date: July 17, 1961
Creator: Goodjohn, A. J. & Wikner, N. F.
Partner: UNT Libraries Government Documents Department

Design, Construction, and Initial Operation of General Atomic In-Pile Loop

Description: From preface: To test the HTGR fuel-element design under environmental conditions of radiation, temperature, and pressure that approximate those in the Peach Bottom core and to test the operability of a dynamic system containing a vented graphite-clad fuel element.
Date: February 15, 1965
Creator: Simon, R. H.
Partner: UNT Libraries Government Documents Department

Prestressed Concrete Reactor Vessel Model 1

Description: From introduction: The goal of engineers associated with nuclear power plants is the achievement of safe plants with low generating costs.One possible means of lowering costs is to increase the power generating capability for a single generating unit. To accomplish this, the sizes of nuclear reactors have been increased.
Date: October 25, 1966
Partner: UNT Libraries Government Documents Department

Technical Foundations of TRIGA

Description: From foreword: The TRIGA is a novel and unusually safe training, research, and isotope-production reactor that contains solid homogeneous uranium-zirconium-hydride-moderator fuel elements and operates at power levels in the range of from 10 kw to 250 kw.
Date: August 27, 1958
Creator: General Dynamics Corporation. General Atomic Division.
Partner: UNT Libraries Government Documents Department