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Final Report on Test L4, a Loss-of-Flow Experiment

Description: The behavior of FTR-type, mixed-oxide, pre-irradiated "high-power-structure" fuel during a simulation of an FTR loss-of-flow accident was studied in the Mark-IIA integral TREAT loop. Analysis of the data leads to a postulated scenario (sequence and timing) of events in this test. This scenario is presented, together with the calculated timing of events obtained by use of SAS code.
Date: December 1976
Creator: Eberhart, James G.; Lo, R. & Barts, E. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Progress Report for the Month of January, 1952

Description: This progress report of the Battelle Memorial Institute covers information in many categories. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
Date: February 1, 1952
Creator: Russell, H. W.; Nelson, H. R. & Dayton, R. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Information Report by Atomic Power Development Associates Covering Work from the Period August 1, 1954 to January 31, 1955

Description: Report issued by the APDA over the work conducted between August 1954 and January 1955. Descriptions of the studies, facilities, and equipment used during this time are presented. This report includes tables, illustrations, and photographs.
Date: January 31, 1955
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transient Temperature Simulation of Reactor Primary Loop

Description: Report issued by the APDA over simulator studies conducted on their Developmental Fast Breeder Reactor. The simulator studies were "designed to predict both the normal and abnormal operating characteristics of the APDA Developmental Fast Breeder Reactor" (p. 1). This report includes tables, and illustrations.
Date: February 1, 1956
Creator: Olson, Richard G. & Ritchie, Donald J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Thermal Bowing of Core Subassemblies

Description: Report issued by the APDA over studies conducted on thermal bowing of core sub-assemblies at the Enrico Fermi Atomic Power Plant. As stated in the introduction and summary, "the present report deals with this problem in the design of the Enrico Fermi Reactor and with the method which has been adopted to avoid a positive temperature coefficient of reactivity" (p. 1). This report includes illustrations, and photographs.
Date: February 20, 1959
Creator: De Stordeur, Arnold
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HAFEVER: An Inelastic Scattering Code for the IBM 704 Computer

Description: Report issued by the APDA over HAFEVER, a code developed for the IBM 704 computer. As stated in the introduction, "HAFEVER is an IBM 704 code which calculates the energy exchange inelastic scattering cross section" (p. 3). Descriptions of the code and the theory behind the code are discussed. This report includes tables.
Date: September 1960
Creator: Friedman, M. A. & Zweifel, P. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of the APDA Fuel Development Programs

Description: Report issued by the APDA over fuel development programs. Designs for fast breeder reactors, safety tests, and methods are presented and discussed. This report includes tables, illustrations, and photographs.
Date: April 1961
Creator: Blessing, W. G.; Busch, J. S.; Duffy, J. G.; Hennig, R. J.; Jens, W. H.; Knight, F. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress Report for the Month of February, 1952

Description: This progress report of the Battelle Memorial Institute covers information in many categories for February, 1952. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
Date: March 1, 1952
Creator: Russell, H. W.; Nelson, H. R. & Dayton, Russell W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Oak Ridge Metals and Ceramics Division Annual Progress Report: 1963

Description: Report documenting research and developments made by the Metals and Ceramic Division of the Oak Ridge National Laboratory. Progress is reported on fundamental research in: crystal physics, reactions at metal surfaces, spectroscopy of ionic media, structure of metals, theory of alloying, physical properties, sintering, deformation of crystalline solids, x ray diffraction, metallurgy of superconducting materials, and electron microscope studies. Long-randge applied research studies were conducted… more
Date: November 11, 1963
Creator: Oak Ridge National Laboratory. Metals and Ceramics Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Initial Operation of the Standard Pile

Description: From abstract: "The Standard Pile was first brought to criticality on July 25, 1953. The first two months of operation permitted calibration of the reactor and preparation of it for use as a neutron source in exponential experiments."
Date: December 1953
Creator: Axtmann, Robert C.; Heinrich, L. A.; Robinson, R. C.; Towler, O. A. & Wade, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operating and Safety Problems in a Research Reactor

Description: Abstract. The purpose of this paper is to present, in the light of 20 years of reactor-operation experience at ORNL, what is being done in preparation for operation of the HFIR (High Flux Isotope Reactor). This paper considers only the areas of staffing and training; development of operating and maintenance procedures; preoperational testing of water systems; and testing of remote handling tools. The preparatory work in other areas such as the hydraulic tests, neutron tests, etc., is not cover… more
Date: October 23, 1963
Creator: McCord, R. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Reactor Project Semiannual Progress Report: September 1964

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 1965
Creator: Trauger, D. B. & Whitman, G. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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