The Closest Packing of Spheres (A Unifying Basis for Crystal Structures) (open access)

The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)

Abstract: An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres.
Date: July 30, 1961
Creator: Gehman, William G.
System: The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System (open access)

Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System

Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date: September 15, 1961
Creator: Schlein, H.
System: The UNT Digital Library
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures) (open access)

The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)

"An intuitive approach to the understanding of crystal structures is presented in terms of the concept of the closest packing of spheres. The qualitative features of the concept are sorted out and correlated by successively treating single, double, triple, and multiple layered arrays of closest packed spheres" (p. ix).
Date: July 30, 1961
Creator: Gehman, William G.
System: The UNT Digital Library
Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor (open access)

Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor

Abstract: A conceptual reference design of a 318 Mw(e) Graphite Moderated Boiling and Superheating Reactor (GBSR) is described.
Date: September 1961
Creator: unknown
System: The UNT Digital Library
Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F (open access)

Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F

Abstract: Because of the outstanding heat transfer efficiency of sodium, it is necessary in sodium-cooled reactors to consider and attempt to prevent the occurrence of adverse stresses as a result of thermal transients in the system.
Date: February 28, 1961
Creator: McDonald, J. S.
System: The UNT Digital Library
Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator (open access)

Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator

Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date: February 28, 1961
Creator: Webster, L. J.
System: The UNT Digital Library
Fabrication Modification Development for OMRE Third Core Loading (open access)

Fabrication Modification Development for OMRE Third Core Loading

Abstract: This report describes the fabrication of elements for the OMRE third core loading.
Date: July 15, 1961
Creator: Peters, E. & Binstock, M. H.
System: The UNT Digital Library
Final Safeguards Summary Report for the Piqua Nuclear Power Facility (open access)

Final Safeguards Summary Report for the Piqua Nuclear Power Facility

Summary: This report contains a description of the final design of the Piqua Nuclear Power Facility (PNPF); an outline of the test and operating procedures, and the organization and responsibilities; and a summary of the hazards and safeguards analyses that have been conducted to evaluate the safety of the facility operations.
Date: August 1, 1961
Creator: unknown
System: The UNT Digital Library
Design Modifications to the SRE during FY 1960 (open access)

Design Modifications to the SRE during FY 1960

Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
System: The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode (open access)

Metallurgical Aspects of SRE Fuel Element Damage Episode

Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
System: The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs (open access)

Investigations of Neutron Penetration in TiH and Steel Slabs

Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date: May 15, 1961
Creator: Karcher, R. H.
System: The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System (open access)

Corrosion and Activity Transfer in the SRE Primary Sodium System

Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date: October 30, 1961
Creator: Johnson, H. E.
System: The UNT Digital Library
The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System (open access)

The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
System: The UNT Digital Library