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Technical Report Archive and Image Library
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AEC research and development report
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AEC research and development report
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AEC research and development report
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Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV
Nuclear Port Survey of the State of New York
Progress Report Pebble Bed Reactor Program: June 1, 1959-October 31, 1960
The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System
Mechanical Properties of Zircaloy-2
Mechanical Properties of Zircaloy-2 Weld Metal
Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor
Reactor Containment Design Study
Boiling of Freon-114 in a Three-Foot Straight Tube Evaporator
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
The Closest Packing of Spheres (A Unifying Basis for Crystal Structures)
Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor
Experimental Evaluation of a Sodium-to-Sodium Heliflow Heat Exchanger at Temperatures up to 1200°F
Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator
Fabrication Modification Development for OMRE Third Core Loading
Final Safeguards Summary Report for the Piqua Nuclear Power Facility
Design Modifications to the SRE during FY 1960
Metallurgical Aspects of SRE Fuel Element Damage Episode
Investigations of Neutron Penetration in TiH and Steel Slabs
Corrosion and Activity Transfer in the SRE Primary Sodium System
Critical Path Scheduling in Maintenance
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 5. Spiked Core Concept
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