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Technical Report Archive and Image Library
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TRAIL Microcard Collection
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Hallam Nuclear Power Facility Reactor Operations Analysis Program Semiannual Progress Report
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OMR Control-Safety Rod Component Development Tests
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
Power Flattening in Sodium Graphite Reactors by Spatial Variation of Moderator Properties
Hot-Pressure Bonding of OMR Fuel Plates
Organic Reactor Waste Gas Analyzer
Terminal Status Report for the Processing Refabrication Experiment
Analysis of Stresses in Bellows
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
A Multichannel Digital Recording System
Hazards Analysis of the Organic Moderated Reactor Experiment
Thermal Cycling Tests of Porous Uranium
Fabrication Modification Development for OMRE Third Core Loading
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
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility
SNAP 10A FSEM-3 Agena Compatibility Test
Basic Chemistry of High Temperature Inorganic Systems, Semiannual Progress Report: July-December 1956
Dynamic Void Fraction Measurement System
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Carbide Fuels in Fast Reactors
Organic Moderated Reactor Experiment Progress Report: October 1955-July 1956
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964
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