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North American Aviation Reports
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Hallam Nuclear Power Facility Reactor Operations Analysis Program Semiannual Progress Report
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report
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Analysis of Stresses in Bellows
Sodium Reactor Experiment Power Expansion Program: Heat Transfer Systems Modifications
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility
Steam Cycle Optimization Study for Large Sodium Graphite Nuclear Power Generating Stations
UC Fuel Element Design and Fabrication
Study of SCTI Control System
Refabrication and Encapsulation of Highly Irradiated Uranium Dioxide
Evaluation of Coolant Impurity Removal Equipment at the OMRE
Radiolysis Products of Polyphenyl Coolants: Part 3, Omre High Boilers
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964
Material Bucklings of Critical and Subcritical Uranium Carbide Fueled Graphite Assemblies: Part 1, Experiment
SNAP 10A-PSM-1: Test Results
Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses
Boiling Depressurization Transients
HNPF Control System Response During Transient Conditions
SNAP 10A Structural Analysis
Structural Test on the Final SNAP 10A Prototype System
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963
Uranium Carbide Transient Heating Experiments - Phase 1
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows
Analog Models for HNPF Control and Protection Studies
Design of an Experimental Bowable Fuel Element for the SRE
Inpile Experiments on Retention of Fission Products in 500°F Sodium
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