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Technical Report Archive and Image Library
213
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Technical Report Archive and Image Library
213
TRAIL Microcard Collection
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General Electric Company Atomic Power Reports
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General Electric Company Atomic Power Reports
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Atomic Energy Commission Reports
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AEC Research and Development Report
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Oak Ridge National Laboratory Reports
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Nuclear Superheat Quarterly Project Report
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Fast Ceramic Reactor Development Program Quarterly Report
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EVESR Nuclear Superheat Fuel Development Project Quarterly Report
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Fuel Cycle Program Progress Report
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Accurate Nuclear Fuel Burnup Analyses Quarterly Report
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Program of Two-Phase Flow Investigation Quarterly Report
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Specific Zirconium Alloy Design Program Quarterly Progress Report
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Transition Boiling Heat Transfer Program...Second Quarterly Progress Report
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Two-Phase Pressure Losses Quarterly Progress Report
3
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report
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In-Core Instrumentation Development Program Quarterly Progress Report
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Transition Boiling Heat Transfer Program...Quarterly Progress Report
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Fast Ceramic Reactor Development Program Summary Report
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Report (U.S. Atomic Energy Commission)
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Southwest Experimental Fast Oxide Reactor Development Program Quarterly Report
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Transition Boiling Heat Transfer Program...First Quarterly Progress Report
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1960-1969
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Technical Report Archive and Image Library
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General Electric Company Atomic Power Reports
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1960-1969
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Transition and Film Boiling Data at 600, 1000, and 1400 PSIA in Forced Convection Heat Transfer to Water
Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964
Oxidation Mechanism of Zirconium and Its Alloys. [Part] II. Oxide Plasticity
Nuclear Superheat Quarterly Project Report: Eighteenth Quarter, November, 1963-January, 1964
Design and Fabrication of Fuel Rods Containing Sintered UO2 Extrusions - Assembly 11L
Design and Fabrication of Pellet Fuel Rods Clad With Thin Wall Stainless Steel
Localized Corrosion of Stainless Steels and High-Nickel Alloys in Simulated Superheat Reactor Environment
Mechanical, Fluid Flow, and Heat Transfer Out-Of-Pile Tests on EVESR MKI Prototype Fuel Bundle
Preoperational Power Stability Analysis of the Consumers Big Rock Point Plant
Sodium Mass Transfer. [Part] 8. Corrosion of Stainless Steel in Isothermal Regions of a Flowing Sodium System
Sodium Mass Transfer. [Part] XI. 1963 Test Run Reports (January - June)
Fuel Cycle Program Progress Report: Fourteenth Quarter, October-December 1963
High Performance UO2 Program Quarterly Progress Report No. 11 October-December 1963
Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: October 1 - December 31, 1963
Consumers Big Rock Point Nuclear Power Reactor Stability Analysis
Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 5
High Performance UO2 Program Quarterly Progress Report No. 13 April-June 1964
High Power Density Development Project: Fifteenth Quarterly Progress Report, October-December 1963
In-Core Instrumentation Development Program Quarterly Progress Report September - December 1963
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Ninth Quarterly Report, October-December 1963
Specific Zirconium Alloy Design Program Quarterly Progress Report: Seventh Quarter, October - December, 1963
Transition Boiling Heat Transfer Program; Fourth Quarterly Progress Report, October - December 1963
Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)
EVESR Nuclear Superheat Fuel Development Project: Sixth Quarterly Report, September - November, 1963
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