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AEC research and development report
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AEC research and development report
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Gamma-Ray Spectrometry of Neutron-Deficient Isotopes Annual Progress Report
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Hallam Nuclear Power Facility Reactor Operations Analysis Program Semiannual Progress Report
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Southwest Experimental Fast Oxide Reactor Development Program Quarterly Report
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AEC research and development report
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1960-1969
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1964
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Chemical Coolants for Machining Uranium in the Presence of Trace Amounts of Chloride
X-Ray Fluorescence Tables: Program Description
Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders
Geophysical Seismic Evaluation Study at Hanford
PRTR second generation shim assembly
Liquid Metal Fast Breeder Reactor Design Study
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies
A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys
Scientific-Information Centers in the U.S.A. and the U.S.S.R
Flow Stability of Gas-Solids Suspensions: Final Report
Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963
A Study of Desalting Plants (15 to 150 mgd) and Nuclear Power Plants (200 to 1500 MWt) for Combined Water and Power Production: Final Report
A Single Stage Axial Compressor Blade Test Facility
Analysis of Stresses in Bellows
A Portable Neutron Counter for Determining Weights of Deposits of Uranium-Fluorine Compounds
Criticality-Accident Dosimetry Studies
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
Reactor Technology Report Number 24: Metallurgy
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