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AEC research and development report
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AEC research and development report
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Salt Bath Heat Transfer Rates for Uranium Plate
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
A Computer Program for Determining First-Collision Neutron Doses
A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal
Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant
Supplement to Reactor Containment Design Study
The Second Refueling of Core I of the Shippingport Atomic Power Station
Reactor Technology Report Number 22: Chemistry
Environmental Monitoring Semiannual Report: January-June 1962
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Thermal Stress Testing of Beryllium Oxide Moderator Shapes
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Capsule Irradiation of Unalloyed Uranium at High Temperatures
Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors
Fast Neutron Flux Measurements and Analysis in SM-1 and PM-2A Core and Vessel Mockups
Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants
PM-2A Core II Zero Power Experiment
Fort McClellan Radiological Instruction Area (ARMS-II)
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1962 - September 1, 1962
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