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Invention Report: Hermetically Sealed Closure on a Sheathed Thermocouple
A Study of the Wear and Galling of Autoclaved Zircaloy-2 By Various Materials
A Model of the PRTR Mark I Fuel Element for Heat Transfer Experiments
Project CGC-830 Plant Modifications for Reprocessing Non-Production Reactor Fuels
Depassivation of 304-L Stainless Steel in Sulfex Decladding Solutions
Thickness Measurement by Ultrasonic Frequency Modulation
Fluidized-Bed Calcination Studies with Stimulated ICPP Waste Solution
Termination Report for Development Test IP-306-K Spline Coilers at K Reactor
Non-destructive Testing Hanford Fuel
Use of Isolated Junction Sheathed Thermocouples for Moderator Temperature Measurements
Steam Water Pressure Drop and Critical Discharge Flow - A Digital Computer Program
Sampling and Analytical Data on Al-Pu Alloy for PRTR Start-Up Tests
Water Chemistry for KER Loop 1- June 29, 1959 to December 31, 1959
Summary Listing of Subcritical Measurements of Heterogenous Water-Uranium lattices Made at Hanford
Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor.
Scavenging as a Predisposal Treatment for NPR Decontamination Wastes
A Study for the Feasibility for the Large Sale Recovery of Ionium (Thorium-230) from the Uranium Ore Milling Industry in the United States
Integrated Radiological Instrumentation System Planning
Coagulant Aids as Filter Aids
HAPO IB Fission Product Shipping Cask Design Evaluation Report
Nuclearly Safe Mass Limits, Volume Limits, Infinite Cylinder Diameters and Slab Thicknesses for Slightly Enriched Uranium Rods in Light Water
Quarterly Report Technology of Non-Production Reactor Fuels Processing Budget Activity 2790
Plutonium Oxide- Plastic Mixtures for Critical Mass Studies
Thermal Hydraulic Bases for Selected PRTR Process Specifications
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