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Hanford Atomic Products Operation Plutonium Recycle Test Reactor Mechanical Seal Pump Operating Experience
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100-N Decontamination Facility Design Guide.
Aluminum Alloy Work at Hanford
APDAC-I, A PCTR Data Analysis Code for the IBM 709
The Blast Cleaning Process as an Aid to Visual Weld Inspection
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
Classification of PuO2 Particles
Coagulant Aids as Filter Aids
Completion Report An Automatic Fuel Element Stamping Machine
Contraction Losses and High Temperature Pressure Drop Determinations for Tube Bundles
Critical Mass Studies of Plutonium Solutions
Critical Pressure Ratio for a Nozzle with Two-Phase Fog Flow
Critical Tests for PRT Reactor
Decontamination of the Irradiated Rupture Prototype with Peroxide-Carbonate and Apace
Density and Hydrogen Content of Uranium Oxide Cakes and Slurries
Depassivation of 304-L Stainless Steel in Sulfex Decladding Solutions
Description of the Thermal Hydraulics Laboratory at Hanford
Development of a Welding Process for End Closures on NPR and KER Fuel Element
Development of a Welding Process for Spire-Can Fuel Elements
Development of Pressures Tubing for the Plutonium Recycle Test Reactor
Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959
Dissolution of Power Reactor Fuel Cores
Effect of the PRTR Fuel Elemental Rupture Test Facility on Plutonium Recycle Program Objectives.
EGCR Lattice Radial and Angular Power Distribution
EGCR Lattice Radial and Angular Power Distribution 2.6 w/o Enrichment
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