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Technical Report Archive and Image Library
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Construction Completion Report: CAI-816, 100-N Reactor Plant
The Effect of Deionized Water on the Reactor Effluent Activities: Part 2 - Zirconium and Aluminum Clad Fuel
The H-4, H-5, and H-6 Irradiation Experiments: Irradiation of N-Reactor Graphite, Interim Report Number 1
Plutonium Recycle Critical Facility: Final Safeguards Analysis Supplements
Development and Demonstration of an Ion-Exchange Process for Kilogram-Scale Production of High Purity Promethium
A Method for Beta-Gamma Hand and Shoe Counting Under Varying Background Conditions
Specifications for Swage Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-M)
Specifications for Vibrationally Compacted, Mixed Oxide (UO2-PuO2), Fuel Elements for the Plutonium Recycle Test Reactor (MARK I-L)
"Crud" Scrubbing with a Purex-Type Zebra Cartridge
Notes on Lattice Parameter Calculations
Final Report, Design Test PR-20 Calandria Characteristics
Darex Pilot Plant Studies
Effect of the PRTR High Pressure Loop on Plutonium Recycle Program Objectives
Neutron Age in Graphite-Water Lattices.
3 Plant Radiation Study Interim Report #5- Part II Data on Gamma Shielding of Special Plutonium Samples
Limitations for Existing Storage Tanks for Radioactive Wastes from Separations Plants
Protection of Carbon Steel from Atmospheric Corrosion
Controlled Temperature Irradiation of Graphite Interim Report No. 4. PT-IP-22A
Transient Pressures Developed by Sodium-Nitric Acid Reactions
Distribution of the Actinide Elements in the Molten System: KCI-AICI3-AI
Accuracy of Volume Measurements in a Large Process Vessel
Plutonium Oxalate Disk Filter and Filter Media Studies
A Rotating Source for Calibration Purposes
Comments on Engineering Review of PRTR by Atomic Power Equipment Department
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