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Hanford Works Reports
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APDAC-I, A PCTR Data Analysis Code for the IBM 709
Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor.
Scavenging as a Predisposal Treatment for NPR Decontamination Wastes
A Wrist Badge Film Dosimeter for Hand Dose Measurement
Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing
Heat Transfer Testing
Experimental PRTR Moderator Flow Distribution Results
Radiobiological Studies of the Columbia River Through December, 1955
Mechanical Features of a Continuous Ion Exchange Unit
Hanford Test Pile
Analysis of High Purity Water by Spectrochemistry
Examination of Irradiated Uranium-Magnesium Matrix Fuel Material
Nuclear Safety Consideration For Continuous Ion Exchange Column Design
Purex Waste Storage. Part I - 241-A Waste Storage Facilities
Modification of a 1706-KER Loop for Boiling
The Results of the D-12 Boil Up Test and Recommendations to Improve the Performance of Bayonet Tube Bundles
An Analysis of the In-Line Uranium Photometer Data from Purex Hot Semi-Works Runs PX-2 Through PX-9
Flow Stress Recovery of Zircaloy-2
Physics Research Quarterly Report: July, August, September 1955
Purex Plant Small Pulse Generator Operation
Hypothesis Concerning Irradiation Embrittlement of Uranium
Rear Face Monitoring by Television: Supplementary Report
Analysis of Errors to be Expected in Measuring the Neutron Absorption Cross Section of C-12
A Rapid Method for Determining Preferred Orientation in Rolled Uranium Rods
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