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Technical Report Archive and Image Library
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Report (U.S. Atomic Energy Commission)
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UNT Libraries Government Documents Department
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Report (U.S. Atomic Energy Commission)
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Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures
Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator
Plutonium Recycle Critical Facility: Final Safeguards Analysis
One-Pion Exchange and the Optical Model
Hazards Report for SM-1 Core Temperature and Flow Instrumentation (Task XIV) Covering Special Test Procedures.
Salt Bath Heat Transfer Rates for Uranium Plate
Simplified Power Conversion: Unit Study
Comparative Study of PuC-UC and PuO₂-UO₂ as Fast Reactor Fuel
Hazards Report for PM-2A Core II
Thermal Analysis of SM-1 Core III
Army PWR Support and Development Program Six Months Summary Report : October 1, 1961 - March 31, 1962
Pulse Amplifier Manual
Experimental Studies of Transient Effects in Fast Reactor Fuels
High Power Density Development Project: Interim Report, 300 MWe HPD Conceptual Design Study
Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants
EOCR Control Rod and Driver Fuel Hydraulic Tests
BWR Reference Design for PL-3
PL-3 Phase I Task 3 Research and Development Report
PWR Preliminary Design for PL-3
Preliminary Technical Report SM-1 Core III with Type 3 Elements
Prediction of the Critical Heat Flux in Forced Convection Flow
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