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3 3. Electrochemical thermodynamics of water-cooled nuclear reactor heat-transport circuits — Digby D Macdonald (1981) | RDL Network
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3 3. Electrochemical thermodynamics of water-cooled nuclear reactor heat-transport circuits
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Digby D Macdonald
University of California, Berkeley
3 3. Electrochemical thermodynamics of water-cooled nuclear reactor heat-transport circuits
Chapter In A Book
1981
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Measurement of pH in Simulated Water-Cooled Nuclear Reactor Heat Transport Circuits
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Electrochemical techniques for monitoring and controlling corrosion in water-cooled nuclear reactor systems
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Article
1996
Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits — III: Effect of Reactor Power Level
Tsung‐Kuang Yeh
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Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—II: Simulation of Operating Reactors
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Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—I: The DAMAGE-PREDICTOR Algorithm
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