Modeling Water Chemistry, Electrochemical Corrosion Potential, and Crack Growth Rate in the Boiling Water Reactor Heat Transport Circuits—I: The DAMAGE-PREDICTOR Algorithm
Author:
Affiliation:
1. The Pennsylvania State University, 517 Deike Building, University Park, Pennsylvania 16802
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE95-A24148
Reference21 articles.
1. Viability of Hydrogen Water Chemistry for Protecting In-Vessel Components of Boiling Water Reactors
2. A coupled environment model for stress corrosion cracking in sensitized type 304 stainless steel in LWR environments
3. Water radiolysis and its effect upon in-reactor zircaloy corrosion
4. Mathematical model of the radiolysis of water in the active zone of an RBMK reactor
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