Characterization of Oxide Films on Stainless Steel Surfaces of Boiling Water Reactor Primary Cooling Systems
Author:
Affiliation:
1. Energy Research Laboratory, Hitachi, Ltd., Moriyamacho, Hitachi, Ibaraki 316, Japan
Publisher
Informa UK Limited
Subject
Nuclear Energy and Engineering
Link
https://www.tandfonline.com/doi/pdf/10.13182/NSE87-A20437
Reference11 articles.
1. A Calculation Model for Predicting Concentrations of Radioactive Corrosion Products in the Primary Coolant of Boiling Water Reactors
2. W. E. BERRY, and R. B. DIEGLE, “Survey of Corrosion Product Generation, Transport, and Deposition in Light Water Nuclear Reactors,” EPRI NP-522, Final Report, Electric Power Research Institute (Mar. 1979).
3. The Transport of Radioactive Corrosion Products in High-Temperature Water II. The Activation of Isothermal Steel Surfaces
4. L. D. ANSTINE, “BWR Radiation Assessment and Control Program: Assessment and Control of BWR Radiation Fields,” EPRI NP-3114, Vol.2, Final Report, Electric Power Research Institute (May 1983).
5. Performance assessment of Class 1E pressure transmitters subjected to environmental stresses
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