Subject
Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics
Reference24 articles.
1. EPRI PWR Fuel Cladding Corrosion PFCC Model: Volume 2 Corrosion Theory and Rate Equation Development;Gilmer,1996
2. Effects of pressurized water reactor (PWR) coolant chemistry on zircaloy corrosion behavior;Karlsen,1994
3. A High Fidelity Multiphysics Framework For Modeling CRUD Deposition on PWR Fuel Rods;Walter,2016
4. A possible mechanism for corrosion product transport and radiation field growth in a pressurized water reactor primary circuit;Burrill;Nucl. Technol.,1977
5. Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments;Xue;J. Nucl. Mater.,2022