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2. Material degradation and ageing in BWR service and their mitigation
2.1 Material ageing and degradation
During prolonged operation, the (synergistic) effects of the thermo-mechanical and thermo-hydraulic loading, increased temperatures, reactor coolant and the irradiation field can progressively result in:
changes of material properties (strength, toughness, corrosion resistance, etc.)
initiation and propagation of cracks (SCC, fatigue)
changes of component dimension/geometry (FAC, plastic deformations, distortions, etc.)
These slowly progressing, operation-induced changes or degradation/damage in the materials are called physical ageing. There are around 50 different potential degradation mechanism...
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Material degradation and ageing in BWR service and their mitigation
Bibliographical sources
Norms and standards
- Standard Specification for Hot-Rolled and Cold-Finished Zirconium Alloy Bars, Rod, and Wire for Nuclear Application - ASTM B351/B351M -
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The Ultimate Scientific and Technical Reference