r5.03.23 Elasto-plastic behavior under metal irradiation: application to tank internals

Summary:

This document presents the writing of a law of behavior under irradiation of 304 and 316 stainless steels, materials of which the internal structures of nuclear reactor vessels are made. The formalism of the model is identical for both materials, only the parameters are different from one material to another. The model takes into account, in addition to thermo-elasticity, plasticity, creep under irradiation, as well as possible swelling under neutron flow.

The implementation of the model and its limitations are detailed here.

This law of behavior, if it was developed for needs specific to EDF, can be used to account for the behavior of any material with characteristics of plasticity, creep under irradiation, and swelling.

• 1. Introduction
• 2. Formulation of the law of behavior
• 3. Implementation: implicit integration
• 4. Material coefficients
  • 4.1. Thermo-elasticity
  • 4.2. Plasticity
  • 4.3. Irradiation creep
  • 4.4. Swelling
• 5. The limitations of the model
• 6. Applying the model in Code_Aster
• 7. Bibliography
• 8. Document version history