**About this Abstract** |

**Meeting** |
**2016 TMS Annual Meeting & Exhibition
** |

**Symposium
** |
**Computational Materials Engineering for Nuclear Reactor Applications
** |

**Presentation Title** |
Predicting the Radiation Dependent Flow Stress and Cleavage Failure in RPV steels using Crystal Plasticity |

**Author(s)** |
Pritam Chakraborty, Yongfeng Zhang, S. Bulent Biner |

**On-Site Speaker (Planned)** |
Pritam Chakraborty |

**Abstract Scope** |
The ductile-brittle transition temperature (DBTT) shifts of fracture toughness increase with irradiation, which increase the failure probability of reactor pressure vessels. Hence accurate assessment of DBTT is necessary to ensure safe operation of nuclear reactors. In recent years, there has been a paradigm shift to utilize coupled engineering-microstructure-atomistic scale models to obtain the variation of flow stress, damage parameters and DBTT shifts, due to the lack of experimental data. In the present work, a similar approach is followed where a dislocation-density based crystal plasticity model is utilized to obtain the variation of flow stress with irradiation in ferritic steels. In the model, the interaction between matrix dislocations, and, irradiation induced SIA loops and precipitates are incorporated. Further, the probability of cleavage initiation in representative polycrystalline microstructures with varying dose-levels has been investigated. Comparison with available experimental data is also made. |

**Proceedings Inclusion?** |
Planned: A print-only volume |