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Short Term and Long Term Analysis of Radiation Damage in Carbon Based Steels with Emphasis on Reactor Pressure Vessel

Zamzamian, Mehrdad | 2020

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  1. Type of Document: Ph.D. Dissertation
  2. Language: Farsi
  3. Document No: 53360 (46)
  4. University: Sharif University of Technology
  5. Department: Energy Engineering
  6. Advisor(s): Samadfam, Mohammad; Feghhi, Amir Hossein
  7. Abstract:
  8. Steels as structural materials of pressure vessels of nuclear reactors, in addition to high temperatures and pressures, are exposed to ionizing radiation such as neutrons. The primary effects of damage caused by exposing these solids to radiation are the displacement of atoms from their equilibrium positions and the formation of point defects and damage clusters caused by damage accumulation due to displacement cascades produced by transmitting the energy of the incident particle to an atom by interactions such as elastic and inelastic scatterings neutrons with the nucleus. These microstructural changes cause large structural defects such as swelling, cracking, cracking, creep, reducing ductility and increasing length which will have a significant impact on the performance and useful life of the reactor pressure vessel alloy. Experimental studies on carbon-based steels used in nuclear reactors have been costly and sometimes non-operational due to limitations in prototyping and facilities. In addition, it is impossible to study the time scale phenomena in picoseconds, empirically. Therefore, simulating such phenomena as radiation damage in these solids is considered a very powerful tool in studying their effects on carbon-based steels. In this thesis, we aim to study radiation-induced damages in carbon-based steels on the short-term timescales by using molecular dynamics simulations and the effects of defects such as dislocation, grain boundary and carbon precipitates on the micro- and macro-structure properties of these materials exposing to the radiation. To study the long-term effects of radiation damage, we used object kinetic Monte Carlo simulations to study the effects of thermal migrations of radiation-induced point defects produced on these materials by applying the results of first-principles calculations and molecular dynamics simulations
  9. Keywords:
  10. Pressure Vessel ; Kinetic Monte Carlo Model ; Ab Initio Calculation ; Molecular Dynamics ; Radiation Damage ; Neutron Radiation ; Nuclear Reactors

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