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Multiscale Modeling of Radiation Damage: Radiation Hardening of Pressure Vessel Steel
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  • Multiscale Modeling of Radiation Damage: Radiation Hardening of Pressure Vessel Steel
  • Multiscale Modeling of Radiation Damage: Radiation Hardening of Pressure Vessel Steel
저자명
Kwon. Junhyun,Kwon. Sang Chul,Hong. Jun-Hwa
간행물명
Journal of the Korean Nuclear Society
권/호정보
2004년|36권 3호|pp.229-236 (8 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

Radiation hardening is a multiscale phenomenon involving various processes over a wide range of time and length. We present a multiscale model for estimating the amount of radiation hardening in pressure vessel steel in the environment of a light water reactor. The model comprises two main parts: molecular dynamics (MD) simulation and a point defect cluster (PDC) model. The MD simulation was used to investigate the primary damage caused by displacement cascades. The PDC model mathematically formulates interactions between point defects and their clusters, which explains the evolution of microstructures. We then used a dislocation barrier model to calculate the hardening due to the PDCs. The key input for this multiscale model is a neutron spectrum at the inner surface of reactor pressure vessel steel of the Younggwang Nuclear Power Plant No.5. A combined calculation from the MD simulation and the PDC model provides a convenient tool for estimating the amount of radiation hardening.