当前位置: X-MOL 学术npj Mater. Degrad. › 论文详情
Our official English website, www.x-mol.net, welcomes your feedback! (Note: you will need to create a separate account there.)
Development of a numerical model for simulating stress corrosion cracking in spent nuclear fuel canisters
npj Materials Degradation ( IF 5.1 ) Pub Date : 2021-05-26 , DOI: 10.1038/s41529-021-00174-5
Xin Wu , Fengwen Mu , Scott Gordon , David Olson , Stephen Liu , Zeev Shayer , Zhenzhen Yu

Prediction and detection of the chloride-induced stress corrosion cracking (CISCC) in Type 304 stainless steel spent nuclear fuel canisters are vital for the lifetime extension of dry storage canisters. This paper conducts a critical review that focuses on the numerical modeling and simulation on the research progress of the CISCC. The numerical models emphasizing the residual stress, susceptible microstructure, and corrosive environment are summarized individually. Meanwhile, the simulation studies on the role of hydrogen-assisted cracking are reviewed. Finally, a multi-physical numerical model, which combines the different fields is proposed based on our recent investigation.



中文翻译:

模拟乏燃料罐中应力腐蚀开裂的数值模型的开发

预测和检测304型不锈钢废核燃料罐中氯化物引起的应力腐蚀开裂(CISCC)对于延长干燥罐的使用寿命至关重要。本文对CISCC的研究进展进行了重要的综述,重点是数值建模和仿真。分别总结了强调残余应力,易受影响的微观结构和腐蚀环境的数值模型。同时,对氢辅助裂解作用的模拟研究进行了综述。最后,根据我们最近的研究,提出了一个结合了不同领域的多物理场数值模型。

更新日期:2021-05-26
down
wechat
bug