Structure and properties of nickel-rich nuclear pressure vessel steel

目前用于核反应堆压力容器的经典钢由于寿命增加的需求而需要被替换。提出了一种新的富镍候选合金，该合金具有更高的力学性能.然而，对该合金的表征有限，因此存在实施该候选合金的潜在风险。因此，本项目的目的是对不同热处理条件下的晶粒结构进行定量研究。将进一步表征和模拟冷却条件方面的微观结构和性能的演变，导致定量模型的发展。基于这些先前的目的，将利用实验来确定这种合金的电子束焊接是否可行，目的是推断这种富镍候选合金是否适合于所需的应用。

A classical steel currently utilised for nuclear reactor pressure vessels is needing to be replaced due the demand for increased lifetime. A new nickel -rich candidate alloy has been suggested due the enhanced mechanical properties. However, limited characterisation of this alloy has been undertaken and thus potential risks of implementing this candidate alloy are present. Thus it is the aim of this project to develop a quantitative understanding of the grain structure with regard to varying heat treatments. Further characterisation and modelling of evolution of the microstructure and properties with regard to cooling conditions will be undertaken leading to the development of quantitative models. Based on these prior aims experiments will be utilised in order to ascertain whether electron beam welding of this alloy will be viable, with the objective to deduce if this nickel-rich candidate alloy is suitable for the desired application.