Silicide-Strengthened Steel - A New Method of Wear Protection within Nuclear Environments

硅化物强化钢——核环境中磨损防护的新方法

• 批准号: EP/R000956/1
• 负责人: Michael Preuss
• 金额: $ 25.59万
• 依托单位: University of Manchester
• 依托单位国家: 英国
• 项目类别: Research Grant
• 财政年份: 2017
• 资助国家: 英国
• 起止时间: 2017 至 无数据
• 项目状态: 已结题
• 来源: https://gtr.ukri.org/projects?ref=EP%2FR000956%2F1
• 关键词: Silicide; Strengthened; Steel; New; Method

Cobalt-based (Co) steel alloys are extensively used in nuclear reactors, particularly in the valves and pumps employed in water-cooled reactors. This is because they provide outstanding wear resistance, and so improve component life and reduce maintenance requirements. However, these alloys are expensive, and also raise the radiation exposure of workers at nuclear utilities, due to the formation of Cobalt-60, a gamma-emitting radioactive isotope. For this reason, replacing Co-based hardfacing alloys in future nuclear reactors is highly desirable in terms of health and safety and cost, as well as long-term decommissioning. To date, however, alternative materials such as iron (Fe)- and nickel (Ni)-based alloys have not been able to match the outstanding properties of Stellite 6, a well-known Co-based alloy for hardfacing applications (i.e. applications where wear is of particular importance). In response to the EPSRC call for feasibility studies related to energy research, we propose to explore the manufacturability of novel silicide-strengthened stainless steels in order to deliver a new class of Co-free hardfacing materials for nuclear components, with high galling- and corrosion-resistance. We have discovered a new class of Fe-based alloys for hardfacing applications only very recently, providing a real and valuable opportunity to finally have a material system that can match Co-based alloys in their wear and corrosion performance, while also offering great cost advantages and reduced exposure risk for nuclear utility workers. Success in demonstrating the viability of this class of material, as proposed here, could further have great impact in many other areas where high-strength stainless steel solutions are required (such as in highly corrosive environments in the petrochemical industry).

钴基（Co）钢合金广泛用于核反应堆，特别是水冷反应堆中使用的阀门和泵。这是因为它们具有出色的耐磨性，从而延长了部件寿命并降低了维护要求。然而，这些合金是昂贵的，并且由于形成钴-60（一种伽马发射放射性同位素），还增加了核设施工人的辐射暴露。出于这个原因，在未来的核反应堆中取代钴基耐磨堆焊合金在健康和安全性和成本以及长期退役方面是非常可取的。然而，迄今为止，诸如铁（Fe）基合金和镍（Ni）基合金的替代材料还不能与钨铬钴合金6的优异性能相匹配，钨铬钴合金6是用于表面硬化应用（即，其中磨损特别重要的应用）的众所周知的钴基合金。为了响应EPSRC关于能源研究可行性研究的呼吁，我们建议探索新型硅化物强化不锈钢的可制造性，以提供一种新型的无钴耐磨堆焊材料，用于核部件，具有高的抗磨损和耐腐蚀性。我们最近才发现了一种用于表面硬化应用的新型铁基合金，这提供了一个真实的宝贵的机会，最终获得一种在磨损和腐蚀性能方面可与钴基合金相媲美的材料系统，同时还为核电站工人提供了巨大的成本优势和降低的暴露风险。成功证明这类材料的可行性，如本文所提出的，可能会进一步在许多其他需要高强度不锈钢解决方案的领域产生重大影响（例如在石化行业的高腐蚀性环境中）。

项目成果

Understanding the microstructural evolution of silicide-strengthened hardfacing steels

了解硅化物强化硬面钢的微观结构演变

• DOI: 10.1016/j.matdes.2018.09.015
• 发表时间: 2019
• 期刊: Materials & Design
• 影响因子: 8.4
• 作者: Bowden D

High compressive loading performance of a complex multi-phase hard-facing alloy explained through a highly elastic silicide phase

通过高弹性硅化物相解释复杂多相硬面合金的高压缩负载性能

• DOI: 10.1016/j.mtla.2023.101815
• 发表时间: 2023
• 期刊: Materialia
• 影响因子: 3.4
• 作者: Thomas R

The interaction of galling and oxidation in 316L stainless steel

316L 不锈钢中磨损和氧化的相互作用

• DOI: 10.1016/j.wear.2020.203234
• 发表时间: 2020
• 期刊: Wear
• 影响因子: 5
• 作者: Rogers S

Phase evolution within multiphase stainless steels during simulated hot isostatic pressing cycles

模拟热等静压循环过程中多相不锈钢的相演化

• DOI: 10.1016/j.mtla.2022.101411
• 发表时间: 2022
• 期刊: Materialia
• 影响因子: 3.4
• 作者: Bowden D

The identification of a silicide phase and its crystallographic orientation to ferrite within a complex stainless steel

复杂不锈钢中硅化物相的识别及其对铁素体的晶体取向

• DOI: 10.1016/j.jnucmat.2019.02.028
• 发表时间: 2019
• 期刊: Journal of Nuclear Materials
• 影响因子: 3.1
• 作者: Bowden D