Silicide-Strengthened Steel - A New Method of Wear Protection within Nuclear Environments
Silicide-Strengthened Steel - A New Method of Wear Protection within Nuclear Environments
批准号:
EP/R000956/1
负责人:
Michael Preuss
金额:
$25.59万
依托单位:
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
项目状态:
已结题
起止时间:
2017 至 --
中文摘要
钴基(Co)钢合金广泛应用于核反应堆,特别是水冷反应堆的阀门和泵。这是因为它们提供了出色的耐磨性,从而提高了组件寿命并减少了维护要求。然而,这些合金价格昂贵,而且由于形成钴-60(一种发射伽马射线的放射性同位素),也会增加核电站工作人员的辐射暴露。因此,在未来的核反应堆中,从健康、安全、成本以及长期退役的角度来看,替换钴基堆焊合金是非常可取的。然而,到目前为止,替代材料,如铁(Fe)和镍(Ni)基合金,还不能与Stellite 6的卓越性能相匹配,Stellite 6是一种众所周知的钴基合金,用于堆焊应用(即磨损特别重要的应用)。为了响应EPSRC对能源研究相关可行性研究的呼吁,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co堆焊材料,用于核部件,具有高抗磨损和耐腐蚀性。我们最近才发现了一类新的铁基合金用于堆焊应用,这为最终拥有一种在磨损和腐蚀性能上可以与钴基合金相匹配的材料系统提供了一个真正的和宝贵的机会,同时也为核电工作人员提供了巨大的成本优势和降低暴露风险。正如本文所提出的,成功证明这类材料的可行性,可能会进一步对需要高强度不锈钢解决方案的许多其他领域产生重大影响(例如石油化工行业的高腐蚀性环境)。
英文摘要
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).
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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]
通讯作者:
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]
通讯作者:
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]
通讯作者:
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]
通讯作者:
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]
通讯作者:
Bowden D
共 6 条
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-
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负责人:Michael Preuss
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依托单位:
From Processing to Simulated In-Reactor Performance of Zr Cladding.
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High Fidelity Ion Beam Simulation of High Dose Neutron Irradiation
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Dislocation-Microstructure Interaction at a Crack Tip - In Search of a Driving Force for Short Crack Growth
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Engineered Zircaloy Cladding Modifications for Improved Accident Tolerance of LWR Fuel
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New Nuclear Manufacturing (NNUMAN)
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-
项目类别:Research Grant
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资助金额:$524.39万
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财政年份:2012
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依托单位:
Enhancing nuclear fuel efficiency through improved understanding of irradiation damage in zirconium cladding
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依托单位:
Irradiation Effects on Flow Localisation in Zirconium Alloys
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项目类别:Research Grant
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资助金额:$40.63万
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依托单位:
Performance and Reliability of Metallic Materials for Nuclear Fission Power Generation
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资助金额:$48.52万
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依托单位:
Strain mapping of individual grains using diffraction contrast tomography
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项目类别:Research Grant
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资助金额:$15.98万
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依托单位:
A fundamental study of deformation mechanisms in advanced polycrystalline nickel-base superalloys
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项目类别:Research Grant
-
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-
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依托单位:
Zirconium alloys for high burn-up fuel in current and advanced light water-cooled reactors
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-
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依托单位:
Effective Structural Unit Size in Polycrystals: Formation, Quantification and Micromechanical Behaviour
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海外基金