无钴涂层作为钠冷快堆堆焊材料候选材料的评价及钠中氧对摩擦学性能的影响

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2019-08-01 DOI:10.1051/epjn/2019025
F. Rouillard, B. Duprey, J. Courouau, R. Robin, P. Aubry, C. Blanc, M. Tabarant, H. Maskrot, L. Nicolas, M. Blat-Yrieix, G. Rolland, T. Marlaud
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引用次数: 3

摘要

运行钠冷快堆(SFRs)所产生的反馈表明了材料摩擦学性能的重要性。在不允许磨损或粘着磨损的情况下,通常在摩擦表面涂上耐磨涂层的堆焊合金。最常用的涂层是钴基合金,名为斯泰利特6®,因为它具有出色的摩擦和磨损性能。然而,钴是一种在反应堆中活化的元素,在反应堆维护和退役期间导致复杂的安全管理。因此,CEA, EDF和FRAMATOME之间的合作工作已经启动,为名为ASTRID的600兆瓦钠冷快堆项目选择有前途的无钴堆焊合金。从文献综述中选择了几种镍基合金,并根据RCC-MRx规范(AFCEN规范)在17Cr奥氏体不锈钢316L(N)上进行了等离子转移电弧或激光熔敷。在众多性能要求中,良好的腐蚀性能和良好的摩擦磨损性能在钠中是必不可少的。本文显示了这些属性的第一个结果。首先,通过在纯化钠中400°C下5000小时的暴露试验来评估所有涂层的腐蚀行为。所有涂层在钠中均表现出可接受的腐蚀行为。最后,在设计的专用设备上研究了一种候选合金NiCrBSi合金在钠中的摩擦磨损性能。考察了钠中氧浓度对摩擦磨损性能的影响。
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Evaluation of cobalt free coatings as hardfacing material candidates in sodium-cooled fast reactor and effect of oxygen in sodium on the tribological behaviour
The feedback produced by operating Sodium-cooled Fast Reactors (SFRs) has shown the importance of material tribological properties. Where galling or adhesive wear cannot be allowed, hardfacing alloys, known to be galling-resistant coatings, are usually applied on rubbing surfaces. The most used coating is the cobalt-base alloy named Stellite 6® because of its outstanding friction and wear behaviour. Nevertheless, cobalt is an element which activates in the reactor leading to complex management of safety during reactor maintenance and mainly decommissioning. As a consequence, a collaborative work between CEA, EDF and FRAMATOME has been launched for selecting promising cobalt-free hardfacing alloys for the 600 MWe Sodium-cooled Fast breeder reactor project named ASTRID. Several nickel-base alloys have been selected from literature review then deposited by Plasma Transferred Arc or Laser Cladding on 17Cr austenitic stainless steel 316L(N) according to RCC-MRx Code (AFCEN Code). Among the numerous properties required for qualifying their use as hardfacing alloys in SFR, good corrosion behaviour and good friction and wear behaviour in sodium are essential. First results on these properties are shown in this article. Firstly, the corrosion behaviour of all coatings was evaluated through exposure tests in purified sodium for 5000 h at 400 °C. All coatings showed an acceptable corrosion behaviour in sodium. Finally, the friction and wear properties of one alloy candidate, NiCrBSi alloy, were studied in sodium in a dedicated designed facility. The influence of the oxygen concentration in sodium on the friction and wear properties was evaluated.
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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