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Orientation relationship of the fcc-to-bcc transformation in DIN 1.4970 austenitic stainless steels due to dissolution corrosion in liquid Pb-Bi eutectic

机译:DIN 1.4970奥氏体不锈钢在DIN 1.4970奥氏体不锈钢中的取向关系因液态PB-BI共晶溶出度腐蚀

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The deployment of Generation-IV lead-cooled fast reactors (Gen-IV LFRs) requires thecompatibility between the candidate structural/fuel cladding steels and the inherently corrosivelead-based alloy coolants. Therefore, understanding the liquid metal corrosion behaviour ofcandidate structural/cladding materials in contact with heavy liquid metal coolants is crucial for thedesign and safe operation of Gen-IV lead-fast reactors (LFRs). The Multipurpose hYbrid ResearchReactor for high-tech Applications (MYRRHA) system, currently under development at SCK•CEN,uses the lead-bismuth eutectic (LBE) alloy as both primary coolant and spallation target. TheMYRRHA candidate steels are: the 316L structural steel and the DIN 1.4970 fuel cladding steel;both steels are austenitic (fcc) stainless steels.At sufficiently high temperatures (T >450 °C) and low LBE oxygen concentrations (CO < 10~(-8)mass%), these steels are susceptible to dissolution corrosion, a particularly undesirable corrosionmechanism that can jeopardize the structural integrity of the reactor components. Dissolutioncorrosion is manifested by the progressive transfer of steel alloying elements to the LBE coolant;dissolution starts by the selective leaching of the highly soluble steel alloying elements (Ni, Mn,Cr), which in turn leads to the ferritization (fcc-to-bcc phase transformation) of the dissolutionaffectedzone due to the removal of the austenite stabilizers (Ni, Mn).In literature, the austenite to ferrite (γ→α) phase transformations have mainly been studied whendepending on the steel alloying and thermal processing of the steels. These transformations canoccur in a displacive manner by a coordinated movement of atoms or through a diffusion-drivenreconstructive transformation mechanism. Specific orientation relationships (ORs) have beenrepeatedly found between the two phases. In steels, for the vast majority of cases, the Kurdjumov-Sachs (K-S) and/or Nishiyama-Wassermann (N-W) ORs have been reported.In this work, the focus is on the less studied austenite-to-ferrite phase transformation, whichoccurs when austenitic stainless steels are exposed to heavy liquid metals (HLMs), such as leadand lead-bismuth eutectic (LBE), under specific exposure conditions (i.e., high temperatures, lowoxygenHLMs). A large statistical population of γ/α phase boundaries was analyzed by electronbackscatter diffraction (EBSD) on LBE-exposed austenitic stainless steels, in order to determinethe dominant OR between several selected ORs (i.e., Bain, K-S, N-W and Pitsch). The Pitschmodel was found to be the dominant orientation relationship, which is unique for γ→α bulktransformations in steels. The unusual nature of the transformation, which involves loss of alloyingelements and the presence of an interfacial liquid metal layer, is discussed to explain this finding.
机译:生成-4V铅冷却的快电抗器(GEN-IV LFR)的部署需要 候选结构/燃料包层钢与固有腐蚀性之间的兼容性 铅基合金冷却剂。因此,了解液体金属腐蚀行为 与重型液体金属冷却剂接触的候选结构/包层材料对于该来说是至关重要的 Gen-IV铅铅反应器(LFR)的设计和安全操作。多功能杂交研究 用于高科技应用(MYRRHA)系统的反应堆,目前正在开发的SCK•CEN, 使用铅铋共晶(LBE)合金作为主要冷却剂和脱晶靶。这 Myrrha候选钢是:316L结构钢和DIN 1.4970燃料包层钢; 两个钢都是奥氏体(FCC)不锈钢。 在足够高的温度(t> 450℃)和低LbE氧浓度(CO <10〜(-8) 质量%),这些钢易于溶出腐蚀,是一种特别不希望的腐蚀 可以危害反应器组分的结构完整性的机制。解散 通过钢合金元素对LBE冷却剂的逐步转移表现出腐蚀; 溶解通过高可溶性钢合金元素(Ni,Mn,CN的选择性浸出来开始 CR),其又导致溶解的脱硫截止物(FCC-TO-BCC相变) 由于去除奥氏体稳定剂(Ni,Mn)而导致的区域。 在文献中,奥氏体向铁氧体(γ→α)相变,主要是何时研究 取决于钢合金化和钢的热加工。这些转变可以 通过各自的原子的协调运动或通过扩散驱动的方式以脱离方式发生 重建转型机制。已经具体的方向关系(或)已成为 反复发现两阶段。在钢材中,对于绝大多数案件,Kurdjumov- 据报道了Sachs(K-S)和/或Nishiyama-Wassermann(N-W)或者。 在这项工作中,重点是较少研究的奥氏体到铁氧体相变,这 当奥氏体不锈钢暴露于重液体金属(HLMS)时发生,例如铅 和铅铋共晶(LBE),在特定的暴露条件下(即,高温,Lowoxygen HLMS)。电子通过电子分析了γ/α相界的大统计群 在LBE暴露的奥氏体不锈钢上反向散射(EBSD),以确定 占主导地位或几个选择的或在几个之间(即,Bain,K-S,N-W和Pitsch)之间。 Pitsch. 模型被发现是主导的取向关系,这对于γ→α散装是独特的 钢材的转变。转化的不寻常性质,涉及丧失合金化 讨论了元素和界面液态金属层的存在以解释这一发现。

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