Magnetic hysteretic characterization of the irradiation-induced embrittlement of Fe, Fe-Cu model alloys, and reactor pressure vessel steel
Magnetic hysteretic characterization of the irradiation-induced embrittlement of Fe, Fe-Cu model alloys, and reactor pressure vessel steel
复制标题
Fe、Fe-Cu 模型合金和反应堆压力容器钢辐照脆化的磁滞特性
DOI：
10.1016/j.jmmm.2008.04.019
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发表时间：
2008
影响因子：
2.7
通讯作者：
L. Dupré
中科院分区：
文献类型：
--
作者：
L. Vandenbossche;M. Konstantinović;L. Dupré
众所周知，中子辐照会导致铁基材料脆化；在核工业中，这种效应可能对反应堆压力容器钢有害。在本文中，我们研究了四种材料（即名义纯 Fe、Fe-0.1 wt% Cu 和 Fe-0.3wt% Cu 模型合金）以及反应堆压力容器钢 JRQ A533-B 因中子辐照而引起的磁滞行为的变化。与磁化环形状相关的两个参数，即最大相对微分磁导率和局部相互作用场分布的峰值强度，被测量为中子注量的函数。对于所有材料，由于辐射诱导形成纳米尺寸缺陷，这两个参数都随着注量的增加而减小。无论脆化的来源如何，脆化过程中磁性参数的这种下降趋势都是显而易见的，脆化的来源可能只是铜沉淀（Fe-Cu 的热老化），只是基体损伤（纯 Fe 的辐照），或两种机制（Fe-Cu 或钢的辐照）。磁性参数相对变化高达 40%，这表明磁性表征在评估辐照引起的材料硬化和脆化方面具有潜力。
Neutron irradiation is known to cause embrittlement of iron-based materials; in the nuclear industry, this effect can be detrimental for reactor pressure vessel steels. In this paper, we investigate the variations of the magnetic hysteretic behavior due to neutron irradiation, for four materials, i.e. nominally pure Fe, Fe-0.1 wt% Cu and Fe-0.3wt%Cu model alloys, and a reactor pressure vessel steel, JRQ A533-B. Two parameters related to the magnetization loop shape, i.e. maximum relative differential permeability and peak intensity of local interaction field distribution, are measured as a function of neutron fluence. For all materials both parameters decrease with increasing fluence, due to the irradiation-induced formation of nano-size defects. This decreasing trend in magnetic parameters during embrittlement is noticeable regardless the origin of the embrittlement, which can be only Cu-precipitation (thermal aging of Fe–Cu), only matrix damage (irradiation of pure Fe), or both mechanisms (irradiation of Fe–Cu or steel). The magnetic parameters relatively change up to 40%, which indicates the potential of magnetic characterization to assess irradiation-induced material hardening and embrittlement.