In this study, the structure damage and its influence on deuterium retention in the reduced-activation ferritic martensitic (RAFM) steel were investigated using heavy ions to simulate the displacement damage caused by neutron irradiation. Iron (Fe) and nickel (Ni) ions were applied as self-ions and other ions to irradiate steel samples. After Fe or Ni heavy ion irradiation, some amorphous cluster structures were evident, especially at the peak displacement damage region located at a depth of around 1.0 µm in the CLF-1 steel. When the displacement damage was higher than 2.0 dpa, the grain boundaries or boundary structures became obscured by the formation of other defects, such as dislocation clusters for samples irradiated by either Fe or Ni ions. The damaged samples irradiated by Fe or Ni heavy ions were exposed to deuterium plasma, and the deuterium release and retention behaviors were measured. The results showed that after being irradiated by Ni ions, the deuterium release peak increased with no changes of the release temperature. However, after Fe ions irradiation, the deuterium release peaks shifted to lower temperatures corresponding to an increase in the number of the low-energy capture sites, such as dislocations. The increase in the total deuterium retention in CLF-1 steel after heavy ion irradiation was less than 56%, which was much lower than those of tungsten materials.

在这项研究中，使用重离子模拟中子辐照引起的位移损伤，研究了还原活化铁素体马氏体（RAFM）钢中的结构损伤及其对氘保留的影响。铁（Fe）和镍（Ni）离子作为自离子和其他离子被施加到钢样品上。在Fe或Ni重离子辐照后，明显出现了一些无定形簇结构，特别是在CLF-1钢中位于约1.0 µm深度处的峰位移损伤区域。当位移损伤高于2.0 dpa时，其他缺陷的形成会掩盖晶界或晶界结构，例如铁或镍离子辐照样品的位错簇。Fe或Ni重离子辐照的损坏样品暴露于氘等离子体中，并测量了氘的释放和保留行为。结果表明，在镍离子辐照后，氘的释放峰增加，且释放温度没有变化。然而，在Fe离子辐照之后，氘的释放峰移至较低的温度，这对应于低能俘获位点如位错数目的增加。重离子辐照后CLF-1钢中总氘保留量的增加小于56％，远低于钨材料。氘的释放峰转移到较低的温度，这对应于低能捕获位点（例如位错）的增加。重离子辐照后CLF-1钢中总氘保留量的增加小于56％，远低于钨材料。氘的释放峰转移到较低的温度，这对应于低能捕获位点（例如位错）的增加。重离子辐照后CLF-1钢中总氘保留量的增加小于56％，远低于钨材料。