Annealing behavior of the hardening and ductility loss of an oxide-dispersion-strengthened (ODS) ferritic steel (16Cr–4Al) irradiated with high-energy heavy ions is studied. ²⁰Ne ions with 123.4 MeV supplied by a cyclotron was used to produce a quasi-uniform atomic region of atomic displacement damage and Ne concentration from surface to a depth of 33 μm in the specimens. Two atomic displacement levels (0.16dpa, 0.70dpa) were approached at about 220 K. The irradiated specimens were subsequently thermally annealed at room temperature, 473 K and 673 K, respectively. Hardness and ductility of the specimens were investigated with nano-indentation technique and small-punch test. The data of the nano hardness were fitted by Nix-Gao model to obtain the bulk equivalent hardness values. The irradiated specimens show observable hardening, which recedes monotonously with the increase of annealing temperature. The Arrhenius plots show a good linearity in the entire temperature range investigated, with an apparent activation energy of 0.13 ± 0.01 eV for both the two damage levels. Assuming that the hardening is caused by the self-interstitial-atom (SIA) clusters initially produced by the cascade damage, an activation energy of 0.70 ± 0.05 eV is deduced for the migration and coalescence process of the SIA-clusters. The small punch test (SPT) of the high-dose specimens shows that a minor ductility loss occurred under conditions as-irradiated or subsequently thermally annealed at 473 K, while a remarkable increase of the ductility loss was observed after the thermal annealing at 673 K, which coincides with the formation of nano-scale gas bubbles in high density in the specimen. It is indicated that the formation of bubbles has minor on the irradiation hardening. A comparison of three ODS ferritic steels Ne-ion-irradiated to 0.7 dpa/260 appm(Ne) shows that the ductility loss decreases with the increase of the sink strength of the oxide dispersoids/ferritic substrate interfaces.

研究了用高能重离子辐照的氧化物弥散强化（ODS）铁素体钢（16Cr-4Al）的硬化和延展性损失的退火行为。²⁰回旋加速器提供的具有123.4 MeV的Ne离子用于产生准均匀的原子位移损伤原子区域，并在样品中从表面到深度为33μm的Ne浓度。在约220 K时达到两个原子位移水平（0.16dpa，0.70dpa）。随后将被辐照的样品分别在室温下473 K和673 K进行热退火。用纳米压痕技术和小冲孔试验研究了试样的硬度和延展性。通过Nix-Gao模型拟合纳米硬度的数据，以获得总当量硬度值。辐照后的试样表现出可观察到的硬化，随着退火温度的升高单调后退。阿雷尼乌斯（Arrhenius）图在所研究的整个温度范围内显示出良好的线性，两种损伤水平的表观活化能均为0.13±0.01 eV。假设硬化是由级联损伤最初产生的自填隙原子（SIA）簇引起的，则推导了0.70±0.05 eV的活化能用于SIA团簇的迁移和聚结过程。高剂量样品的小冲孔试验（SPT）显示，在473 K辐照或随后进行热退火的条件下，发生了较小的延展性损失，而在673 K进行热退火后，观察到延展性损失显着增加。 ，这与样品中高密度纳米级气泡的形成相吻合。这表明在辐射硬化中气泡的形成很小。Ne离子辐照至0的三种ODS铁素体钢的比较。