Mechanical properties of calcium silicate hydrates (C-S-H) with C/S ratios of 0.75, 1, and 1.33 were examined with nanoindentation after gamma-adsorbed doses of 0.145, 0.280, 0.500, and 0.784 MGy, and were compared with control samples. Young' s modulus and stress relaxation tests showed no apparent trend with irradiation dose. Qualitatively, most of the irradiated samples were found to relax more than their respective controls, but not always in a statistically significant manner. Most of the Young' s modulus irradiated–control pairs showed marginally higher stiffness in the irradiated samples, but overall trends with irradiation dose were not obvious. Creep compliance was obtained for the samples irradiated at the highest dose and their respective controls. Two of the three irradiated samples exhibited less creep than their respective controls, but only one of which was statistically significant. The lack of clear changes in mechanical properties for these samples correlates with separate chemical analyses that showed no loss of interlayer water by exposure to irradiation or changes in the mean silicate chain length. Further research evaluating higher doses (25 and 200 MGy) representative of those received by concrete structures in nuclear power plants at prolonged operation is being carried out to complement the present study.

在γ吸附剂量为0.145、0.280、0.500和0.784 MGy后，用纳米压痕法检查了C / S比为0.75、1和1.33的水合硅酸钙水合物（CSH）的机械性能，并与对照样品进行了比较。杨氏模量和应力松弛试验表明，随着辐照剂量的增加，没有明显的趋势。定性地，发现大多数受辐照样品比其各自的对照更松弛，但并不总是以统计学上显着的方式松弛。大多数杨氏模量辐照-对照对在辐照样品中显示出稍高的刚度，但总体辐照剂量的趋势并不明显。对于以最高剂量辐照的样品及其相应的对照物，获得了蠕变柔量。三个受辐照样品中有两个显示的蠕变比其各自的对照小，但只有一个具有统计学意义。这些样品的机械性能没有明显变化，这与单独的化学分析有关，这些化学分析表明，暴露于辐照或平均硅酸盐链长的变化不会造成夹层水的损失。为了补充本研究，正在进行进一步研究，评估代表长期使用的核电站混凝土结构所接受的剂量更高的剂量（25和200 MGy）。这些样品的机械性能没有明显变化，这与单独的化学分析有关，这些化学分析表明，暴露于辐照或平均硅酸盐链长的变化不会造成夹层水的损失。为了补充本研究，正在进行进一步研究，评估代表长期使用的核电站混凝土结构所接受的剂量更高的剂量（25和200 MGy）。这些样品的机械性能没有明显变化，这与单独的化学分析有关，这些化学分析表明，暴露于辐照或平均硅酸盐链长的变化不会造成夹层水的损失。为了补充本研究，正在进行进一步研究，评估代表长期使用的核电站混凝土结构所接受的剂量更高的剂量（25和200 MGy）。