Post-irradiation creep rupture properties of FBR grade 316 SS structural material
Post-irradiation creep rupture properties of FBR grade 316 SS structural material
复制标题
FBR 级 316 SS 结构材料的辐照后蠕变断裂性能
DOI：
10.1016/s0022-3115(98)00776-4
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发表时间：
1999
影响因子：
3.1
通讯作者：
S. Onose
中科院分区：
文献类型：
--
作者：
N. Miyaji;Y. Abe;S. Ukai;S. Onose
为了研究中子辐照对结构材料用FBR级316不锈钢（316FR）蠕变性能的影响，对在JOYO和JMTR中辐照的316不锈钢试样进行了辐照后蠕变断裂试验。低于约0.3 dpa的中子照射，316 FR的断裂强度几乎保持相同的水平，未照射的一个，因为精细分散的沉淀物应该捕获的晶粒内的氦泡，并防止氦在晶界处的积累。然而，超过约0.3 dpa，观察到316 FR的蠕变断裂强度降低和沿晶脆性断裂模式。这种现象可归因于磷化物沉淀物的生长，磷化物沉淀物的生长降低了氦在晶粒内的捕集能力和磷在基体中的固溶强化。这些结果可用于聚变堆结构材料的设计。
In order to investigate the effects of neutron irradiation on the creep properties of FBR grade type 316 stainless steel for structural material (316FR), post-irradiation creep rupture tests were conducted in the specimens irradiated in JOYO and JMTR. Below the neutron exposure of around 0.3 dpa, the rupture strength of 316FR almost maintains the same level of unirradiation one, since finely dispersed precipitates should trap the helium bubbles within grains and prevent the helium accumulation at grain-boundaries. However, beyond about 0.3 dpa, a reduction of creep rupture strength and intergranular brittle fracture mode were observed in 316FR. Such phenomena could be attributed to the growth of phosphide precipitates which deteriorates both the trapping capability of helium within the grain and solution strengthening of phosphorus in matrix. These results are applicable to the design of structural materials in fusion reactor.