To address the lack of high‑temperature irradiation performance data for the austenitic stainless steel 316H,the material used for the reactor pressure vessel of a fourth‑generation high‑temperature gas‑cooled microreactor,at the design operating temperature of 550 ℃,a research plan involving irradiation damage tests and aging tests was proposed.The SRIM software was used to simulate the trajectories and irradiation damage defects of energetic ions (He2+) incident on the material.Combined with high‑temperature irradiation tests under different cumulative irradiation doses (0.005,0.05,0.5 dpa) and an irradiation aging test at 650 ℃ for 100 h,the evolution laws of the material's high‑temperature damage behavior and aging behavior with microstructure were established.The results show that at the design temperature of 550 ℃,316H exhibits good irradiation resistance.The irradiation damage layer is approximately several micrometers thick,and the damage mainly manifests as microvoids and dislocations.After aging at 650 ℃ for 100 h,carbides precipitate along grain boundaries,with C and Mo elements enriching at the grain boundaries and Cr element depleting near the grain boundaries,presenting a certain risk of failure.This study provides a reference for subsequent engineering implementation of in‑reactor irradiation tests.
| 科 Family | 属数 Number of genus | 种数 Number of species | 占总种数比例 Percentage of total species (%) | 属 Genus | 种数 Number of species | 占总种数比例 Percentage of total species (%) |
|---|---|---|---|---|---|---|
| 鹅膏菌科Amanitaceae | 2 | 11 | 5.26 | 鹅膏菌属 Amanita | 10 | 4.78 |
| 小菇科 Mycenaceae | 2 | 12 | 5.74 | 丝盖伞属 Inocybe | 5 | 2.39 |
| 多孔菌科 Polyporaceae | 8 | 14 | 6.70 | 蜡蘑属 Laccaria | 5 | 2.39 |
| 红菇科 Russulaceae | 3 | 23 | 11.00 | 小皮伞属 Marasmius | 6 | 2.87 |
| 小菇属 Mycena | 11 | 5.26 | ||||
| 光柄菇属 Pluteus | 5 | 2.39 | ||||
| 红菇属 Russula | 17 | 8.13 | ||||
| 栓菌属 Trametes | 5 | 2.39 |