Self-ion emulation of high dose neutron irradiated microstructure in stainless steels

Self-ion emulation of high dose neutron irradiated microstructure in stainless steels
复制标题

不锈钢高剂量中子辐照微观结构的自离子模拟

DOI:
10.1016/j.jnucmat.2018.01.054
复制
发表时间:
2018
影响因子:
3.1
通讯作者:
G. Was
G. Was
中科院分区:
工程技术2区
文献类型:
--
作者:
Z. Jiao;J. Michalička;G. Was

文献摘要

被引文献

相似文献

采用溶液退火304L不锈钢(SS)在380 °C下辐照130 dpa, 500 °C和600 °C下辐照15 dpa,冷加工316 SS (CW 316 SS)在380 °C下用5 MeV Fe++/Ni++辐照130 dpa,产生显微组织和辐射诱导偏析(RIS),并与BOR60反应堆中320 °C至46 dpa的中子辐照进行比较。对于304L SS合金,380 °C的自离子辐照产生的位错环组织与中子辐照相媲美。在380 °C自离子辐照和中子辐照条件下均未观察到空洞。在600 °C的辐照下,中子辐照对辐射诱导的Cr和Ni偏析的匹配效果最好,这与Mansur不变关系对RIS的较大温度变化的预测一致。在380 °C下辐照至130 dpa的316ss合金,辐照后的显微组织(位错环、析出相和空洞)和RIS与中子辐照后的样品相匹配。在316ss中,RIS的温度变化较小可能是由于冷加工引起的高汇(位错)密度。在反应器中,剂量率为~ 1000倍的单次自离子辐照条件与溶液退火304L SS中的位错环和RIS不匹配。然而,单次辐照温度与连续316ss中的位错/沉淀微观结构和RIS都有合理的匹配,这表明汇密度是决定自离子辐照温度变化的关键因素。
Solution-annealed 304L stainless steel (SS) was irradiated to 130 dpa at 380 °C, and to 15 dpa at 500 °C and 600 °C, and cold-worked 316 SS (CW 316 SS) was irradiated to 130 dpa at 380 °C using 5 MeV Fe++/Ni++to produce microstructures and radiation-induced segregation (RIS) for comparison with that from neutron irradiation at 320 °C to 46 dpa in the BOR60 reactor. For the 304L SS alloy, self-ion irradiation at 380 °C produced a dislocation loop microstructure that was comparable to that by neutron irradiation. No voids were observed in either the 380 °C self-ion irradiation or the neutron irradiation conditions. Irradiation at 600 °C produced the best match to radiation-induced segregation of Cr and Ni with the neutron irradiation, consistent with the prediction of a large temperature shift by Mansur's invariant relations for RIS. For the CW 316 SS alloy irradiated to 130 dpa at 380 °C, both the irradiated microstructure (dislocation loops, precipitates and voids) and RIS reasonably matched the neutron-irradiated sample. The smaller temperature shift for RIS in CW 316 SS was likely due to the high sink (dislocation) density induced by the cold work. A single self-ion irradiation condition at a dose rate ∼1000× that in reactor does not match both dislocation loops and RIS in solution-annealed 304L SS. However, a single irradiation temperature produced a reasonable match with both the dislocation/precipitate microstructure and RIS in CW 316 SS, indicating that sink density is a critical factor in determining the temperature shift for self-ion irradiations.