EFFECTS OF LARGE CONCENTRATIONS OF HELIUM ON MECHANICAL-PROPERTIES OF NEUTRON-IRRADIATED STAINLESS-STEEL
EFFECTS OF LARGE CONCENTRATIONS OF HELIUM ON MECHANICAL-PROPERTIES OF NEUTRON-IRRADIATED STAINLESS-STEEL
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DOI：
10.1016/0022-3115(75)90103-8
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发表时间：
1975-01-01
影响因子：
3.1
通讯作者：
WIFFEN, FW
中科院分区：
文献类型：
--
作者：
BLOOM, EE;WIFFEN, FW
在高通量同位素反应堆中，在380至785°C范围内，对316型不锈钢试样进行了辐照，测定了其拉伸和蠕变性能。在该反应堆中进行的316型辐照部分模拟了聚变堆辐照，在两年内实现了高达120 dpa的位移损伤水平和高达6000 appm的氦含量。在退火条件下用约100 dpa和4000 appm氦气辐照的样品在350 - 600 ℃之间显示出增加的屈服强度，除350 ℃外，与未辐照材料的值相比，极限拉伸强度降低。在20%冷加工条件下辐照的样品在所有试验温度下的屈服强度和极限拉伸强度均有所下降。退火和冷加工材料的辐照样品在650° C下的试验中几乎没有应变硬化，总延伸率很小并为零。在575°C下的拉伸试验和在550°C下的蠕变断裂试验表明，当氦含量高于约30 appm时，注量对强度和延展性有很强的影响。光学金相显示出广泛的碳化物沉淀在所有温度和沉淀的第二相，被认为是西格玛，在较高的温度。
Tensile and creep properties have been determined on specimens of type 316 stainless steel irradiated in the High Flux Isotope Reactor in the range 380 to 785°C. Irradiation of type 316 in this reactor partially simulates fusion reactor irradiation, with displacement damage levels up to 120 dpa and helium contents up to 6000 appm achieved in two years. Samples irradiated in the annealed condition to about 100 dpa and 4000 appm helium showed an increased yield strength between 350 and 600°C and, except at 350°C, a reduced ultimate tensile strength compared with values for the unirradiated material. Samples irradiated in the 20%-cold-worked condition showed decreases in both yield and ultimate tensile strengths at all test temperatures. The irradiated samples of both annealed and cold-worked material exhibited little strain hardening, and total elongations were small and became zero,for tests at 650° C. Tensile tests at 575°C and creep-rupture tests at 550°C showed strong effects of fluence on strength and ductility for helium contents above about 30 appm. Optical metallography showed extensive carbide precipitation at all temperatures and precipitation of a second phase, believed to be sigma, at the higher temperatures.