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AUSTENITIC STEEL EXPOSED TO HIGH TEMPERATURE AND HIGH PRESSURE WATER UNDER NEUTRON IRRADIATION

机译:中子辐照下暴露于高温高压水的奥氏体钢

摘要

PURPOSE:To improve the resistance to irradiation brittleness, swelling resistance and stress corrosion resistance in high temp. and high pressure water of apparatus parts to be subjected to neutron irradiation in the core part of a nuclear reactor and a nuclear fusion reactor by manufacturing the apparatus parts with an austenitic stainless steel having specific compsn. CONSTITUTION:The apparatus and structure of the core part subjected to neutron irradiation in a water-boiling reactor, pressurized-water reactor and nuclear fusion reactor are manufactured with a stainless steel having the compsn. contg., by weight, 0.02 to 0.065% C, 1% Si, 10% Mn, 9 to 26% Cr, 8 to 20% Ni, 0.5 to 2.5% Cu and 0.015% B, contg. one or more kinds among 0.8% Nb, 0.8% Ta and 0.6% Ti, contg. at least one one kind among 0.01 to 0.2% Zr, Hf, Y and La and the balance =50% Fe and having the structure constituted of austenite. The stainless steel has =1% tensile elongation at the room temp. after the irradiation of electrons of 5X1022n/cm3 at 300 deg.C, has =3% swelling amt. and has =0.6 ratio of Cr concn. in grain boundary to Cr concn. in a mother phase, by which the service life of the furnace core member can exceedingly be improved.
机译:目的:提高高温下的耐辐照脆性,抗溶胀性和抗应力腐蚀性能。通过使用具有特定组成的奥氏体不锈钢制造设备部件,在核反应堆和核聚变反应堆的芯部中对要进行中子辐照的设备零件的高压水和高压水。组成:在沸腾反应堆,压水反应堆和核聚变反应堆中经受中子辐照的堆芯部分的装置和结构,是用具有这种成分的不锈钢制造的。以重量计,包括0.02至0.065%的C,<1%的Si,<10%的Mn,9至26%的Cr,8至20%的Ni,0.5至2.5%的Cu和<0.015%的B,续<0.8%Nb,<0.8%Ta和<0.6%Ti中的一种或多种,​​续Zr,Hf,Y和La为0.01〜0.2%中的至少一种,其余为> = 50%Fe,且具有由奥氏体构成的结构。不锈钢在室温下的拉伸伸长率> = 1%。在300℃下以5×10 22 n / cm 3的电子辐照后,具有≤3%的膨胀amt。并具有≥0.6的Cr含量。晶界处的Cr含量。在母相中,可以极大地提高炉芯构件的使用寿命。

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