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Influence of Simulated Outside-Reactor Irradiation on Anticorrosion Property of Austenitic Stainless Steel

机译:模拟的外部反应器辐照对奥氏体不锈钢防腐性能的影响

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摘要

The influence of gamma-ray irradiation on the properties of inside-reactor stainless steel structures was studied by simulating the working condition of pressurized water reactor (PWR) first circuit and the outside-reactor y-ray irradiation. The result shows that the simulated outside-reactor irradiation (irradiation dose 4.4 X 10~4 Gy) has no influence on anticorrosion properties of solutionized SUS304 austenitic stainless steel, including intergranular corrosion (IC) and stress corrosion cracking (SCO. Anticorrosion properties (IC, SCO of sensitized SUS304 austenitic stainless steel are reduced by simulated outside-reactor irradiation. The longer the sensitized time is, the more obvious the influence is.
机译:通过模拟压水堆第一回路的工作条件和外部反应器的y射线辐照,研究了γ射线辐照对内部反应器不锈钢结构性能的影响。结果表明,模拟的外部反应器辐照(辐照剂量为4.4 X 10〜4 Gy)对固溶SUS304奥氏体不锈钢的抗腐蚀性能没有影响,包括晶间腐蚀(IC)和应力腐蚀开裂(SCO)。模拟的外部反应器辐照降低了敏化SUS304奥氏体不锈钢的SCO,敏化时间越长,影响越明显。

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