首页> 外文会议>International conference on environmental degradation of materials in nuclear power systems water reactors >INFLUENCE OF M ICROSTRUCTURE ON IASCC GROWTH BEHAVIOR OF NEUTRON IRRADIATED TYPE 304 AUSTEN ITIC STAIN LESS STEELS IN SIMULATED BWR CONDITION
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INFLUENCE OF M ICROSTRUCTURE ON IASCC GROWTH BEHAVIOR OF NEUTRON IRRADIATED TYPE 304 AUSTEN ITIC STAIN LESS STEELS IN SIMULATED BWR CONDITION

机译:微观结构对模拟BWR条件下中子辐照304型奥氏体不锈钢的IASCC生长行为的影响

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Crack growth rate (CGR) tests have been conducted with neutron irradiated compact tension (CT) specimens. The specimens were irradiated in the core region of the Japan Materials Testing Reactor (JMTR) in simulated BWR water environments at 288 °C from 0.37 to 5.55 x 1025 n/m2 (E>1MeV) (0.62- 9.2 dpa). The CGR tests were performed using the reversing DC potential drop (DCPD) method under constant load at a few average stress intensity factors (K) and electrochemical corrosion potential (ECP) conditions at 288 °C in water. The CGRs of base metals in high ECP condition with 10
机译:裂纹扩展率(CGR)测试已经用中子辐照的致密张力(CT)标本进行了。在模拟的BWR水环境中,在288°C的0.37至5.55 x 1025 n / m2(E> 1MeV)(0.62- 9.2 dpa)的辐照下,在日本材料试验反应堆(JMTR)的核心区域中对样品进行辐照。在恒定负载下,在一些平均应力强度因子(K)和288°C的水中电化学腐蚀电势(ECP)的条件下,使用可逆DC电势降(DCPD)方法进行了CGR测试。在10

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