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Do Haeng Hur - One of the best experts on this subject based on the ideXlab platform.

  • Stress Corrosion Cracking behavior of alloy 600 coupled to magnetite under high temperature caustic conditions
    Materials, 2019
    Co-Authors: Geun Dong Song, Jeoh Han, Soonhyeok Jeon, Do Haeng Hur
    Abstract:

    This study aims to investigate and explain the magnetite-accelerated Stress Corrosion Cracking phenomenon of Alloy 600 under caustic conditions, based on the electrochemical behavior. After the SCC test that lasted for 300 h, no cracks were observed in any of the magnetite-free specimens, whereas cracks with a depth of 150 to 280 μm were generated in all the magnetite-deposited specimens. Furthermore, the electrochemical behavior of magnetite and Alloy 600 demonstrated that Alloy 600 behaved as an anode in the coupling system with magnetite. In this coupling system, the electrochemical potential of Alloy 600 can be shifted into the range potentially susceptible to Stress Corrosion Cracking.

Gary S. Was - One of the best experts on this subject based on the ideXlab platform.

  • Stress Corrosion Cracking of ferritic martensitic steels in simulated boiling water reactor environment
    Corrosion, 2015
    Co-Authors: Parag M Ahmedabadi, Gary S. Was
    Abstract:

    Stress Corrosion Cracking of advanced powder metallurgy technology (APMT) and T91 (UNS K90901, ferritic-martensitic) steels were investigated in the as-received and proton-irradiated conditions in simulated boiling water reactor environment (2 ppm O2) using constant extension tensile tests at 288°C at a strain rate of 3×10−7 s−1. Significant Stress Corrosion Cracking was not observed in the as-received condition. A few cracks, perpendicular the loading direction, were observed in the proton-irradiated (5 dpa) specimen of T91. No intergranular fracture was observed on the fracture surfaces of as-received and proton-irradiated specimens of T91. No Cracking was observed for APMT in un-irradiated and proton-irradiated (5 dpa) conditions. Results indicate that both APMT and T91 are highly resistant to Stress Corrosion Cracking in a reactor environment and that irradiation to 5 dpa does not appreciably increase susceptibility.

  • irradiation assisted Stress Corrosion Cracking
    Corrosion Reviews, 2011
    Co-Authors: Gary S. Was, Yugo Ashida, Peter L. Andresen
    Abstract:

    Irradiation-assisted Stress Corrosion Cracking (IASCC) is aptly named since the effect of irradiation is to enhance an inherent susceptibility to Stress Corrosion Cracking (SCC). This chapter introduces the basic SCC dependencies in austenitic stainless steels and nickel alloys under unirradiated conditions and then describes how they are accentuated or diminished as a result of radiation. SCC results from a confluence of Stress, microstructure, and water chemistry, and each is affected by irradiation. With increasing plant operation and improved laboratory capability, it has been concluded that true immunity to SCC growth apparently does not exist in common engineering materials although different conditions can produce large changes in SCC susceptibility. As nuclear power plants operate longer, an increased incidence of SCC can be expected unless active mitigation steps are taken.

  • Corrosion and Stress Corrosion Cracking in supercritical water
    Journal of Nuclear Materials, 2007
    Co-Authors: Gary S. Was, Pantip Ampornrat, Gaurav Gupta, S Teysseyre, E A West, T R Allen, Kumar Sridharan, Lizhen Tan, Yun Chen, X Ren
    Abstract:

    Abstract Supercritical water (SCW) has attracted increasing attention since SCW boiler power plants were implemented to increase the efficiency of fossil-based power plants. The SCW reactor (SCWR) design has been selected as one of the Generation IV reactor concepts because of its higher thermal efficiency and plant simplification as compared to current light water reactors (LWRs). Reactor operating conditions call for a core coolant temperature between 280 °C and 620 °C at a pressure of 25 MPa and maximum expected neutron damage levels to any replaceable or permanent core component of 15 dpa (thermal reactor design) and 100 dpa (fast reactor design). Irradiation-induced changes in microstructure (swelling, radiation-induced segregation (RIS), hardening, phase stability) and mechanical properties (strength, thermal and irradiation-induced creep, fatigue) are also major concerns. Throughout the core, Corrosion, Stress Corrosion Cracking, and the effect of irradiation on these degradation modes are critical issues. This paper reviews the current understanding of the response of candidate materials for SCWR systems, focusing on the Corrosion and Stress Corrosion Cracking response, and highlights the design trade-offs associated with certain alloy systems. Ferritic–martensitic steels generally have the best resistance to Stress Corrosion Cracking, but suffer from the worst oxidation. Austenitic stainless steels and Ni-base alloys have better oxidation resistance but are more susceptible to Stress Corrosion Cracking. The promise of grain boundary engineering and surface modification in addressing Corrosion and Stress Corrosion Cracking performance is discussed.

  • Stress Corrosion Cracking behavior of alloys in aggressive nuclear reactor core environments
    Corrosion, 2007
    Co-Authors: Gary S. Was, Peter L. Andresen
    Abstract:

    Abstract The effects of irradiation on Stress Corrosion Cracking occur through changes in the water chemistry and in the alloy microstructure. Considerable reactor experience has shown that a high-temperature water environment and a radiation field combine to produce irradiation-assisted Stress Corrosion Cracking (IASCC) in core components of light water reactors. The principal effect of irradiation on water chemistry is through radiolysis, which results in an increase in the Corrosion potential through the formation of radiolytic species consisting of radicals and molecules that can be oxidizing or reducing. In addition, profound effects of irradiation on the microchemistry and alloy microstructure create numerous pathways for IGSCC to occur. Radiation-induced segregation, the formation of a dislocation loop microstructure, irradiation hardening, and irradiation creep all occur simultaneously in space and time. Unfolding these various effects to determine the primary factors governing the observed effect...

  • Role of coincident site lattice boundaries in creep and Stress Corrosion Cracking
    MRS Proceedings, 2004
    Co-Authors: Gary S. Was, B. Alexandreanu, Peter L. Andresen, Mukul Kumar
    Abstract:

    Interfaces control many properties in engineering materials, several of which are critical to the integrity of the engineering structure. In single phase, solid solution, austenitic alloys, grain boundaries are often the weak link, displaying susceptibility to creep, Corrosion and Stress Corrosion Cracking. As such, grain boundary structure control affords the opportunity to improve the overall performance of alloys in a variety of applications. The role of coincident site lattice boundary (CSLB) enhancement and grain boundary connectivity is examined for how it affects the response of an alloy to Stress and the environment. Specifically, the effect of grain boundary character on creep, grain boundary sliding, intergranular Stress Corrosion Cracking, and irradiation assisted Stress Corrosion Cracking in austenitic nickel-base (high purity Ni-Cr-Fe and alloy 600) and iron-base (high purity Fe-Cr-Ni and 304 stainless steel) alloys and for ferritic- martensitic alloy T91 is discussed.

Weixing Chen - One of the best experts on this subject based on the ideXlab platform.

  • Stress Corrosion Cracking initiation under the disbonded coating of pipeline steel in near neutral ph environment
    Corrosion Science, 2010
    Co-Authors: A Eslami, B Fang, Richard Kania, B Worthingham, Jenny Been, Reg Eadie, Weixing Chen
    Abstract:

    A novel test setup has been used in this study to simulate Stress Corrosion Cracking initiation under a disbonded coating on an X-65 pipeline steel. In this setup, the synergistic effects of cyclic loading, cathodic protection and soil solution environment under disbonded coatings have been considered. When the X-65 pipeline steel was exposed to the test environment, there existed a wide range of Corrosion products on the steel surface in the gradient of cathodic protection. Increasing the test time and the maximum Stress increased the possibility of Stress Corrosion Cracking initiation in regions with a high susceptibility to pitting Corrosion.

M L Aparicio - One of the best experts on this subject based on the ideXlab platform.

  • effects of prior cold work and sensitization heat treatment on chloride Stress Corrosion Cracking in type 304 stainless steels
    Corrosion Science, 2001
    Co-Authors: C Garcia, F Martin, P De Tiedra, J A Heredero, M L Aparicio
    Abstract:

    Abstract The effects of prior cold work (CW) and sensitization treatment on the Stress Corrosion Cracking (SCC) behaviour of Type 304 stainless steels have been studied in chloride solutions using electrochemical tests and magnesium chloride tests with U-bend specimen. The results indicated that the SCC behaviour of the CW steel was essentially different from that of the solution-annealed steel. Intergranular Stress Corrosion Cracking (IGSCC) of solution-annealed material changed into a mixed mode or dominant transgranular Stress Corrosion Cracking (TGSCC) when the degree of CW was increased. The sensitization treatment enhanced IGSCC susceptibility by shortening failure time and accelerating crack initiation and propagation rates, but this effect was different for several other degrees of CW. These effects were revised taking into consideration the electrochemical and microstructural phenomena. The most dangerous degrees of deformation for different sensitization conditions for the development of IGSCC and TGSCC processes have been determined.

Geun Dong Song - One of the best experts on this subject based on the ideXlab platform.

  • Stress Corrosion Cracking behavior of alloy 600 coupled to magnetite under high temperature caustic conditions
    Materials, 2019
    Co-Authors: Geun Dong Song, Jeoh Han, Soonhyeok Jeon, Do Haeng Hur
    Abstract:

    This study aims to investigate and explain the magnetite-accelerated Stress Corrosion Cracking phenomenon of Alloy 600 under caustic conditions, based on the electrochemical behavior. After the SCC test that lasted for 300 h, no cracks were observed in any of the magnetite-free specimens, whereas cracks with a depth of 150 to 280 μm were generated in all the magnetite-deposited specimens. Furthermore, the electrochemical behavior of magnetite and Alloy 600 demonstrated that Alloy 600 behaved as an anode in the coupling system with magnetite. In this coupling system, the electrochemical potential of Alloy 600 can be shifted into the range potentially susceptible to Stress Corrosion Cracking.