Corrosion and stress corrosion cracking in supercritical water
Corrosion and stress corrosion cracking in supercritical water
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DOI：
10.1016/j.jnucmat.2007.05.017
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发表时间：
2007-09
影响因子：
3.1
通讯作者：
G. Was;P. Ampornrat;G. Gupta;S. Teysseyre;E. West;T. Allen;K. Sridharan;L. Tan;Yun Chen
中科院分区：
文献类型：
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作者：
G. Was;P. Ampornrat;G. Gupta;S. Teysseyre;E. West;T. Allen;K. Sridharan;L. Tan;Yun Chen
自从超临界水（SCW）锅炉发电厂的实施以提高化石燃料发电厂的效率以来，超临界水（SCW）引起了越来越多的关注。超临界水反应堆 (SCWR) 设计已被选为第四代反应堆概念之一，因为与当前的轻水反应堆 (LWR) 相比，其热效率更高且工厂简化。反应堆运行条件要求堆芯冷却剂温度在 280°C 至 620°C 之间，压力为 25MPa，对任何可更换或永久堆芯组件的最大预期中子损伤水平为 15dpa（热反应堆设计）和 100dpa（快堆设计）。辐照引起的微观结构变化（膨胀、辐射引起的偏析 (RIS)、硬化、相稳定性）和机械性能（强度、热和辐照引起的蠕变、疲劳）也是主要问题。在整个核心中，腐蚀、应力腐蚀开裂以及辐照对这些降解模式的影响都是关键问题。本文回顾了目前对 SCWR 系统候选材料响应的理解，重点关注腐蚀和应力腐蚀开裂响应，并强调与某些合金系统相关的设计权衡。铁素体-马氏体钢通常具有最佳的抗应力腐蚀开裂性能，但氧化程度最差。奥氏体不锈钢和镍基合金具有更好的抗氧化性，但更容易出现应力腐蚀开裂。讨论了晶界工程和表面改性在解决腐蚀和应力腐蚀开裂性能方面的前景。
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 25MPa and maximum expected neutron damage levels to any replaceable or permanent core component of 15dpa (thermal reactor design) and 100dpa (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.