Corrosion, Stress-Corrosion Cracking and Corrosion-product Deposition in Supercritical Water-Cooled Reactors (SCWRs)

超临界水冷反应堆 (SCWR) 中的腐蚀、应力腐蚀开裂和腐蚀产物沉积

• 批准号: 424111-2011
• 负责人: Cook, William
• 金额: $ 5.83万
• 依托单位: University of New Brunswick
• 依托单位国家: 加拿大
• 项目类别: NSERC/NRCan/AECL Generation IV Energy Technologies Program
• 财政年份: 2011
• 资助国家: 加拿大
• 起止时间: 2011-01-01 至 2012-12-31
• 项目状态: 已结题
• 来源: https://www.nserc-crsng.gc.ca/ase-oro/Details-Detailles_eng.asp?id=495995
• 关键词: Corrosion; Stress; Cracking; product; Deposition

The successful design and operation of a supercritical water-cooled reactor (SCWR) will ultimately be determined by the choice of materials for in-core and out-of-core components and the water chemistry strategies employed to minimize corrosion and degradation. Also related to corrosion of key components is the input of corrosion-products to the coolant that will lead to their transport and deposition in the reactor core and downstream components. This is highly undesirable due to their potential activation in the neutron field of the reactor core and subsequent transport downstream leading to radiation fields on out-of-core components. Using the UNB SCW test loop, this program will investigate the corrosion and degradation mechanisms (general corrosion and stress-corrosion cracking - SCC) on selected materials under simulated operating conditions expected in a SCWR; namely, temperatures up to 625 degC and pressures of ~ 25 MPa in nominally pure water with various concentrations of dissolved oxygen and hydrogen in the water. Additional experiments will be run in the UNB SCW test loop to evaluate the extent and kinetics of corrosion-product deposition that will occur in the SCWR core and the effects of minor impurities such as chloride, sulfate and lead that may be present in an operating reactor.

超临界水冷反应堆（SCWR）的成功设计和操作将最终取决于选择用于最小化腐蚀和降解的核心内部和核心成分材料以及用于最小化腐蚀和降解的水化学策略。 与关键成分的腐蚀相关的也是对冷却液的腐蚀产物的输入，这将导致其在反应堆核心和下游组件中的传输和沉积。 这是高度不希望的，这是因为它们在反应堆芯的中子场中的潜在激活以及随后在下游的转运，从而导致核心外部成分的辐射场。 使用UNB SCW测试循环，该程序将在SCWR中预期的模拟操作条件下研究所选材料的腐蚀和降解机制（一般腐蚀和应力腐蚀破裂-SCC）；也就是说，在名义上纯净的水中，温度最高为625度，在水中具有不同浓度的溶解氧和氢的压力。 其他实验将在INB SCW测试环中进行，以评估将在SCWR核心中发生的腐蚀产物沉积的程度和动力学，以及在操作反应堆中可能存在的少量杂质（例如氯化物，硫酸盐和铅）的影响。