Corrosion in a Supercritical Water-cooled Reactor - Developing a Mechanistic Framework

摘要：

In the Canadian SCWR, the coolant temperature increases from 350 °C to 625 °C from core inletto outlet. The coolant properties change significantly over this temperature range, especiallynear the critical point. Data suggest different corrosion mechanisms occur in high-density subcritical/near-critical water and in low-density SCW, highlighting the need for a mechanisticframework within which to interpret the data. This paper explores the relationship betweenenvironmental parameters and corrosion mechanisms in an SCWR core and importance ofunderstanding surface rather than bulk conditions. The implications of this work on selectionand testing of materials, corrosion mitigation strategies, chemistry and corrosion monitoring arediscussed.

作者: D.A.Guzonas W.G.Cook

作者单位: Atomic Energy of Canada Limited University of New Brunswick

会议类型: 国际会议

会议名称: 3rd China-Canada Joint Workshop on Supercritical Water-Cooled Reactors(第三届中国-加拿大超临界水堆研讨会 (CCSC-2012)

会议地点: 西安

会议语种:英文

页码: 1-12

在线出版日期: 2012-04-18（万方平台首次上网日期，不代表论文的发表时间）