A Review of Alloy 800H for Applications in the Gen IV Nuclear Energy Systems
合金
核电站
工程类
服务(商务)
建筑工程
冶金
系统工程
材料科学
核工程
业务
营销
作者
Weiju Ren,R.W. Swindeman
出处
期刊:ASME 2010 Pressure Vessels and Piping Conference: Volume 6, Parts A and B日期:2010-01-01被引量:10
标识
DOI:10.1115/pvp2010-25278
摘要
Alloy 800H is currently under consideration for applications in the Next Generation Nuclear Plant at operational temperatures above 750°C. To provide supporting information in this paper at the attempt to facilitate the consideration, service requirements of the nuclear system for structural materials is first described; and then an extensive review of Alloy 800H is given on its codification with respect to development and research history, mechanical behavior and design allowables, metallurgical aging resistance, environmental effect considerations, data requirements and availability, weldments, as well as many other aspects relevant to the intended nuclear application; an finally further research and development activities to support the materials qualification are suggested.