An overview of corrosion issues for the design and operation of high-temperature lead- and lead-bismuth-cooled reactor systems

被引:108
作者
Ballinger, RG [1 ]
Lim, J [1 ]
机构
[1] MIT, Cambridge, MA 02139 USA
关键词
lead-bismuth; corrosion; lead-cooled reactors;
D O I
10.13182/NT04-A3540
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The viability of advanced Pb- or Pb-Bi-cooled fast reactor systems will depend on the development of classes of materials that can operate over the temperature range 650-1200degreesC. We briefly review the current state of the technology concerning the interaction of Pb and Pb-Bi alloys with structural materials. We then identify the key challenges to successful use of materials in these systems and suggest a path forward to the development of new materials and operating methods to allow higher-temperature operation. Our focus is on the necessary trade-offs that must be considered and how these trade-offs influence R&D choices. Our analysis suggests that three classes of materials will be needed for successful deployment of a lead-alloy-cooled reactor system. A lower-temperature qualified material will be necessary for the pressure boundary. The structural and cladding materials will require 1000degreesC- and 1200degreesC-class materials. The 1000degreesC-class material will be exposed to the 1000degreesC coolant. The 1200degreesC-class material will be required for the cladding and structural materials in the core region. The higher-temperature material will be required to accommodate anticipated temperature transients from potential accident scenarios, such as a loss of flow.
引用
收藏
页码:418 / 435
页数:18
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