Developing and Evaluating Candidate Materials for Generation IV Supercritical Water Reactors. Final Technical Report, INERI-2003-008-K.

Cole, J. I. ; Rempe, J. L. ; Totemeier, T. C. ; Was, G. S. ; Sridharan, K.

Technical Information Center Oak Ridge Tennessee

关键词: Nuclear reactors;    Alloys;    Corrosion;    Efficiency;    Electricity;   

RP-ID  :  DE2008911705

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The Generation IV Supercritical Water Reactor (GEN IV SCWR) is being proposed as an advanced high efficiency thermal reactor for baseload electricity production. One of the major unknowns with this reactor concept is the behavior of fuel cladding and structural components under the extremely aggressive SCWR environment. The objective of this project was to evaluate candidate materials for SCWR application. The path the project has taken is to first determine the most likely candidate materials by surveying the literature in three principle areas; existing supercritical water fossil plants (SCFP), commercial light-water reactors (LWR) and DOE research programs in liquid-metal-fast-breeder (LMFBR) and fusion reactors. The work then entailed efforts to evaluate candidate alloys in terms of high temperature mechanical properties, corrosion and stress corrosion cracking, radiation stability. As the diagram in this document depicts, the qualification testing was designed to provide a better understanding of likely degradation processes, aiding in the development of potential mitigation strategies.