Materials challenges in nuclear energy

被引:1920
|
作者
Zinkle, S. J. [1 ]
Was, G. S. [2 ]
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
[2] Univ Michigan, Nucl Engn & Radiol Sci Dept, Ann Arbor, MI 48109 USA
关键词
Nuclear materials; Radiation effects; Stress corrosion cracking; Structural alloys (steels and nickel base); Nuclear fuels; STRESS-CORROSION CRACKING; FERRITIC-MARTENSITIC STEELS; AUSTENITIC STAINLESS-STEELS; LOW-TEMPERATURE IRRADIATION; LIGHT-WATER; STRUCTURAL-MATERIALS; MICROSTRUCTURAL EVOLUTION; ZIRCONIUM ALLOYS; MECHANICAL-PROPERTIES; FRACTURE-TOUGHNESS;
D O I
10.1016/j.actamat.2012.11.004
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Nuclear power currently provides about 13% of electrical power worldwide, and has emerged as a reliable baseload source of electricity. A number of materials challenges must be successfully resolved for nuclear energy to continue to make further improvements in reliability, safety and economics. The operating environment for materials in current and proposed future nuclear energy systems is summarized, along with a description of materials used for the main operating components. Materials challenges associated with power uprates and extensions of the operating lifetimes of reactors are described. The three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues. The major corrosion and stress corrosion cracking degradation mechanisms for light-water reactors are reviewed. The materials degradation issues for the Zr alloy-clad UO2 fuel system currently utilized in the majority of commercial nuclear power plants are discussed for normal and off-normal operating conditions. Looking to proposed future (Generation IV) fission and fusion energy systems, there are five key bulk radiation degradation effects (low temperature radiation hardening and embrittlement; radiation-induced and -modified solute segregation and phase stability; irradiation creep; void swelling; and high-temperature helium embrittlement) and a multitude of corrosion and stress corrosion cracking effects (including irradiation-assisted phenomena) that can have a major impact on the performance of structural materials. (C) 2012 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.
引用
收藏
页码:735 / 758
页数:24
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