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 24.01.2013   Карта сайта     Language По-русски По-английски
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24.01.2013



Volume 61, Issue 3, February 2013, Pages 735–758


The Diamond Jubilee Issue — Materials Challenges in Tomorrow’s World Selected Topics in Materials Science and Engineering


Edited By The Acta Editors




Materials challenges in nuclear energy




  • a Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831, USA

  • b Nuclear Engineering and Radiological Sciences Department, University of Michigan, Ann Arbor, MI 48109, USA



Corresponding author contact information

Corresponding author. Tel.: +1 865 576 5785.









Abstract


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.



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  • Harton Vladislav Vadim  honorary member of ISSC science council

  • Lichtenstain Alexandr Iosif  honorary member of ISSC science council

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  • Yakushev Mikhail Vasilii  honorary member of ISSC science council

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