Research Progress of Core Material Embrittlement in Nuclear Reactors
A special issue of Metals (ISSN 2075-4701). This special issue belongs to the section "Entropic Alloys and Meta-Metals".
Deadline for manuscript submissions: closed (31 July 2024) | Viewed by 268
Special Issue Editor
2. Department of Mechanical and Aerospace Engineering, Carleton University, 1125 Colonel By Drive, Ottawa, ON K1S 5B6, Canada
Interests: nuclear materials; radiation damage; microstructure; XRD; TEM; mechanical properties; irradiation creep; irradiation swelling
Special Issue Information
Dear Colleagues,
The loss of strength and ductility of nuclear reactor core components is a major concern for reactor life management as utilities endeavor to prolong the operation of aging reactors and develop improved components for reactor refurbishment activities. Build reactors are also designed to have the maximum possible operating life under conditions extending the envelope of stress, temperature, and neutron flux/spectrum for which operating experience exists. Cracking of permanent or semi-permanent (non-fuel assembly) components in reactor cores must be avoided at all costs, and reactor operation is often shortened when there are concerns that cracking may occur or could occur under foreseeable events. Light water reactor pressure vessels are typically made from ferritic steels, and the concern is low-temperature embrittlement if the temperature drops and the primary heat transport system remains pressurized. Similar concerns exist for pressure tube reactors when hydride cracking is possible. Helium embrittlement and irradiation-assisted stress corrosion cracking concern reactor internals and fuel assembly components made from austenitic stainless steel and Ni-alloys. In pressure tube reactors, the fuel and primary containment are contained in Zr-alloy tubing that degrades with both neutron dose and hydrogen or deuterium pick-up. Because the pressure boundary is within the core, irradiation-enhanced creep is a concern for creep ductility, but cracking due to the combined effects of irradiation and hydride embrittlement can be an even bigger concern. For the UK advanced gas reactors with graphite as the moderator and CO2 as the coolant, a life-limiting concern is weight loss and cracking of the graphite that may or may not be exacerbated by irradiation effects. For this Special Issue, we welcome articles focusing on cracking permanent or semi-permanent nuclear reactor components exposed to the neutron flux, i.e., the reactor core internals and containment vessels.
Dr. Malcolm Griffiths
Guest Editor
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Keywords
- nuclear reactor materials
- radiation damage
- embrittlement
- irradiation
- core
- crack
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