Comprehensive Nuclear Materials 2020
DOI: 10.1016/b978-0-12-803581-8.12051-x
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Radiation Effects in Ferritic Steels and Advanced Ferritic-Martensitic Steels

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Cited by 4 publications
(4 citation statements)
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“…Like fusion reactors, these fast-spectrum systems have different materials property changes compared to those that occur in a thermal reactor energy spectrum (i.e., light-water reactors). One primary change that requires study is helium embrittlement of nickel-based alloys in fast reactors (Griffiths 2020) and ferritic-martensitic (FM) steels in fusion reactors (Hashimoto 2020). Tailoring HFIR's neutron spectrum for fast fission reactor testing could be accomplished with the use of thermal neutron shielding (e.g., Eu 2 O 3 or Gd).…”
Section: In-core Materials Irradiation Researchmentioning
confidence: 99%
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“…Like fusion reactors, these fast-spectrum systems have different materials property changes compared to those that occur in a thermal reactor energy spectrum (i.e., light-water reactors). One primary change that requires study is helium embrittlement of nickel-based alloys in fast reactors (Griffiths 2020) and ferritic-martensitic (FM) steels in fusion reactors (Hashimoto 2020). Tailoring HFIR's neutron spectrum for fast fission reactor testing could be accomplished with the use of thermal neutron shielding (e.g., Eu 2 O 3 or Gd).…”
Section: In-core Materials Irradiation Researchmentioning
confidence: 99%
“…Obtaining fusion-typical spectrums is not as likely in HFIR because of the lack of neutrons at the >10 MeV range energy present in deuterium-tritium (D-T) fusion systems that cause the helium embrittlement. This obstacle has been approached in the past by doping FM steels with either 10 B or 58 Ni, increasing the isotopic content of 54 Fe, pre-irradiation helium implantation, or performing high-energy proton irradiation at spallation neutron sources (Hashimoto 2020). Doping with 10 B or 58 Ni is less than ideal because the dopants affect the asmanufactured microstructure and mechanical properties.…”
Section: In-core Materials Irradiation Researchmentioning
confidence: 99%
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“…In contrast to austenitic steels, radiation swelling, and high-temperature radiation embrittlement are not the dominant mechanisms of F/M steels degradation under conditions of the internal operation [ 30 ].…”
Section: Introductionmentioning
confidence: 99%