A review on the potential use of austenitic stainless steels in nuclear fusion reactors

Sahin S., Uebeyli M.

JOURNAL OF FUSION ENERGY, cilt.27, sa.4, ss.271-277, 2008 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 27 Sayı: 4
  • Basım Tarihi: 2008
  • Doi Numarası: 10.1007/s10894-008-9136-3
  • Dergi Adı: JOURNAL OF FUSION ENERGY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.271-277
  • Anahtar Kelimeler: austenitic stainless steel, fusion reactor, irradiation behavior, corrosion behavior, CYCLE FATIGUE PROPERTIES, STRUCTURAL-MATERIALS, TENSILE PROPERTIES, 1ST WALL, HYLIFE-II, MICROSTRUCTURAL EVOLUTION, MECHANICAL-PROPERTIES, IRRADIATION CREEP, NEUTRON-SPECTRUM, PHASE-STABILITY
  • Gazi Üniversitesi Adresli: Evet

Özet

Various engineering materials; austenitic stainless steels, ferritic/martensitic steels, vanadium alloys, refractory metals and composites have been suggested as candidate structural materials for nuclear fusion reactors. Among these structural materials, austenitic steels have an advantage of extensive technological database and lower cost compared to other non-ferrous candidates. Furthermore, they have also advantages of very good mechanical properties and fission operation experience. Moreover, modified austenitic stainless (Ni and Mo free) have relatively low residual radioactivity. Nevertheless, they can't withstand high neutron wall load which is required to get high power density in fusion reactors. On the other hand, a protective flowing liquid wall between plasma and solid first wall in these reactors can eliminate this restriction. This study presents an overview of austenitic stainless steels considered to be used in fusion reactors.