Neutronic investigation on the ARIES-ST fusion reactor with fissionable molten salts

Uebeyli M., ACIR A.

ENERGY CONVERSION AND MANAGEMENT, cilt.51, sa.12, ss.2531-2534, 2010 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 51 Sayı: 12
  • Basım Tarihi: 2010
  • Doi Numarası: 10.1016/j.enconman.2010.05.018
  • Dergi Adı: ENERGY CONVERSION AND MANAGEMENT
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.2531-2534
  • Gazi Üniversitesi Adresli: Evet

Özet

There have been a number of major fusion reactor design studies especially during the last 35 years. One of them is ARIES-ST fusion reactor, a 1000 MW(el) fusion reactor power plant [1-10]. Its design is based on the spherical tokamak concept [1-10]. Furthermore, it has an advantage of having compact power core [1-10]. In ARIES-ST fusion reactor, the coolant of LiPb is considered to be used as both energy carrier and tritium breeder [1-10]. The current study investigates the main neutronic parameters of the ARIES-ST fusion reactor utilizing the molten salts with fissile isotopes: Flibe + Weapon Grade (WG) PuF(4) or Flibe + Spent Fuel Grade (SFG) PuF(4). The neutronic calculations in the fusion blanket were carried out with the help of Scale 5 for various coolant compositions. Numerical results showed that the best neutronic performance in the reactor was attained with the coolant of Flibe + 1% WG PuF(4). In addition, a significant improvement in the energy multiplication of the reactor was obtained in comparison to the pure ARIES-ST fusion reactor. (C) 2010 Elsevier Ltd. All rights reserved.