Rapid Transmutation of High-Level Nuclear Wastes in a Catalyzed Fusion-Driven System

Demir N., GENÇ G., Altunok T., Yapici H.

JOURNAL OF FUSION ENERGY, cilt.28, sa.1, ss.107-117, 2009 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 28 Sayı: 1
  • Basım Tarihi: 2009
  • Doi Numarası: 10.1007/s10894-008-9155-0
  • Dergi Adı: JOURNAL OF FUSION ENERGY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.107-117
  • Anahtar Kelimeler: Nuclear waste transmutation, Catalyzed fusion, Fusion-driven systems, High level waste, Long-lived fission products, FREE HELICAL REACTOR, LIVED FISSION-PRODUCTS, PWR-UO2 SPENT FUEL, NEUTRONIC ANALYSIS, MINOR ACTINIDES, TRANSURANIC ELEMENTS, WEAPON PROLIFERATION, HYBRID REACTOR, ENERGY BREEDER, MODERATED D
  • Erciyes Üniversitesi Adresli: Evet

Özet

The aim of this study is to investigate the high-level waste (HLW) transmutation potential of fusion-driven transmuter (FDT) based on catalyzed D-D fusion plasma for various fuel fractions. The Minor actinide (MA) (Np-237, Am-241, Am-243 and Cm-244) and long-lived fission product (LLFP) (Tc-99, I-129 and Cs-135) nuclides discharged from high burn-up pressured water reactor-mixed oxide spent fuel are considered as the HLW. The volume fractions of the MA and LLFP are raised from 10 to 20% stepped by 2% and 10 to 80% stepped by 5%, respectively. The transmutation analyses have been performed for an operation period (OP) of up to 6 years by 75% plant factor (eta) under a first-wall neutron load (P) of 5 MW/m(2) by using two different computer codes, the XSDRNPM/SCALE4.4a neutron transport code and the MCNP4B Monte Carlo code. The numerical results bring out that the considered FDT has a high neutronic performance for an effective and rapid transmutation of MA and LLFP as well as the energy generation along the OP.