Evaluation of sodium borate glasses for radioactive waste immobilization applications

Erentürk S., BENGİSU M., Erdogan C.

JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, cilt.314, sa.3, ss.2069-2086, 2017 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 314 Sayı: 3
  • Basım Tarihi: 2017
  • Doi Numarası: 10.1007/s10967-017-5536-z
  • Dergi Adı: JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.2069-2086
  • Anahtar Kelimeler: Borate glasses, Radioactive waste, Vitrified waste, Chemical durability, Structural characterization, CHEMICAL DURABILITY, SILICATE-GLASSES, PBO-B2O3 GLASSES, REMOVAL
  • İstanbul Teknik Üniversitesi Adresli: Evet

Özet

Properties of sodium borate glasses, including chemical durability, leaching rate, glass transformation temperature, and melting temperature were analyzed for waste immobilization applications. The lowest dissolution rate (1.6 x 10(-8) g cm(-2) min(-1)) among candidate sodium borate host glasses was achieved in 45Na(2)O center dot 5P(2)O(5)center dot 5PbO center dot 45B(2)O(3). Similarly, the lowest dissolution rate (5.5 x 10(-8) g cm(-2) min(-1)) for simulated waste glass compositions was achieved in 20SrO center dot 80(30Na(2)O center dot 60PbO center dot 10B(2)O(3)). Clear vitrified waste products containing up to 35 mol% SrO and 25 mol% Cs2O were obtained. Low melting temperatures ranging from 222 to 440 A degrees C were achieved in simulated waste glasses.