Use of Th and U in CANDU-6 and ACR-700 on the once-through cycle: Burnup analyses, natural U requirement/saving and nuclear resource utilization

TÜRKMEN M., ZABUNOGLU O. H.

JOURNAL OF NUCLEAR MATERIALS, cilt.429, ss.263-269, 2012 (SCI-Expanded) identifier identifier

  • Yayın Türü: Makale / Tam Makale
  • Cilt numarası: 429
  • Basım Tarihi: 2012
  • Doi Numarası: 10.1016/j.jnucmat.2012.06.008
  • Dergi Adı: JOURNAL OF NUCLEAR MATERIALS
  • Derginin Tarandığı İndeksler: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Sayfa Sayıları: ss.263-269
  • Hacettepe Üniversitesi Adresli: Evet

Özet

Use of U and U-Th fuels in CANDU type of reactors (CANDU-6 and ACR-700) on the once-through nuclear fuel cycle is investigated. Based on the unit-cell approximation with the homogeneous-bundle/core model, utilizing the MONTEBURNS code, burnup computations are performed; discharge burnups are determined and expressed as functions of U-235 and Th fractions, when applicable. Natural Uranium Requirement (and Saving) and Nuclear Resource Utilization are calculated for varying fuel compositions. Results are analyzed to observe the effects of U-235 and Th fractions, thus to reach conclusions about use of Th in CANDU-6 and ACR-700 on the once-through cycle. (C) 2012 Elsevier B.V. All rights reserved.