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, vol.429, pp.263-269, 2012 (SCI-Expanded) identifier identifier

  • Publication Type: Article / Article
  • Volume: 429
  • Publication Date: 2012
  • Doi Number: 10.1016/j.jnucmat.2012.06.008
  • Journal Name: JOURNAL OF NUCLEAR MATERIALS
  • Journal Indexes: Science Citation Index Expanded (SCI-EXPANDED), Scopus
  • Page Numbers: pp.263-269
  • Hacettepe University Affiliated: Yes

Abstract

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.