Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1566139 | Journal of Nuclear Materials | 2012 | 7 Pages |
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 235U 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 235U and Th fractions, thus to reach conclusions about use of Th in CANDU-6 and ACR-700 on the once-through cycle.
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
Mehmet Türkmen, Okan H. Zabunoğlu,