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

Mehmet Türkmen; Okan H. Zabunoglu

doi:10.1016/j.jnucmat.2012.06.008

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

Mehmet Türkmen
, Okan H. Zabunoglu

Division of Nuclear Technology

Hacettepe University

Research output: Contribution to journal › Article › peer-review

5 Citations (Scopus)

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.

Original language	English
Pages (from-to)	263-269
Number of pages	7
Journal	Journal of Nuclear Materials
Volume	429
Issue number	1-3
DOIs	https://doi.org/10.1016/j.jnucmat.2012.06.008
Publication status	Published - Oct 2012

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10.1016/j.jnucmat.2012.06.008

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title = "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",

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.",

author = "Mehmet T{\"u}rkmen and Zabunoglu, \{Okan H.\}",

year = "2012",

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doi = "10.1016/j.jnucmat.2012.06.008",

language = "English",

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T2 - Burnup analyses, natural U requirement/saving and nuclear resource utilization

AU - Türkmen, Mehmet

AU - Zabunoglu, Okan H.

PY - 2012/10

Y1 - 2012/10

N2 - 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.

AB - 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.

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VL - 429

SP - 263

EP - 269

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3

ER -

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

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