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Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors
Joint Authors
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2018, Issue 2018 (31 Dec. 2018), pp.1-17, 17 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2018-03-01
Country of Publication
Egypt
No. of Pages
17
Abstract EN
The objective of this study was to evaluate accident-tolerant fuel (ATF) concepts being considered for CANDU reactors.
Several concepts, including uranium dioxide/silicon carbide (UO2-SiC) composite fuel, dense fuels, microencapsulated fuels, and ATF cladding, were modelled in Serpent 2 to obtain reactor physics parameters, including important feedback parameters such as coolant void reactivity and fuel temperature coefficient.
In addition, fuel heat transfer was modelled, and a simple accident model was tested on several ATF cases to compare with UO2.
Overall, several concepts would require enrichment of uranium to avoid significant burnup penalties, particularly uranium-molybdenum (U-Mo) and fully ceramic microencapsulated (FCM) fuels.
In addition, none of the fuel types have a significant advantage over UO2 in terms of overall accident response or coping time, though U-9Mo fuel melts significantly sooner due to its low melting point.
Instead, the different ATF concepts appear to have more modest advantages, such as reduced fission product release upon cladding failure, or reduced hydrogen generation, though a proper risk assessment would be required to determine the magnitude of these advantages to weigh against economic disadvantages.
The use of uranium nitride (UN) enriched in N15 would increase exit burnup for natural uranium, providing a possible economic advantage depending on fuel manufacturing costs.
American Psychological Association (APA)
Younan, Simon& Novog, David R.. 2018. Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors. Science and Technology of Nuclear Installations،Vol. 2018, no. 2018, pp.1-17.
https://search.emarefa.net/detail/BIM-1214961
Modern Language Association (MLA)
Younan, Simon& Novog, David R.. Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors. Science and Technology of Nuclear Installations No. 2018 (2018), pp.1-17.
https://search.emarefa.net/detail/BIM-1214961
American Medical Association (AMA)
Younan, Simon& Novog, David R.. Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors. Science and Technology of Nuclear Installations. 2018. Vol. 2018, no. 2018, pp.1-17.
https://search.emarefa.net/detail/BIM-1214961
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-1214961