Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup
Abstract
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Ethical Statement
References
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- [5] Isotalo, A. (2013). Computational methods for burnup calculations with Monte Carlo neutronics, Doctoral dissertation, aalto university.
- [6] Sogbadji, R. B. M. (2012). Neutronic study of the mono-recycling of americium in PWR and of the core conversion in MNSR using the MURE code, PhD thesis, Unıversity of paris sud.
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- [8] Cacuci, D. G. (Ed.). (2010). Handbook of Nuclear Engineering: Vol. 1: Nuclear Engineering Fundamentals; Vol. 2: Reactor Design; Vol. 3: Reactor Analysis; Vol. 4: Reactors of Generations III and IV; Vol. 5: Fuel Cycles, Decommissioning, Waste Disposal and Safeguards (Vol. 1). Springer Science & Business Media.
Details
Primary Language
English
Subjects
Nuclear Sciences , Nuclear Applications
Journal Section
Research Article
Authors
Early Pub Date
September 26, 2024
Publication Date
September 30, 2024
Submission Date
August 13, 2024
Acceptance Date
September 9, 2024
Published in Issue
Year 2024 Volume: 12 Number: 3
