Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup
Abstract
Keywords
Etik Beyan
Kaynakça
- [1] Lamarsh, J. R., & Baratta, A. J. (2001). Introduction to nuclear engineering (Vol. 3, p. 783). Upper Saddle River, NJ: Prentice Hall.
- [2] Monterroso Urrutia, E. A. (2021). Determination of burnup of nuclear fuel. Master’s thesis. Nuclear Engineering, University of Ljubljana.
- [3] Marguet, S. (2018). The physics of nuclear reactors. Springer.
- [4] Spence, G. R. (2014). Phoenix: A Reactor Burnup Code With Uncertainty Quantification, Doctoral dissertation, Nuclear Engineering, Texas A&M University, College Station, TX.
- [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.
- [7] Haeck, W., & Verboomen, B. (2007). An optimum approach to Monte Carlo burnup. Nuclear Science and Engineering, 156(2), 180-196.
- [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.
Ayrıntılar
Birincil Dil
İngilizce
Konular
Nükleer Bilimler , Nükleer Uygulamalar
Bölüm
Araştırma Makalesi
Yazarlar
Erken Görünüm Tarihi
26 Eylül 2024
Yayımlanma Tarihi
30 Eylül 2024
Gönderilme Tarihi
13 Ağustos 2024
Kabul Tarihi
9 Eylül 2024
Yayımlandığı Sayı
Yıl 2024 Cilt: 12 Sayı: 3
