EN
Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup
Öz
The neutronic behavior of nuclear reactors is being investigated by considering different fuel, cladding, and neutron-moderating materials. In the present manuscript, two different assembly types of SMART small modular reactor with different enrichments and different numbers of IFBA rods are considered, and the effects of mixed heavy/light water moderator, with varying fractions of heavy water during the burnup, on the assembly cycle burnup are investigated. It is observed that, to extend the cycle burnup we have to use a higher fraction of D2O at the Beginning of the Cycle (BOC) whereas it reduces toward the End of the Cycle (EOC). A higher fraction of heavy water causes the neutron spectrum to shift to the resonance region, resulting in a higher capture rate of the fertile materials. This, in turn, causes an increase in the conversion ratio. on the contrary, toward the EOC, by increasing the light water fraction, the neutron spectrum becomes softer. This also causes an increase in the fission rate of fissile materials. Finally, a certain improvement in the cycle burnup is observed. Moreover, by implementing the proposed method on an assembly containing (Th+U)O2 fuel, the UO2 mass saving is calculated.
Anahtar Kelimeler
Etik Beyan
My previous name and surname: Bahram Rashidian Maleki
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
APA
Melikkendli, B. (2024). Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji, 12(3), 702-713. https://doi.org/10.29109/gujsc.1532980
AMA
1.Melikkendli B. Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup. GUJS Part C. 2024;12(3):702-713. doi:10.29109/gujsc.1532980
Chicago
Melikkendli, Behram. 2024. “Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup”. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji 12 (3): 702-13. https://doi.org/10.29109/gujsc.1532980.
EndNote
Melikkendli B (01 Eylül 2024) Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji 12 3 702–713.
IEEE
[1]B. Melikkendli, “Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup”, GUJS Part C, c. 12, sy 3, ss. 702–713, Eyl. 2024, doi: 10.29109/gujsc.1532980.
ISNAD
Melikkendli, Behram. “Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup”. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji 12/3 (01 Eylül 2024): 702-713. https://doi.org/10.29109/gujsc.1532980.
JAMA
1.Melikkendli B. Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup. GUJS Part C. 2024;12:702–713.
MLA
Melikkendli, Behram. “Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup”. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji, c. 12, sy 3, Eylül 2024, ss. 702-13, doi:10.29109/gujsc.1532980.
Vancouver
1.Behram Melikkendli. Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup. GUJS Part C. 01 Eylül 2024;12(3):702-13. doi:10.29109/gujsc.1532980
