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VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi

Year 2020, Volume: 23 Issue: 4, 1379 - 1385, 01.12.2020
https://doi.org/10.2339/politeknik.683658

Abstract

Nükleer güç reaktörlerinin tasarımının ve güvenle çalışmasının en önemli öğelerinden biri, kritiklik ve bağıl güç yoğunluk dağılımının incelenmesidir. Bu çalışmada VVER-1000'in kritiklik ve bağıl güç yoğunluk dağılımını içeren nötronik performans analizleri MCNP nötronik kod yardımıyla hesaplanmıştır. Dört farklı yakıt tipi için nötronik hesaplamalar gerçekleştirilmiştir. Her bir yakıt demeti için yapılan hesaplamalar sonucunda reaktör korunda kritiklik ve bağıl güç yoğunluk dağılımları elde edilmiştir. Bu çalışmada elde edilen sonuçlar literatürle karşılaştırılmış ve elde edilen kritiklik ve bağıl güç yoğunluk dağılımı değerlerinin birbirleriyle benzerlik gösterdiği görülmüştür.

References

  • Abuqudaira, T. M., Stogov, Y. V., “Neutronic calculations for the VVER-1000 LEU and MOX assembly computational benchmark using the GETERA code.” Journal of Physics: Conference Series, 1133: 1-10, (2018).
  • Louis, H. K., “Investigation of the Pin-By-Pin Fission Rate Distributions for VVER MOX and LEU Fuel Assemblies Using MCNPX Code”, International Journal of Science, Engineering and Technology Research (IJSETR), Volume 5 Issue 9, 2926 – 2931, (2016)
  • OECD NEA, A VVER-1000 LEU and MOX Assembly Computational Benchmark: Specification and Results, 2002
  • Mercatali, L., Venturini. A., Daeubler, M., Sanchez, V. H., “SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark” Annals of Nuclear Energy, Volume 83: 328–341, (2015)
  • Gordienko, P. V., Kiryukhin, P. K., Shcherbakov, A. A., “Benchmark calculation AER VVER-1000 - ETE using BIPR8”, IOP Conf. Series: Journal of Physics: Conf. Series 1133: 1-14, (2018)
  • Thilagam, L., Sunny, S. C., Jagannathan, V., Subbaiah, K. V., “A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL”, Annals of Nuclear Energy, Volume 36, Issue 4: 505–519, (2009)
  • Lazarenko, A., Kalugin, M., Bychkov, S., “Benchmark Calculations for VVER-1000 Fuel Assemblies Using Uranium or MOX Fuel”
  • Snoj, L., Ravnik, M., “Calculation of Power Density with MCNP in TRIGA Reactor”, Proceedings of the International Conference Nuclear Energy for New Europe, 1091-1096, (2006)
  • Fadli, O. E., Suparmi, S., Khakim, A., Suharyana, S., Riyatun, R., “Power and neutron flux distribution analysis in the RSG-GAS reactor: preliminary study to identify the reactor readiness as Power Ramp Test Facility (PRTF)”, IOP Conf. Series: Journal of Physics: Conf. Series 1153, 1-7, (2019)
  • Khakim, A., “Regulatory Assessment on a New utilization of SAMOP Test Facility: Determination on Fission Power”, IOP Conf. Series: Journal of Physics: Conf. Series 1198, 1-8, (2019)
  • Acır A., Coskun H., Sahin H. M., Erol Ö., “Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method”, Annals of Nuclear Energy, vol. 38, 298–301, (2011)
  • Saadati H., Hadad K., Rabiee A., “Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid”, Nuclear Engineering and Technology, vol. 50, 639-647, (2018)
  • F. Faghihi, F. Roosta, S. Ghaemi, S. Bagheri, “Core designing of the newly proposed (U+Gd)O2 FAs in the VVERs core and comparison with current UO2FAs”, Alexandria Engineering Journal, 58, 647–658, (2019)
  • Veen D. V., Hoogenboom J. E., “Efficiency Improvement of Local Power Estimation in the General Purpose Monte Carlo Code MCNP”, Progress in Nuclear Science and Technology, Vol.2, pp 866-871, (2011)
  • Nazari T., Rabiee A., Kazeminejad H., “Numerical investigation of the modal characteristics for a VVER-1000 fuel assembly”, Nuclear Engineering and Design, vol. 345, pp1-6, (2019)
  • Coşkun, H., “Alternatif Nükleer Yakıtlı Çakıl Yataklı Modüler Reaktörün Monte Carlo Yöntemiyle Nötronik Analizi”, Yüksek Lisans Tezi, Gazi Üniversitesi Fen Bilimleri Enstitüsü, (2010)
  • Venturini, A., “Neutronic investigations of MOX and LEU fuel assemblies for VVER reactors”, Master of Science Thesis, the University of Pisa School of Engineering, (2014)
  • Şahin H. M., Acır A., Altınok T., Yalçın Ş.,, “Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor”, Energy Conversion and Management, Volume 49, Issue 7, 1960-1965 (2008)

Investigation of Criticality and Relative Power Density Distribution in VVER-1000 Nuclear Power Reactor

Year 2020, Volume: 23 Issue: 4, 1379 - 1385, 01.12.2020
https://doi.org/10.2339/politeknik.683658

Abstract

One of the most important elements of the design and safe operation of nuclear power reactors is the examination of the criticality and relative power density distribution. In this study, the neutronic performance analysis of the VVER-1000 containing the critical and relative power density distribution was calculated with the help of the MCNP neutronic code. Neutronic calculations were performed for four different fuel types. As a result of the calculations for each fuel assembly, criticality and relative power density distributions were obtained in the reactor core. The results obtained in this study were compared with the literature and it was seen that the critical and relative power density distribution values were similar.

References

  • Abuqudaira, T. M., Stogov, Y. V., “Neutronic calculations for the VVER-1000 LEU and MOX assembly computational benchmark using the GETERA code.” Journal of Physics: Conference Series, 1133: 1-10, (2018).
  • Louis, H. K., “Investigation of the Pin-By-Pin Fission Rate Distributions for VVER MOX and LEU Fuel Assemblies Using MCNPX Code”, International Journal of Science, Engineering and Technology Research (IJSETR), Volume 5 Issue 9, 2926 – 2931, (2016)
  • OECD NEA, A VVER-1000 LEU and MOX Assembly Computational Benchmark: Specification and Results, 2002
  • Mercatali, L., Venturini. A., Daeubler, M., Sanchez, V. H., “SCALE and SERPENT solutions of the OECD VVER-1000 LEU and MOX burnup computational benchmark” Annals of Nuclear Energy, Volume 83: 328–341, (2015)
  • Gordienko, P. V., Kiryukhin, P. K., Shcherbakov, A. A., “Benchmark calculation AER VVER-1000 - ETE using BIPR8”, IOP Conf. Series: Journal of Physics: Conf. Series 1133: 1-14, (2018)
  • Thilagam, L., Sunny, S. C., Jagannathan, V., Subbaiah, K. V., “A VVER-1000 LEU and MOX assembly computational benchmark analysis using the lattice burnup code EXCEL”, Annals of Nuclear Energy, Volume 36, Issue 4: 505–519, (2009)
  • Lazarenko, A., Kalugin, M., Bychkov, S., “Benchmark Calculations for VVER-1000 Fuel Assemblies Using Uranium or MOX Fuel”
  • Snoj, L., Ravnik, M., “Calculation of Power Density with MCNP in TRIGA Reactor”, Proceedings of the International Conference Nuclear Energy for New Europe, 1091-1096, (2006)
  • Fadli, O. E., Suparmi, S., Khakim, A., Suharyana, S., Riyatun, R., “Power and neutron flux distribution analysis in the RSG-GAS reactor: preliminary study to identify the reactor readiness as Power Ramp Test Facility (PRTF)”, IOP Conf. Series: Journal of Physics: Conf. Series 1153, 1-7, (2019)
  • Khakim, A., “Regulatory Assessment on a New utilization of SAMOP Test Facility: Determination on Fission Power”, IOP Conf. Series: Journal of Physics: Conf. Series 1198, 1-8, (2019)
  • Acır A., Coskun H., Sahin H. M., Erol Ö., “Criticality and burnup analyses of a PBMR-400 full core using Monte Carlo calculation method”, Annals of Nuclear Energy, vol. 38, 298–301, (2011)
  • Saadati H., Hadad K., Rabiee A., “Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid”, Nuclear Engineering and Technology, vol. 50, 639-647, (2018)
  • F. Faghihi, F. Roosta, S. Ghaemi, S. Bagheri, “Core designing of the newly proposed (U+Gd)O2 FAs in the VVERs core and comparison with current UO2FAs”, Alexandria Engineering Journal, 58, 647–658, (2019)
  • Veen D. V., Hoogenboom J. E., “Efficiency Improvement of Local Power Estimation in the General Purpose Monte Carlo Code MCNP”, Progress in Nuclear Science and Technology, Vol.2, pp 866-871, (2011)
  • Nazari T., Rabiee A., Kazeminejad H., “Numerical investigation of the modal characteristics for a VVER-1000 fuel assembly”, Nuclear Engineering and Design, vol. 345, pp1-6, (2019)
  • Coşkun, H., “Alternatif Nükleer Yakıtlı Çakıl Yataklı Modüler Reaktörün Monte Carlo Yöntemiyle Nötronik Analizi”, Yüksek Lisans Tezi, Gazi Üniversitesi Fen Bilimleri Enstitüsü, (2010)
  • Venturini, A., “Neutronic investigations of MOX and LEU fuel assemblies for VVER reactors”, Master of Science Thesis, the University of Pisa School of Engineering, (2014)
  • Şahin H. M., Acır A., Altınok T., Yalçın Ş.,, “Monte Carlo calculation for various enrichment lithium coolant using different data libraries in a hybrid reactor”, Energy Conversion and Management, Volume 49, Issue 7, 1960-1965 (2008)
There are 18 citations in total.

Details

Primary Language Turkish
Subjects Engineering
Journal Section Research Article
Authors

Yasin Genç This is me 0000-0002-2786-4824

Sinem Uzun 0000-0002-2814-1062

Adem Acır 0000-0002-9856-3623

Publication Date December 1, 2020
Submission Date October 3, 2019
Published in Issue Year 2020 Volume: 23 Issue: 4

Cite

APA Genç, Y., Uzun, S., & Acır, A. (2020). VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi. Politeknik Dergisi, 23(4), 1379-1385. https://doi.org/10.2339/politeknik.683658
AMA Genç Y, Uzun S, Acır A. VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi. Politeknik Dergisi. December 2020;23(4):1379-1385. doi:10.2339/politeknik.683658
Chicago Genç, Yasin, Sinem Uzun, and Adem Acır. “VVER-1000 Nükleer Güç Reaktöründe Kritiklik Ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi”. Politeknik Dergisi 23, no. 4 (December 2020): 1379-85. https://doi.org/10.2339/politeknik.683658.
EndNote Genç Y, Uzun S, Acır A (December 1, 2020) VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi. Politeknik Dergisi 23 4 1379–1385.
IEEE Y. Genç, S. Uzun, and A. Acır, “VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi”, Politeknik Dergisi, vol. 23, no. 4, pp. 1379–1385, 2020, doi: 10.2339/politeknik.683658.
ISNAD Genç, Yasin et al. “VVER-1000 Nükleer Güç Reaktöründe Kritiklik Ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi”. Politeknik Dergisi 23/4 (December 2020), 1379-1385. https://doi.org/10.2339/politeknik.683658.
JAMA Genç Y, Uzun S, Acır A. VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi. Politeknik Dergisi. 2020;23:1379–1385.
MLA Genç, Yasin et al. “VVER-1000 Nükleer Güç Reaktöründe Kritiklik Ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi”. Politeknik Dergisi, vol. 23, no. 4, 2020, pp. 1379-85, doi:10.2339/politeknik.683658.
Vancouver Genç Y, Uzun S, Acır A. VVER-1000 Nükleer Güç Reaktöründe Kritiklik ve Bağıl Güç Yoğunluk Dağılımının İncelenmesi. Politeknik Dergisi. 2020;23(4):1379-85.