Araştırma Makalesi
Yıl 2020,
Cilt: 23 Sayı: 4, 1379 - 1385, 01.12.2020
Öz
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.
Anahtar Kelimeler
Kaynakça
- 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
Öz
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.
Anahtar Kelimeler
Kaynakça
- 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)
Toplam 18 adet kaynakça vardır.
Ayrıntılar
| Birincil Dil | Türkçe |
|---|---|
| Konular | Mühendislik |
| Bölüm | Araştırma Makalesi |
| Yazarlar | |
| Yayımlanma Tarihi | 1 Aralık 2020 |
| Gönderilme Tarihi | 3 Ekim 2019 |
| Yayımlandığı Sayı | Yıl 2020 Cilt: 23 Sayı: 4 |
Kaynak Göster
TARANDIĞIMIZ DİZİNLER (ABSTRACTING / INDEXING)
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