Araştırma Makalesi

Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Cilt: 11 Sayı: 4 28 Aralık 2023
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Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model

Öz

In this study, the effective reactivity and burnup analyses have been performed for heterogeneous three-dimensional high-temperature gas-cooled thorium reactor (HTGR) which has 60 MWth full core geometry by using continuous-energy multi-purpose three-dimensional Monte Carlo particle transport Serpent code with ENDF/ B-VII data libraries. Nuclear fuel have been selected as 50 % ThO2+50% RG-PuO2. Firstly, effective reactivity for three different qualities of graphite for operation period have been determined. The effective reactivity showed better performance with increasing densities of graphite. Secondly, it has been also examined to ZrC and SiC cladding materials effect on the effective reactivity. It is observed that SiC has a positive effect on reactivity compared to ZrC. As a results, the full core life low-power thorium-burner HTGR have been calculated as up to ~4500 days depending on the graphite material whereas, the corresponding burn−ups came out to be ~ 189 GWd/ton, for end of life.

Anahtar Kelimeler

Kaynakça

  1. 1. IAEA, (2003), Potential of Thorium Based Fuel Cycles to Constrain Plutonium and Reduce Long Lived Waste Toxicity, IAEA-TECDOC-1349, International Atomic Energy Agency.
  2. 2. Şahin, S., Yıldız, K., Acır, A., (2004a), Power Flattening in the Fuel Bundle of a CANDU Reactor, Nuclear Engineering and Design, 232(1): 7 – 18.
  3. 3. Şahin, S., K. Yıldız, H. M. Şahin, A. Acır (2006a), “Investigation of CANDU Reactors as a Thorium Burner”, Energy Conversion and Management, Vol. 47, nos. 13 - 14, pp. 1661 – 1675.
  4. 4. Sahin, S; Sahin, HM and Acir, A. (2010). Utilization of TRISO fuel with reactor grade plutonium in CANDU reactors, 240 (8) , pp.2066-2074.
  5. 5. Sahin, S; Sahin, HM and Acir, A. (2010). Criticality and burn up evolutions of the Fixed Bed Nuclear Reactor with alternative fuels, Energy Conversion and Management, 51 (9) , pp.1781-1787
  6. 6. Acir, A and Coskun, H (2012). Neutronic analysis of the PBMR-400 full core using thorium fuel mixed with plutonium or minor actinides, Annals of Nuclear Energy, 48 , 45-50
  7. 7. Mohamed A. Alzamly, Moustafa Aziz, Alya A. Badawi, Hana Abou Gabal, Abdel Rraouf A. Gadallah (2020). Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide, Nuclear Engineering and Technology, 52, 4, 674-680.
  8. 8. I.V. Shamanin (2018). Neutronic7 properties of high-temperature gas-cooled reactors with thorium fuel. Annals of Nuclear Energy, 113, 286–293.

Ayrıntılar

Birincil Dil

İngilizce

Konular

Mühendislik

Bölüm

Araştırma Makalesi

Erken Görünüm Tarihi

6 Haziran 2023

Yayımlanma Tarihi

28 Aralık 2023

Gönderilme Tarihi

24 Mayıs 2023

Kabul Tarihi

4 Haziran 2023

Yayımlandığı Sayı

Yıl 2023 Cilt: 11 Sayı: 4

Kaynak Göster

APA
Çifci, A., & Acır, A. (2023). Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji, 11(4), 903-912. https://doi.org/10.29109/gujsc.1302009
AMA
1.Çifci A, Acır A. Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model. GUJS Part C. 2023;11(4):903-912. doi:10.29109/gujsc.1302009
Chicago
Çifci, Ahmet, ve Adem Acır. 2023. “Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model”. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji 11 (4): 903-12. https://doi.org/10.29109/gujsc.1302009.
EndNote
Çifci A, Acır A (01 Aralık 2023) Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji 11 4 903–912.
IEEE
[1]A. Çifci ve A. Acır, “Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model”, GUJS Part C, c. 11, sy 4, ss. 903–912, Ara. 2023, doi: 10.29109/gujsc.1302009.
ISNAD
Çifci, Ahmet - Acır, Adem. “Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model”. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji 11/4 (01 Aralık 2023): 903-912. https://doi.org/10.29109/gujsc.1302009.
JAMA
1.Çifci A, Acır A. Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model. GUJS Part C. 2023;11:903–912.
MLA
Çifci, Ahmet, ve Adem Acır. “Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model”. Gazi Üniversitesi Fen Bilimleri Dergisi Part C: Tasarım ve Teknoloji, c. 11, sy 4, Aralık 2023, ss. 903-12, doi:10.29109/gujsc.1302009.
Vancouver
1.Ahmet Çifci, Adem Acır. Neutronic Assessment of High-Temperature Gas-Cooled Thorium Burner using Monte Carlo Calculation Method with Full Core Model. GUJS Part C. 01 Aralık 2023;11(4):903-12. doi:10.29109/gujsc.1302009

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