Effect of the various tritium breeding materials on the tritium breeding ratio in ARC fusion reactor

Yıl 2023, , 273 - 288, 23.06.2023

Uğur Atalay , Güven Tunç

https://doi.org/10.58559/ijes.1308031

Öz

This study deals with TBR (Tritium Breeding Ratio) performance of the four different types of molten salt (FLiBe, FLiNaK, FLiNaBe, FLiNaRb) which has four different Li-6 enrichment ratios (0%, 30%, 60%, 90%) Moreover, two different vacuum vessel materials (SiC composite and V4Cr4Ti alloy) have been used in ARC reactor geometry. In models with TBR ≥1.05, it has been desired to examine the sustainability of the tritium production of the reactor by removing the neutron multiplication layer from the design without using the toxic Beryllium element. The neutronic performance studies have been examined in OpenMC, which is an open-source Monte Carlo neutron and photon transport code. The TBR values of the different models obtained and the change of these values according to Li-6 enrichment were examined. Obtaining result showed that the FLiBe molten salt and V4Cr4Ti alloy vacuum vessel wall material could be the best choice for the ARC reactor.

Anahtar Kelimeler

Fusion reactor, ARC reactor, Tritium breeding ratio, Molten salts

Kaynakça

• [1] Lilley J. Nükleer Fizik İlkeler ve Uygulamalar. Nobel Akademik Yayıncılık, Ankara, 2018
• [2] Yican W. Fusion Neutronics, First Edition, Springer Nature Singapore Pte Ltd., Singapore, 2017.
• [3] Segantin S, Testoni R, Hartwig Z, Whyte D, Zucchetti M. Optimization of tritium breeding ratio in ARC reactor. Fusion Engineering and Design 2020; 154: 111531.
• [4] Sorbom BN, Ball J, Palmer, TR, Mangiarotti FJ, Whyte DG. ARC: A compact, high-field, fusion nuclear science facility and demonstration power plant with demountable magnets. Fusion Engineering and Design 2015; 100: 378-405.
• [5] Segantin S, Testoni R, Zucchetti M. Neutronic comparison of liquid breeders for ARC-like reactor blankets. Fusion Engineering and Design 2020; 160: 112013.
• [6] Segantin S, Meschini S. Preliminary investigation of neutron shielding compounds for ARC-class tokamaks. Fusion Engineering and Design 2022; 185: 113335.
• [7] Bocci B, Hartwig Z, Segantin S, Testoni R, Whyte D, Zucchetti M. ARC reactor materials: Activation analysis and optimization. Fusion Engineering and Design 2020; 154: 111539.
• [8] Kuang AQ, Cao NM, Creely AJ, Dennett CA, Hecla J, LaBombard B, Tinguely RA, Tolman EA, Hoffman H, Major M, Ruiz Ruiz J, Brunner D, Grover P, Laughman C, Sorbom BN, Whyte DG. Conceptual design study for heat exhaust management in the ARC fusion pilot plant. Fusion Engineering and Design 2018; 137: 221-242.
• [9] Fausser C, Puma AL, Gabriel F, Villari R. Tokamak D-T neutron source models for different plasma physics confinement modes. Fusion Engineering and Design 2012; 87: 787-792.
• [10] Şahin HM, Tunç G, Karakoç A, Omar MM. Neutronic study on the effect of first wall material thickness on tritium production and material damage in a fusion reactor. Nuclear Science and Techniques 2022; 33: 4.
• [11] Şahin HM. Monte Carlo calculation of radiation damage in first wall of an experimental hybrid reactor. Annals of Nuclear Energy 2007; 34: 861–870.
• [12] Segantin S, Testoni R, Zucchetti M. ARC Reactor – Neutron irradiation analysis. Fusion Engineering and Design 2020; 159: 111792.
• [13] Fenici P, Farias Rebelo AJ, Jones RH, Kohyama A, Snead LL. Current status of SiC/SiC composites R&D. Journal of Nuclear Materials 1998; 258-263: 215-225.
• [14] Şahin S. Selection Criteria For Fusion Reactor Structures. Journal of Thermal Engineering 2019; 5(2): 46- 57.
• [15] Alexandridils A. The high-field path to fusion energy Plasma Science and Fusion Center (PSFC) MIT.
• [16] Tajoore MMO. Neutronic Investigation of The Effect of First Wall Material Composition and Thickness On Reactor Structure Performance In A Fusion Reactor. Ph.D. Thesis, Karabuk University, 2022.
• [17] Biel W, Cismondi F. Tritium Breeding and blanket technology. 2014.
• [18] Jiang S, Shen J, Nagasaka T, Muroga T, Zheng P. Formation of intermetallic and its effect on the hardening of welding joint between vanadium alloy and Hastelloy X alloy after heat treatment. Nuclear Materials and Energy 2023; 34: 101389.
• [19] Sohal MS, Ebner MA, Sabarwall P, Sharpe P. Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties, Idaho National Laboratory, Idaho Falls, Idaho 2010; 83415.
• [20] Romano PK, Horelik NE, Herman BR, Nelson AG, Forget B, Smith K. OpenMC: A state-of-the-art Monte Carlo code for research and development. Annals of Nuclear Energy 2015; 82: 90-97.
• [21] Chadwick MB, Obložinský P, Herman M, Greene NM, McKnight RD, Smith DL,Van der Marck SC. ENDF/B-VII. 0: next generation evaluated nuclear data library for nuclear science and technology. Nuclear data sheets 2006; 107(12): 2931-3060.