Neutronic study on the effect of first wall material thickness on tritium production and material damage in a fusion reactor

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dc.authoridTUNC, GUVEN/0000-0001-7038-8168
dc.authoridKarakoc, Alper/0000-0002-3692-5895
dc.contributor.authorSahin, Haci Mehmet
dc.contributor.authorTunc, Guven
dc.contributor.authorKarakoc, Alper
dc.contributor.authorOmar, Melood Mohamad
dc.date.accessioned2024-09-29T15:54:53Z
dc.date.available2024-09-29T15:54:53Z
dc.date.issued2022
dc.departmentKarabük Üniversitesien_US
dc.description.abstractIn this study, the effects of changing first wall materials and their thicknesses on a reactor were investigated to determine the displacement per atom (DPA) and gas production (helium and hydrogen) in the first wall, as well as the tritium breeding ratio (TBR) in the coolant and tritium breeding zones. Therefore, the modeling of the magnetic fusion reactor was determined based on the blanket parameters of the International Thermonuclear Experimental Reactor (ITER). Stainless steel (SS 316 LN-IG), Oxide Dispersion Strengthened Steel alloy (PM2000 ODS), and China low-activation martensitic steel (CLAM) were used as the first wall (FW) materials. Fluoride family molten salt materials (FLiBe, FLiNaBe, FLiPb) and lithium oxide (LiO2) were considered the coolant and tritium production material in the blanket, respectively. Neutron transport calculations were performed using the well-known 3D code MCNP5 using the continuous-energy Monte Carlo method. The built-in continuous energy nuclear and atomic data libraries along with the Evaluated Nuclear Data file (ENDF) system (ENDF/B-V and ENDF/B-VI) were used. Additionally, the activity cross-section data library CLAW-IV was used to evaluate both the DPA values and gas production of the first wall (FW) materials. An interface computer program written in the FORTRAN 90 language to evaluate the MCNP5 outputs was developed for the fusion reactor blanket. The results indicated that the best TBR value was obtained for the use of the FLiPb coolant, whereas depending on the thickness, the first wall replacement period in terms of radiation damage to all materials was between 6 and 11 years.en_US
dc.identifier.doi10.1007/s41365-022-01029-7
dc.identifier.issn1001-8042
dc.identifier.issn2210-3147
dc.identifier.issue4en_US
dc.identifier.scopus2-s2.0-85128493297en_US
dc.identifier.scopusqualityQ2en_US
dc.identifier.urihttps://doi.org/10.1007/s41365-022-01029-7
dc.identifier.urihttps://hdl.handle.net/20.500.14619/4317
dc.identifier.volume33en_US
dc.identifier.wosWOS:000783821200001en_US
dc.identifier.wosqualityQ1en_US
dc.indekslendigikaynakWeb of Scienceen_US
dc.indekslendigikaynakScopusen_US
dc.language.isoenen_US
dc.publisherSpringer Singapore Pte Ltden_US
dc.relation.ispartofNuclear Science and Techniquesen_US
dc.relation.publicationcategoryMakale - Uluslararası Hakemli Dergi - Kurum Öğretim Elemanıen_US
dc.rightsinfo:eu-repo/semantics/closedAccessen_US
dc.subjectITERen_US
dc.subjectFirst wall materialen_US
dc.subjectMaterial damageen_US
dc.subjectTritium breeding ratioen_US
dc.subjectFluorides family molten salt materialsen_US
dc.titleNeutronic study on the effect of first wall material thickness on tritium production and material damage in a fusion reactoren_US
dc.typeArticleen_US

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