INVESTIGATING THE POTENTIAL FUELS FOR DFRm REACTOR CONCEPT
| dc.contributor.author | Daydas, Semra | |
| dc.contributor.author | Tiftikci, Ali | |
| dc.date.accessioned | 2026-04-25T14:20:35Z | |
| dc.date.available | 2026-04-25T14:20:35Z | |
| dc.date.issued | 2024 | |
| dc.department | Sinop Üniversitesi | |
| dc.description | 33rd International Conference on Nuclear Energy for New Europe -- SEP 09-12, 2024 -- Portoroz, SLOVENIA | |
| dc.description.abstract | The Dual Fluid Reactor (DFR) is a conceptual design that combines the advantageous properties of two of the selected Gen IV reactor concepts: the Molten Salt Reactor (MSR) and the Lead Cooled Fast Reactor (LFR). In the DFR molten salt is used (from MSR) in a separate circuit and is cooled by the molten lead (from LFR). In the DFR, molten fuel flows inside the SiC fuel tubes while being cooled by lead that flows around these fuel tubes. The advantages of these two separate cycles enable the use of undiluted fuel salts and metallic fuels. Therefore, there are mainly two DFR concepts named DFRs and DFRm which use molten salt and molten metallic fuel respectively. In this study, neutronic analysis has been conducted for the DFRm design by using SERPENT code. Reference DFRm reactor uses U-Cr metallic fuel with the lowest temperature of 860 degrees C with 4.78 wt. % Cr, %12.8 wt.% U-235 and 82.42 wt.% U-238 composition. To increase the operation temperature margin U-Ni and U-Fe fuels are proposed. U-Ni eutectic metallic fuel reaches its lowest melting point at 740 degrees C with 11 wt.% nickel and 89 wt.% uranium composition. As for U- Fe fuel, fuel composition at the eutectic point is 10.2 wt.% Fe and 89.8 wt.% uranium at 725 degrees C. It is shown that both U-Ni and U-Fe fuels have similar k(eff) trends with the reference U-Cr fuel with lower k(eff) values. This is because proposed fuel compositions have lower uranium content. To reach the same k(eff) values U-235 content in the fuel must be higher for both U-Ni and U-Fe fuels. Thus, with these fuels in the DFRm core, it is possible to reduce the fuel freezing risk and by this, the safety would be increased and ensure a wider operating temperature range. | |
| dc.identifier.isbn | 978-961-6207-59-1 | |
| dc.identifier.scopusquality | N/A | |
| dc.identifier.uri | https://hdl.handle.net/11486/8647 | |
| dc.identifier.wos | WOS:001453270200005 | |
| dc.identifier.wosquality | N/A | |
| dc.indekslendigikaynak | Web of Science | |
| dc.language.iso | en | |
| dc.publisher | Nuclear Society Slovenia | |
| dc.relation.ispartof | 33rd International Conference Nuclear Energy for New Europe | |
| dc.relation.publicationcategory | Konferans Öğesi - Uluslararası - Kurum Öğretim Elemanı | |
| dc.rights | info:eu-repo/semantics/closedAccess | |
| dc.snmz | KA_WOS_20260420 | |
| dc.title | INVESTIGATING THE POTENTIAL FUELS FOR DFRm REACTOR CONCEPT | |
| dc.type | Conference Object |












