Molten Salt Fast Reactors (MSFRs) have prominent advantages such as fuel breeding, nuclear waste transmutation, and inherent safety. They are the only liquid-fueled nuclear reactors currently receiving significant attention as fourth-generation advanced nuclear systems. To address the challenges of short operational lifetimes and proliferation issues during online fuel processing, the breed-and-burn (B&B) MSFR is among the most promising advanced reactor types. In this study, a large-volume B&B MSFR model without online actinide element treatment was simulated and analyzed using the Monte Carlo simulation software SERPENT, considering different power levels and sizes of the inactive core. The results demonstrate that, under otherwise identical conditions, the operational lifetime and conversion ratio of MSFRs increase with decreasing power levels and increasing the size of the inactive core. These findings provide a foundation and theoretical basis for achieving B&B MSFRs without online actinide element treatment. / Smält saltsnabbreaktorer (MSFRs) har framträdande fördelar såsom bränsleförädling, transmutation av kärnavfall och inneboende säkerhet. De är de enda flytande drivna kärnreaktorerna som för närvarande får betydande uppmärksamhet som fjärde generationens avancerade kärnkraftverk. För att möta utmaningarna med korta driftstider och spridningsproblem vid online bränslebearbetning är rask-och-bränning (B&B) MSFR bland de mest lovande avancerade reaktortyperna. I denna studie simulerades och analyserades en storskalig B&B MSFR-modell utan behandling av aktinidelement online med hjälp av Monte Carlo simuleringsprogramvaran SERPENT, med hänsyn till olika effektnivåer och storlekar på den inaktiva kärnan. Resultaten visar att livslängden och konverteringsförhållandet för MSFRs ökar under annars identiska förhållanden i takt med att effektnivåerna minskar och storleken på den inaktiva kärnan ökar. Dessa resultat ger en grund och teoretisk grund för att uppnå B&B MSFRs utan behandling av aktinidelement online.

A breed-and-burn molten salt reactor (BBMSR) concept is proposed to address the Generation IV fuel cycle sustainability objective in a once-through cycle with low enrichment and no reprocessing. The BBMSR uses separate fuel and coolant molten salts, with the fuel contained in assemblies of individual tubes that can be shuffled and reclad periodically to enable high burnup. In this dual-salt configuration, the BBMSR may overcome several limitations of previous breed-and-burn (B$\&$B) designs to achieve high uranium utilisation with a simple, passively safe design. A central challenge in design of the BBMSR fuel is balancing the neutronic requirement of large fuel volume fraction for B$\&$B mode with the thermal-hydraulic requirements for safe and economically competitive reactor operation. Natural convection of liquid fuel within the tubes aids heat transfer to the coolant, and a systematic approach is developed to efficiently model this complex effect. Computational fluid dynamics modelling is performed to characterise the unique physics of the system and produce a new heat transfer correlation, which is used alongside established correlations in a numerical model. A design framework is built around this numerical model to iteratively search for the limiting power density of a given fuel and channel geometry, applying several defined temperature and operational constraints. It is found that the trade-offs between power density, core pressure drop, and pumping power are lessened by directing the flow of coolant downwards through the channel. Fuel configurations that satisfy both neutronic and thermal-hydraulic objectives are identified for natural, 5$\%$ enriched, and 20$\%$ enriched uranium feed fuel. B$\&$B operation is achievable in the natural and 5$\%$ enriched versions, with power densities of 73 W/cm$^3$ and 86 W/cm$^3$, and theoretical uranium utilisations of 300 $\mathrm{MWd/kgU_{NAT}}$ and 25.5 $\mathrm{MWd/kgU_{NAT}}$, respectively. Using 20$\%$ enriched feed fuel relaxes neutronic constraints so a wider range of fuel configurations can be considered, but there is a strong inverse correlation between power density and uranium utilisation. The fuel design study demonstrates the flexibility of the BBMSR concept to operate along a spectrum of modes ranging from high fuel utilisation at moderate power density using natural uranium feed fuel, to high power density and moderate utilisation using 20$\%$ uranium enrichment.