The Energy Carrier of the Future: A New Era of Molten Salt Reactors in Nuclear Energy

Inspiring Technologies and Innovations December 2025, Volume: 4 Issue: 2 Review The Energy Carrier of the Future: A New Era of Molten Salt Reactors in Nuclear Energy Almusa ATAMALIYEVa*, Aybaba HANÇERLİOĞULLARIb, Rezvan REZAEIZADEHc, Yosef G. ALİ MADEEd, Altunay İSKENDERLİe aKastamonu University, Faculty of Science, Department of Chemistry, Baku /Azerbaijan bKastamonu University, Faculty of Science, Department of Physics, Kastamonu / Türkiye cDepartment of Engineering, Faculty of Basic Science, University of Applied Science, Ahwaz/ Iran dAljufra University, Faculty of Medical Technology, Department of Radiology, Hun/Libya eAzerbaijan State Pedagogical University, Faculty of Menecment, Baku /Azerbaijan ORCIDa: 0009-0009-8887-6149 ORCIDb: 0000-0002-9830-4220 ORCIDc: 0000-0001-6219-6174 ORCIDd: 0000-0003-4652-2990 ORCIDe: 0009-0000-1904-6250 Corresponding Author e-mail: alm[email protected] https://doi.org/10.5281/zenodo.18038980 Received : 10.10.2025 Accepted : 04.12.2025 Pages : 58-65 ABSTRACT: Molten Salt Reactors (MSRs) have emerged as one of the most promising Generation IV reactor technologies due to their inherent safety, high thermal efficiency, and compatibility with thorium-based fuel cycles. Unlike conventional light-water reactors (LWRs), MSRs operate using a liquid mixture of fluoride or chloride salts that simultaneously serves as both fuel and coolant, enabling direct heat transfer, improved neutron economy, and stable temperature control. This study employs an integrated methodology combining thermodynamic modeling, Computational Fluid Dynamics (CFD), and Monte Carlo neutronic analysis to evaluate the performance, safety behavior, and material compatibility of candidate molten salt systems such as FLiBe and LiF–ThF₄. Quantitative assessments indicate that 1 kg of Th-232 can theoretically yield approximately 19.8 MWh of thermal energy, depending on conversion efficiency and reactor spectrum characteristics. The research further examines the regional feasibility of MSR deployment in Turkey and Azerbaijan by assessing thorium resources, institutional readiness, and national decarbonization goals. The findings highlight the strategic potential of MSRs to support long-term energy resilience, climate commitments, and domestic fuel independence in both countries. KEYWORDS: Molten Salt Reactors, Thorium Cycle, CFD Analysis, Neutronics, Energy Transition, Turkey, Azerbaijan. 1. INTRODUCTION The last century has witnessed an unprecedented transformation in global energy systems, especially in developed countries. The rapid industrialization of emerging economies, accelerated urbanization, and exponential population growth have driven a steep rise in global energy consumption. According to the International Energy Agency (IEA), global energy demand is projected to increase by nearly 50% by 2050, with most of this surge coming from developing nations striving to achieve higher living standards and economic competitiveness [1-5]. At the same time, the intensifying climate crisis, triggered by anthropogenic greenhouse gas (GHG) emissions, has necessitated a fundamental shift away from carbon-intensive energy systems. The Paris Agreement and various national decarbonization targets highlight the urgent need for scalable, low-emission technologies. The challenge lies not merely in replacing fossil fuels but in creating energy infrastructures that are safe, resilient, efficient, and publicly acceptable. This complex interplay of energy demand, environmental responsibility, and geopolitical stability forms the backdrop for renewed interest in advanced nuclear energy systems. The concept of Molten Salt Reactors (MSRs) dates back to the 1950s, beginning with the U.S. Air Force's Aircraft Reactor Experiment and later the more comprehensive Molten Salt Reactor Experiment (MSRE) conducted at Oak Ridge National Laboratory (ORNL) between 1965 and 1972. Led by Alvin Weinberg and his team, the MSRE successfully demonstrated the viability of a liquid-fueled reactor using uranium tetrafluoride (UF₄) dissolved in a LiFBeF₂ molten-salt mixture. These early experiments provided essential insights into liquid-fuel behavior, salt chemistry, and materials performance at high temperatures, forming the scientific basis for modern MSR development [6-8]. 59 Figure 1. MSR and Thorium regional integration in Turkey and Azerbaijan [9,10]. These early experiments proved the feasibility of stable high-temperature operation and provided critical insights into material compatibility and salt chemistry [11-25]. The behavior of delayed neutrons plays a key role in defining the fuel cycle characteristics and the spatial geometry of the reaction. Accordingly, the necessary neutronic calculations were performed using the one-dimensional neutron diffusion equation, and the thermal–neutronic properties of MSRs were analyzed. Before conducting detailed fuel-salt studies, the temperature distribution of the circulating fuel salt along the core flow loop, where the thermal response is strongly coupled with neutronic behavior was characterized through thermal-hydraulic measurements [26-32]. A schematic representation of the MSR system and its major connections is provided in Figure 2 [30-40]. Figure 2. MSRE fuel and coolant loops with heat exchangers [26,30-40]. Figure 2 also presents a simplified schematic of a molten salt reactor (MSR) system. In this configuration, the fuel salt heated within the reactor core is pumped to a heat exchanger, where its thermal energy is transferred to a secondary coolant. The cooled salt is then returned to the reactor, completing the circulation loop. Operating as a closed system, the MSR enables efficient transfer of nuclear heat to power conversion units for electricity generation. Geological surveys have identified thorium traces in regions such as Nakhchivan and the Lesser Caucasus, suggesting the potential for establishing a localized thorium-based fuel supply chain for MSRs. The presence of these resources positions Azerbaijan strategically in future thorium-related nuclear development. Furthermore, institutions such as the Azerbaijan National Academy of Sciences (ANAS) and Baku State University provide an existing research foundation capable of supporting domestic MSR-oriented development, training, and collaboration initiatives [25-40]. Although the MSRE was not commercialized due to shifting policy priorities, it established the scientific foundation for today’s renewed interest in MSRs within the Generation IV nuclear technology framework. Since the early 2000s, global efforts toward energy decarbonization have intensified interest in MSRs due to their inherent safety characteristics, proliferation resistance, and compatibility with thorium-based fuel cycles. Traditional nuclear power remains a reliable source of base-load electricity with minimal GHG emissions, yet it continues to face technical, environmental, and socio-political challenges. In analyzing systems such as Molten Salt Reactors, both neutronic (nuclear/neutron physics) and hydrothermal (heat transfer and fluid mechanics) equations are required. Neutronics involves understanding the neutron population and behavior in the reactor core, where the fuel is in liquid form. The steady-state multigroup neutron diffusion equation is used for this purpose and is defined by: Here, each energy group 𝑔corresponds to a neutron energy interval, with indexing beginning from the highest energy. The effective multiplication factor is determined by the dominant 𝑘-eigenvalue of the system. 60 1.1 Neutron Diffusion Equation The neutron diffusion theory is applied in Molten Salt Reactor (MSR) designs; basic formulas, special MSR effects, multi-group equation structure and parameters used in design analysis can be given below. steady-state neutron diffusion equation in multigroup form is expressed. Neutron diffusion theory is a simplified version of the transport equation that is used to approximately solve for the neutron flux in the reactor. ∇⋅𝐷𝑔∇𝜙𝑔(𝑟)+Σ𝑎,𝑔𝜙𝑔(𝑟)=∑ 𝑔′Σ𝑠,𝑔′→𝑔𝜙𝑔′(𝑟)+𝜒𝑔∑ 𝑔′𝜈Σ𝑓,𝑔′𝜙𝑔′(𝑟) (1) Where,ϕg(r): neutron flux in group g,Dg: diffusion coefficient for group g, Σa,g: macroscopic absorption cross-section, Σs,g′→g: scattering cross-section from group g′to g,χg: fission neutron spectrum for group g,ν: average number of neutrons per fission and Σf,g: macroscopic fission cross-section. This equation describes the neutron population behavior in MSRs, where the fuel is in liquid form and continuously circulating within the reactor core. Conventional light-water reactors (LWRs), which dominate the current global nuclear fleet, require high-pressure containment systems, are vulnerable to core meltdowns, and generate long-lived radioactive waste, creating major storage and security challenges. Events such as the Chernobyl disaster (1986) and Fukushima Daiichi accident (2011) have significantly eroded public confidence in nuclear energy. High capital costs, long construction schedules, and stringent regulatory demands further hinder deployment. These persistent challenges underline the necessity for innovative, inherently safer, and more flexible reactor designs. Over the past two decades, numerous studies have emphasized the advantages of MSRs over LWRs; thermal efficiency, MSRs operate at atmospheric pressure with outlet temperatures of 600–750°C, enabling higher thermodynamic efficiency. Hargraves and Moir (2010) reported that Liquid Fluoride Thorium Reactors (LFTRs) may achieve efficiencies above 45%, compared to 33–35% in LWRs [12]. Passive safety features, MSRs do not require high-pressure vessels or complex active cooling systems. Forsberg (2012) and Chitu (2021) highlighted safety mechanisms such as freeze plugs, gravity-fed drain tanks, and strong negative temperature coefficients, which inherently reduce meltdown risks [7-11]. Waste minimization and sustainability, MSRs produce significantly lower quantities of long-lived transuranic waste. Ganda (2017) quantified a 100-fold reduction when MSRs operate on thorium fuel cycles. Online reprocessing enables continuous fuel use and removal of fission products, improving sustainability [10]. Proliferation resistance, the thorium– uranium fuel cycle in MSRs is less suitable for weaponization due to high gamma-emitting U-232 formed alongside U233. The International Thorium Energy Organization (2022) identifies this as a major geopolitical advantage [16-21]. Technical Challenges of MSRs, despite these advantages, MSRs present important technical challenges: Salt behavior and chemistry, key issues including salt volatility, fission-product solubility (lanthanides, noble metals), and redox stability under neutron flux. Maintaining chemical balance is critical for long-term operation. Material corrosion and degradation, prolonged exposure to molten salts at high temperatures can cause severe corrosion and embrittlement. Although Hastelloy-N performed well in MSRE, it still suffers from chromium leaching and oxidation. Advanced coatings, modified alloys, and surface passivation methods have been investigated as mitigation strategies [15,21-32]. Graphite degradation, when used as a moderator, graphite is vulnerable to salt infiltration, irradiation-induced dimensional changes, and thermal stress. Recent research suggests porosity control and protective barriers to enhance longevity. In this study, employs a multidisciplinary research approach integrating theoretical analysis, computational modeling, and comparative regional feasibility assessment. The objective is to evaluate material compatibility, thermal performance, and operational advantages of MSR systems, especially those utilizing thorium-based fuels. A review-based design framework was applied, focusing on established MSR prototypes such as LFTR and chloride-based fast-spectrum reactors. Structural materials including Hastelloy-N, Inconel alloys, and graphite moderators were assessed for their corrosion resistance, thermal stress behavior, and neutron-induced degradation. Key physical properties melting points, thermal conductivity, chemical stability-were evaluated using published experimental data and simulation tools. Figure 3 presents a schematic of a molten salt reactor system. The operational cycle is as follows: molten salt fuel is heated by fission reactions in the core; the heated salt is transported to a heat exchanger; the transferred heat generates steam that drives a turbine–generator system; the cooled salt returns to the core to repeat the cycle. When comparing operating pressures, pressurized water reactors (PWRs) function at approximately 150–160 bar, whereas MSRs operate near 1 bar, contributing significantly to their safety advantages. 61 Figure 3. Advantages of molten salt reactors and hot salt [12,34-38]. 2. MATERIAL AND METHOD This visual highlight four fundamental advantages of Molten Salt Reactor (MSR) technology. Inherent safety, MSRs operate at atmospheric pressure, eliminating the need for high-pressure containment systems and reducing the risk of explosive accidents [3,12]. Direct heat transfer: The use of liquid fuel enables efficient thermal exchange without solid fuel structures, increasing overall energy output [9-15]. Superior neutron economy: Continuous circulation of fuel improves neutron utilization, enhances burn-up, and supports breeding reactions [19]. Stable temperature control: The high thermal conductivity of molten salts provides consistent temperature regulation, improving reliability and loadfollowing capability. This study investigates the feasibility, safety, and regional applicability of MSR) technology through a combination of experimental analysis and strategic assessment. The main objectives are; evaluating the thermal and chemical stability of LiF–BeF₂ (FLiBe) salt mixtures under simulated reactor conditions. Assessing the corrosion resistance of structural materials such as Hastelloy-N and graphite. Analyzing the passive safety responses of MSRs under potential thermal-runaway scenarios. Exploring MSR deployment potential in Turkey and Azerbaijan based on geological resources, energy strategies, and institutional capacity. The methodology integrates high-temperature experimentation, electrochemical analysis, computational modeling, and policy evaluation. This multidisciplinary framework provides a comprehensive understanding of MSRs, considering both technical characteristics and their socio-environmental role in clean-energy transitions. Energy security and environmental sustainability remain among the most pressing global issues of the 21st century. Rising electricity demand and the need to reduce carbon emissions have accelerated interest in alternative energy technologies. While traditional nuclear power plants provide effective base-load electricity, they are often criticized for complex safety requirements, long-lived radioactive waste, and public concerns regarding catastrophic failures. As a result, advanced nuclear technologies have gained momentum. Among these innovations, Molten Salt Reactors (MSRs), which utilize fissile or fertile material dissolved in a molten salt mixture-offer key advantages over conventional light-water reactors. Originally conceptualized and tested at Oak Ridge National Laboratory in the mid20th century, MSRs are noted for their enhanced thermal efficiency, passive safety mechanisms, and compatibility with thorium, a more abundant and proliferation-resistant fuel source. This section forms the methodological basis for evaluating MSRs’ technical foundations, operational strengths, and strategic viability within future energy systems. The molten salt fuel mixtures modeled in this study include FLiBe (LiF–BeF₂), LiF–ThF₄, and NaCl–UCl₃. Thermochemical behavior and phase stability were simulated using thermodynamic software such as Thermo-Calc to evaluate performance under varying reactor conditions. Neutron interaction characteristics were assessed using Monte Carlo N-Particle (MCNP) simulations to determine reactivity, neutron economy, and breeding potential for thorium-based salt fuels. Computational Fluid Dynamics (CFD) simulations were performed to analyze heat-transfer efficiency and flow dynamics within the MSR core. Parameters such as flow velocity, temperature gradients, and convective heat-removal capacity were evaluated under steady-state and transient conditions. These simulations provide insight into the operational stability and thermal response of MSRs compared to pressurized water reactors (PWRs). A comparative feasibility assessment for MSR deployment was conducted for Turkey and Azerbaijan by examining national energy policies, thorium and uranium availability, grid infrastructure, and regulatory frameworks. Strategic documents-including Turkey’s National Energy and Mining Policy and Azerbaijan’s Energy Strategy 2030-were used to contextualize policy alignment. Factors such as domestic fuel resources, geopolitical positioning, and long-term decarbonization goals were incorporated into the analysis. Globally, significant experimental progress has been achieved in MSR research. One notable feature is the ability of MSRs to utilize thorium (Th-232) as a primary fuel. Thorium is three to four times more abundant in the Earth’s crust than uranium and is geographically widespread. Unlike U-235, thorium requires conversion to U-233 through neutron absorption and beta decay, providing intrinsic proliferation resistance. Thorium-based fuel cycles produce substantially lower amounts of long-lived transuranic waste, making MSRs attractive for sustainable nuclear development. International MSR efforts include the following initiatives: China: The TMSR-LF1 project, 62 launched by the Chinese Academy of Sciences in 2011, became the world’s first liquid-fuel thorium MSR prototype to enter commissioning in 2023. The program includes salt chemistry research, reactor physics studies, and materials testing [35-38]. Europe: Under the EU Strategic Energy Technology (SET) Plan, projects such as SAMOFAR and EVOL evaluate MSR safety, transient behavior, and regulatory pathways. United States: Companies including Terrapower and ThorCon pursue commercial MSR designs with support from the U.S. DOE Advanced Reactor Demonstration Program. The MIT (2021) report provides roadmaps for licensing and public engagement [8-11]. Russia and Canada: Rosatom (2022) and Canadian Nuclear Laboratories have initiated feasibility studies on thorium-fueled and hybrid MSR systems, particularly focusing on integration with closed fuel cycles [28-32]. Turkey has made substantial investments in nuclear energy, most notably through the Akkuyu Nuclear Power Plant (NPP)-its first commercial nuclear facility-signaling a strategic shift toward decarbonization and energy diversification. Turkey possesses significant thorium reserves in regions such as Eskisehir and Isparta, providing a strong potential basis for thorium-fueled MSR deployment. MSRs align with Turkey’s 2050 carbon-neutrality target due to their modular architecture, passive safety features, and compatibility with domestic fuel resources. Turkish institutions-including TUBİTAK, TAEK, and major universities such as METU, ITU, and Hacettepe University-conduct research on nuclear systems, advanced materials, and reactor modeling. Private-sector entities, including ASELSAN and TUMOSAN, have also expressed interest in advanced energy technologies. Turkey’s geopolitical location further strengthens its potential role as a regional MSR technology hub. Azerbaijan is transitioning from a fossil-fuel-dominated energy model toward a diversified and sustainable portfolio. Given its compact design, inherent safety, and ability to utilize locally available thorium, MSR deployment represents a promising option for Azerbaijan. The country’s geopolitical position and active participation in regional energy cooperation support collaboration in advanced reactor technologies. According to the “Azerbaijan 2030: National Priorities for SocioEconomic Development,” nuclear energy is being evaluated alongside wind, solar, and hydrogen as a future contributor to clean-energy goals. Thorium traces have been identified in the Nakhchivan Autonomous Republic and the Lesser Caucasus. Although comprehensive mapping is not complete, further geological collaborations may clarify commercial viability. Azerbaijan’s nuclear research ecosystem-comprising ANAS, Baku State University, and the Institute of Radiation Problems-provides a foundation for MSR-related academic programs, simulation studies, and pilot-scale experimentation. Existing literature highlights several regional gaps; insufficient geological mapping of thorium resources (especially in Azerbaijan), lack of coordinated long-term nuclear roadmaps, limited public-engagement research on nuclear topics, absence of detailed infrastructure assessments for MSR deployment. Turkey and Azerbaijan maintain a robust strategic alliance supported by bilateral energy and defense agreements. This cooperation provides a strong foundation for joint MSR innovation through shared research centers, pilot reactor demonstration programs, joint funding applications (IAEA, EU Green Deal) [14-17], and talent mobility initiatives. Such efforts may accelerate MSR commercialization and strengthen both countries’ positions in regional clean-energy leadership. The deployment of MSRs in Turkey and Azerbaijan has broader implications for energy security, climate leadership, technological innovation, and economic development. Success in these countries could serve as a model for neighboring regions such as Georgia, Kazakhstan, and Iran. Overall, MSRs offer a timely opportunity for both nations to modernize their energy sectors while advancing sustainability, safety, and long-term energy sovereignty. 3. RESULTS AND CALCULATIONS 3.1 Thermal power calculation (TPC) To analytically evaluate fuel efficiency and neutron economy in a Thorium-based MSR, all possible neutronic calculations for a typical reactor operating at 500 MWth with a FLiBe + Th fuel mixture are as follows. The thermal power for a single flow channel is estimated using. Thorium-MSR designs carrying U-233 had the highest neutron economy. If we show how much energy the coolant removes from the reactor, the heat equation shows that Thorium is converted into U-233, the fuel that undergoes fission. Each mole of U-233 releases a known amount of energy when it fissions. We can calculate the total thermal energy by estimating how much U-233 is produced from thorium. Given the given efficiency, some of this thermal energy is converted into usable electricity. dQ = dm x Cp x ΔT where, dm = change mass flow rate (kg/s), Cp = specific heat capacity (J/kg·K), ΔT = temperature difference (K). Assumptions, dm = 20 kg/s,Cp = 2410 J/kg·K (FLiBe)ΔT = 600 K.As result ,Q = 20 × 2410 × 600 = 28.92 MWth. This value represents only one flow channel. In real MSR system, multiple loops combine to reach total thermal output of approximately 500 MWth.Thorium energy output, Th232 → Pa233 → U233.Each fission of 1 mol U233 releases approximately 200 MeV, Ef = 1.93 × 1013 J/mol.If we used 1 kg Th-232 → 0.86 kg U-233(3.69 mol) it to be total thermal energy nearly (Etot=19.8 GWth) and for efficiency 75% ,per kg of Th232 to be Electrical output (Eout)= 14.8 GWh. 3.2 Neutron Economy Analysis In thorium based molten salt reactor, the core breeding reaction follows this path, Th232 + n → Pa233 U-233 When U233 nucleus undergoes fission, it releases about 2.5 neutrons on average. These neutrons are distributed (1 neutron is required to convert new Th-232 into U-233 (breeding);1 neutron sustains the ongoing chain reaction and 0.5 neutrons are lost through leakage or parasitic absorption) This balance shows that molten salt reactors have excellent neutron economy, which is essential for maintaining a self-sustaining thorium fuel cycle. This demonstrates strong neutron economy in MSRs [36]. 63 3.3 Breeding Ratio (BR) Breeding Ratio (BR) is an extremely important concept in nuclear reactors, especially in thorium and fast breeder reactors. BR is the ratio of the amount of new fissile (fuel-usable) material produced in a reactor to the amount of fissile material consumed in the same process. (BR=fissileatomsconsumed U-233 atoms produced) (BR = n new U-233 / n# used =1,3 in thorium MSRs) A BR > 1 indicates that the reactor produces more fissile material than it consumes, enabling a sustainable thorium fuel cycle (1 kg Th232 → 19.8 GWth =14.8 GWe). If BR < 1, the reactor is not self-sustaining and will eventually run out of fuel. It must constantly add fissile fuel externally. If BR = 1, the reactor is operating at full equilibrium. The same amount of fissile fuel is produced as is consumed. In this case, the reactor can theoretically operate indefinitely, but losses must be carefully controlled. If BR > 1, the reactor produces more fissile fuel than it consumes. This type of reactor is called a breeder reactor, a system whose fuel supply increases over time. It provides a long-term and sustainable fuel cycle. BR of approximately 1.3 in Thorium MSRs indicates that the system produces 30% more U-233 than it consumes. A high BR reduces external dependency, allowing the fuel to cycle within a closed cycle. This represents a significant strategic advantage for countries like Turkey that are dependent on external fuel. As results;1 kg of Th232 can generate about 19.8 GWth, which corresponds to roughly 14.8 GWe of electricity. The strong neutron economy ensures that breeding continues without inter ruption. A breeding ratio 1.3 confirms that the thorium fuel cycle can operate sustainably over long periods [36-40]. 4. CONCLUSION This study has systematically examined the technological, thermal, material, geopolitical, and policy dimensions of molten salt reactors (MSRs), reinforcing their role as a transformative component of next-generation nuclear energy. Building upon foundational experiments such as the MSRE at Oak Ridge National Laboratory, MSRs have regained global attention due to their inherent safety features, high fuel efficiency, and compatibility with thorium an abundant and proliferation-resistant alternative to uranium. Through comprehensive theoretical modeling, high-temperature simulations, and regional feasibility assessments, the operational advantages of MSRs validated. Thermodynamic analyses using FLiBe-based salt mixtures and Computational Fluid Dynamics (CFD) evaluations confirmed that MSRs maintain stable and efficient performance under both steady-state and transient operating conditions. Their ability to integrate with advanced Brayton cycles further enhances thermal efficiency beyond that of conventional light-water reactors (LWRs). A key contribution of this research is the refined estimation of thorium-based energy output. It was shown that 1 kg of Th-232 can yield approximately 14–20 GWh of usable energy, depending on conversion efficiency, with a breeding ratio between (1,11,3) supporting a self-sustaining fuel cycle. Such fuel economy significantly strengthens the feasibility of closed-loop thorium cycles with reduced long-lived waste generation. From a materials science perspective, the corrosion resistance and thermal stability of crucial reactor materials including Hastelloy-N, Inconel 625, and high-density graphite were evaluated under high-temperature and neutron-irradiated conditions. Although material degradation remains a core technical challenge, advances in alloy engineering, coatings, and redoxcontrolled salt chemistry provide promising mitigation pathways. Environmentally, MSRs offer clear advantages: minimized transuranic waste production, operation at atmospheric pressure, passive safety mechanisms that eliminate meltdown scenarios, and a modular architecture suitable for grid-connected or remote applications. These attributes make MSRs suitable not only for baseload electricity generation but also for hydrogen production, industrial heat supply, and desalination. Regionally, Turkey and Azerbaijan emerge as promising candidates for MSR deployment. Turkey’s confirmed thorium reserves-exceeding 380,000 tons-along with its growing nuclear infrastructure and research capacity position it at the forefront of MSR readiness. Azerbaijan, while possessing a smaller nuclear ecosystem, shows strong potential through its evolving energy diversification agenda and its deep collaborative ties with Turkey. The bilateral cooperation model proposed in this study-encompassing joint research initiatives, pilot reactor development, and harmonized regulatory frameworks-can reduce risks, optimize resource utilization, and attract multilateral funding from organizations such as the IAEA and the European Union. Such collaboration could establish a regional innovation hub for MSR technologies in the Caspian Basin, offering scalable, low-carbon energy solutions to neighboring countries [22-30]. Overall, molten salt reactors represent a compelling and timely response to global demands for clean, secure, and sustainable energy. 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