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Keywords = nuclear propulsion

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20 pages, 3693 KB  
Article
LSTM-Based Reduced-Order Modeling of Secondary Loop of Nuclear-Powered Propulsion Actuation System
by Kaiyu Li, Lizhi Jiang, Xinxin Cai, Fengyun Li, Gang Xie, Zhiwei Zheng, Wenlin Wang, Hongxing Lu and Guohua Wu
Actuators 2026, 15(4), 225; https://doi.org/10.3390/act15040225 - 16 Apr 2026
Viewed by 184
Abstract
The dynamic response of the secondary circuit system in nuclear propulsion plants is critical to the power output, safety, and energy efficiency of nuclear-powered ships. High-fidelity thermo-hydraulic simulation models can accurately capture system transients but are computationally expensive and unsuitable for real-time applications. [...] Read more.
The dynamic response of the secondary circuit system in nuclear propulsion plants is critical to the power output, safety, and energy efficiency of nuclear-powered ships. High-fidelity thermo-hydraulic simulation models can accurately capture system transients but are computationally expensive and unsuitable for real-time applications. To address this limitation, this study proposes a reduced-order dynamic parameter prediction method that integrates high-fidelity simulation with deep learning. A multi-operating-condition simulation model of a typical nuclear-powered ship secondary circuit system is developed to generate time-series data covering load ramping and propulsion mode switching. Based on this dataset, a conventional recurrent neural network (RNN) and a multilayer long short-term memory (LSTM) network are constructed for multivariate autoregressive prediction of 17 key dynamic parameters, and their performances are systematically compared. Results show that the LSTM significantly outperforms the RNN in capturing long-term temporal dependencies, achieving average RMSE and MAPE values of 0.0228% and 0.365%, respectively. The proposed model completes 50-step-ahead prediction within 0.84 s, satisfying real-time requirements. The hybrid simulation-driven and data-driven framework provides a practical solution for intelligent monitoring and control optimization of nuclear-powered ship propulsion systems. Full article
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41 pages, 5336 KB  
Review
From Processing to Performance: Innovations and Challenges in Ceramic-Based Materials
by Sachin Kumar Sharma, Sandra Gajević, Lokesh Kumar Sharma, Yogesh Sharma, Mohit Sharma, Saša Milojević, Slobodan Savić and Blaža Stojanović
Crystals 2026, 16(2), 85; https://doi.org/10.3390/cryst16020085 - 25 Jan 2026
Cited by 3 | Viewed by 1295
Abstract
In aerospace, defense, and energy systems, ceramic matrix composites (CMCs) are smart structural materials designed to function continuously in harsh mechanical, thermal, and oxidative conditions. Using high-strength fiber reinforcements and tailored interphases that enable damage-tolerant behavior, their creation tackles the intrinsic brittleness and [...] Read more.
In aerospace, defense, and energy systems, ceramic matrix composites (CMCs) are smart structural materials designed to function continuously in harsh mechanical, thermal, and oxidative conditions. Using high-strength fiber reinforcements and tailored interphases that enable damage-tolerant behavior, their creation tackles the intrinsic brittleness and low fracture toughness of monolithic ceramics. With a focus on chemical vapor infiltration, polymer infiltration and pyrolysis, melt infiltration, and additive manufacturing, this paper critically analyzes current developments in microstructural design, processing technologies, and interfacial engineering. Toughening mechanisms are examined in connection to multiscale mechanical responses, including controlled debonding, fiber bridging, fracture deflection, and energy dissipation pathways. Cutting-edge environmental barrier coatings are assessed alongside environmental durability issues like oxidation, volatilization, and hot corrosion. High-performance braking, nuclear systems, hypersonic vehicles, and turbine propulsion are evaluated as emerging uses. Future directions emphasize self-healing systems, ultra-high-temperature design, and environmentally friendly production methods. Full article
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17 pages, 1260 KB  
Article
A Submersible Power Station: Part B Propulsion Systems
by Jon Serna, Stefania Romero, Eduardo Anselmi Palma, Dimitrios Fouflias and Pericles Pilidis
J. Mar. Sci. Eng. 2025, 13(9), 1666; https://doi.org/10.3390/jmse13091666 - 30 Aug 2025
Viewed by 1456
Abstract
Nuclear power continues to be a great promise in the green revolution, as it is a cost-effective, low-emission, and safer alternative to fossil fuels that is capable of continuous operation. A preliminary design evaluation is presented for a submersible nuclear power station capable [...] Read more.
Nuclear power continues to be a great promise in the green revolution, as it is a cost-effective, low-emission, and safer alternative to fossil fuels that is capable of continuous operation. A preliminary design evaluation is presented for a submersible nuclear power station capable of operating under its own power during emergencies and routine maintenance. Because it is stationed at sea, it offers a resilient solution to natural disasters such as earthquakes and tsunamis, giving it the capability to disengage and sail to deeper waters in less than a half of an hour. In the present evaluation, the hull dimensions of a very large existing submarine and the turbomachinery layout of a Pebble Bed Modular Reactor cycle were used as baselines. The conceptual design of the submersible nuclear power station includes reactor and turbomachinery integration, preliminary sizing (4 pressure hull design; total length of 57.74 m), and propulsion system analysis, demonstrating the technical viability of the proposed submersible power station. Full article
(This article belongs to the Section Ocean Engineering)
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11 pages, 8468 KB  
Article
Nuclear Thermal Rocket Emulator for a Hardware-in-the-Loop Test Bed
by Brandon A. Wilson, Jono McConnell, Wesley C. Williams, Nick Termini, Craig Gray, Charles E. Taylor and N. Dianne Ezell Bull
Energies 2025, 18(16), 4439; https://doi.org/10.3390/en18164439 - 21 Aug 2025
Cited by 1 | Viewed by 3076
Abstract
To support NASA’s mission to use nuclear thermal rockets for future Mars missions, an instrumentation and control test bed has been built at Oak Ridge National Laboratory. The system is designed as a hardware-in-the-loop test bed for testing control elements and autonomous control [...] Read more.
To support NASA’s mission to use nuclear thermal rockets for future Mars missions, an instrumentation and control test bed has been built at Oak Ridge National Laboratory. The system is designed as a hardware-in-the-loop test bed for testing control elements and autonomous control algorithms for nuclear thermal propulsion rockets. The mock reactor system consists of a modular and scalable framework, using inexpensive components and open-source software. The hardware system consists of a two-phase flow loop and a mock reactor with six control drums. A single-board computer (NVIDIA Jetson) handles reactor core emulation and hosts a message queuing telemetry transport broker that allows user-deployed control algorithms to interact with the system hardware. The reactor emulator receives sensor data from the hardware and provides the simulated performance of the reactor under steady-state, transient, and fault conditions. The emulator uses a reactivity lookup table and the point kinetics equations to solve for the reactor dynamics in real time. Emulated reactor dynamics and sensor input inform the autonomous control algorithm’s decision-making in a closed-loop manner. The current system is capable of operating at 10 Hz, but faster cycle rates are an area of ongoing research. This test bed will enable NASA and other space vendors to rigorously test their autonomous control systems for NTP rockets under transient (reactor startup and shutdown), steady-state, and fault conditions to reduce development time and risk for autonomous control systems in future missions. Full article
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21 pages, 4954 KB  
Article
Direct Ink Writing and Characterization of ZrC-Based Ceramic Pellets for Potential Nuclear Applications
by Narges Malmir, Guang Yang, Thomas Poirier, Nathaniel Cavanaugh, Dong Zhao, Brian Taylor, Nikhil Churi, Tiankai Yao, Jie Lian, James H. Edgar, Dong Lin and Shuting Lei
J. Manuf. Mater. Process. 2025, 9(8), 270; https://doi.org/10.3390/jmmp9080270 - 11 Aug 2025
Viewed by 1790
Abstract
Developing advanced nuclear fuel technologies is critical for high-performance applications such as nuclear thermal propulsion (NTP). This study explores the feasibility of direct ink writing (DIW) for fabricating ceramic pellets for potential nuclear applications. Zirconium carbide (ZrC) is used as a matrix material [...] Read more.
Developing advanced nuclear fuel technologies is critical for high-performance applications such as nuclear thermal propulsion (NTP). This study explores the feasibility of direct ink writing (DIW) for fabricating ceramic pellets for potential nuclear applications. Zirconium carbide (ZrC) is used as a matrix material and vanadium carbide (VC) is used as a surrogate for uranium carbide (UC) in this study. A series of ink formulations were developed with varying concentrations of VC and nanocrystalline cellulose (NCC) to optimize the rheological properties for DIW processing. Post-sintering analysis revealed that conventionally sintered samples at 1750 °C exhibited high porosity (>60%), significantly reducing the compressive strength compared to dense ZrC ceramics. However, increasing VC content improved densification and mechanical properties, albeit at the cost of increased shrinkage and ink flow challenges. Spark plasma sintering (SPS) achieved near-theoretical density (~97%) but introduced geometric distortions and microcracking. Despite these challenges, this study demonstrates that DIW offers a viable route for fabricating ZrC-based ceramic structures, provided that sintering strategies and ink rheology are further optimized. These findings establish a baseline for DIW of ZrC-based materials and offer valuable insights into the porosity control, mechanical stability, and processing limitations of DIW for future nuclear fuel applications. Full article
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24 pages, 3097 KB  
Review
Advancements and Development Trends in Lead-Cooled Fast Reactor Core Design
by Cong Zhang, Ling Chen, Yongfa Zhang and Song Li
Processes 2025, 13(6), 1773; https://doi.org/10.3390/pr13061773 - 4 Jun 2025
Cited by 8 | Viewed by 5156
Abstract
Motivated by the growth of global energy demand and the goal of carbon neutrality, lead-cooled fast reactors, which are core reactor types of fourth-generation nuclear energy systems, have become a global research hotspot due to their advantages of high safety, nuclear fuel breeding [...] Read more.
Motivated by the growth of global energy demand and the goal of carbon neutrality, lead-cooled fast reactors, which are core reactor types of fourth-generation nuclear energy systems, have become a global research hotspot due to their advantages of high safety, nuclear fuel breeding capability, and economic efficiency. However, its engineering implementation faces key challenges, such as material compatibility, closed fuel cycles, and irradiation performance of structures. This paper comprehensively reviews the latest progress in the core design of lead-cooled fast reactors in terms of the innovation of nuclear fuel, optimization of coolant, material adaptability, and design of assemblies and core structures. The research findings indicate remarkable innovation trends in the field of lead-cooled fast reactor core design, including optimizing the utilization efficiency of nuclear fuel based on the nitride fuel system and the traveling wave burnup theory, effectively suppressing the corrosion effect of liquid metal through surface modification technology and the development of ceramic matrix composites; replacing the lead-bismuth eutectic system with pure lead coolant to enhance economic efficiency and safety; and significantly enhancing the neutron economy and system integration degree by combining the collaborative design strategy of the open-type assembly structure and control drums. In the future, efforts should be made to overcome the radiation resistance of materials and liquid metal corrosion technology, develop closed fuel cycle systems, and accelerate the commercialization process through international standardization cooperation to provide sustainable clean energy solutions for basic load power supply, high-temperature hydrogen production, ship propulsion, and other fields. Full article
(This article belongs to the Special Issue Process Safety Technology for Nuclear Reactors and Power Plants)
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21 pages, 2284 KB  
Review
Artificial Intelligence as Enabler for Adoption of Sustainable Nuclear-Powered Maritime Ships: Challenges and Opportunities
by Miltiadis Alamaniotis and Konstantinos Ipiotis
Sustainability 2025, 17(8), 3654; https://doi.org/10.3390/su17083654 - 18 Apr 2025
Cited by 6 | Viewed by 3233
Abstract
Decarbonization stands as one of humanity’s most pressing challenges, demanding collective efforts from multiple sectors to meet established goals. The transportation industry plays a pivotal role in this endeavor, with the maritime sector offering significant potential to reduce emissions. As a cornerstone of [...] Read more.
Decarbonization stands as one of humanity’s most pressing challenges, demanding collective efforts from multiple sectors to meet established goals. The transportation industry plays a pivotal role in this endeavor, with the maritime sector offering significant potential to reduce emissions. As a cornerstone of global goods and commodity transport, the maritime industry is uniquely positioned to contribute meaningfully to the global drive for lower carbon emissions. Artificial intelligence (AI), with its profound influence across diverse domains, is anticipated to play a vital role in supporting the nuclear shipping industry on its path to a decarbonized future. Specifically, AI provides tools to make nuclear power on ships a more economically viable solution while enhancing the safety and security of nuclear systems. This paper explores AI tools as an enabler for adopting nuclear-powered ships, delving into the challenges and opportunities associated with their implementation. Ultimately, it highlights AI’s role in fostering sustainable nuclear-powered maritime solutions, which align with and contribute to achieving global decarbonization goals. Full article
(This article belongs to the Section Energy Sustainability)
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18 pages, 8602 KB  
Article
A Preliminary Exploratory Study of the Flow and Heat Transfer Characteristics of Fuel Elements in Low-Enriched Uranium Cores
by Mingxue Shao, Songjiang Feng, Kangkang Guo, Yiheng Tong and Wei Lin
Aerospace 2025, 12(4), 290; https://doi.org/10.3390/aerospace12040290 - 30 Mar 2025
Viewed by 950
Abstract
Nuclear thermal propulsion, which uses a reactor core as the energy source of a nuclear thermal rocket, is expected to become an effective means of deep space exploration in the future. The reactor core can be damaged by a large temperature gradient. Thus, [...] Read more.
Nuclear thermal propulsion, which uses a reactor core as the energy source of a nuclear thermal rocket, is expected to become an effective means of deep space exploration in the future. The reactor core can be damaged by a large temperature gradient. Thus, investigating the structural distribution of its internal components and understanding its flow and heat transfer characteristics is highly important. In this study, a 19-hole hollow hexagonal prism fuel element is selected for simulation. A new type of fuel element is proposed by changing the diameter of the channels in the work material, and the heat transfer characteristics are compared and analyzed. Compared with a conventional fuel element under uniform inlet conditions, when the inlet conditions and the diameter of the channel in the work material are changed, the peak temperature inside the fuel element decreases, but the overall temperature distribution is more uniform. Along the flow direction, the temperature distribution boundary is located at y = 300–500 mm. From the inlet to this position, the temperature distribution on the axial cross-section is uniform. From this position to the outlet, the temperature difference along the radial cross-section is significantly reduced, and the temperature fluctuation at the periphery of the fuel element is significantly improved. The research results can provide a reference for the design of fuel elements. Full article
(This article belongs to the Section Astronautics & Space Science)
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36 pages, 12554 KB  
Review
A Review of Maritime Nuclear Reactor Systems
by Keith E. Holbert
J. Nucl. Eng. 2025, 6(1), 5; https://doi.org/10.3390/jne6010005 - 5 Feb 2025
Cited by 9 | Viewed by 20675
Abstract
Marine reactors have been applied to floating nuclear power plants, naval vessels such as submarines, and civilian ships such as icebreakers. Nuclear-powered shipping is gaining increased interest because of decarbonization goals motivated by climate change. Enhanced reactor safety can potentially reduce regulatory and [...] Read more.
Marine reactors have been applied to floating nuclear power plants, naval vessels such as submarines, and civilian ships such as icebreakers. Nuclear-powered shipping is gaining increased interest because of decarbonization goals motivated by climate change. Enhanced reactor safety can potentially reduce regulatory and liability challenges to the adoption of nuclear propulsion systems for merchant ships. This gives strong impetus for reviewing past use of nuclear reactor systems in marine environments, especially from the perspective of any accident scenarios, lest planners be caught unaware of historical incidents. To that end, a loss of coolant accident (LOCA) in a Lenin icebreaker reactor in 1965 and disposal at sea of some of its damaged fuel and reactor vessel as well as the entire tri-reactor compartment is recounted. Full article
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39 pages, 4052 KB  
Article
Evaluation of a New Kind of Z-Pinch-Based Space Propulsion Engine: Theoretical Foundations and Design of a Proof-of-Concept Experiment
by S. K. H. Auluck, R. Verma and R. S. Rawat
Plasma 2024, 7(4), 939-977; https://doi.org/10.3390/plasma7040052 - 19 Dec 2024
Viewed by 3934
Abstract
This paper explores a recently proposed scalable z-pinch-based space propulsion engine in greater detail. This concept involves a “modified plasma focus with a tapered anode that transports current from a pulsed power source to a consumable portion of the anode in the form [...] Read more.
This paper explores a recently proposed scalable z-pinch-based space propulsion engine in greater detail. This concept involves a “modified plasma focus with a tapered anode that transports current from a pulsed power source to a consumable portion of the anode in the form of a hypodermic needle tube continuously extruded along the axis of the device”. This tube is filled with a gas at a high pressure and also optionally with an axial magnetic field. The current enters the metal tube through its contact with the anode and returns to the cathode via the plasma sliding over its outer wall. The resulting rapid electrical explosion of the metal tube partially transfers current to a snowplough shock in the fill gas. Both the metal plasma and the fill gas form axisymmetric converging shells. Their interaction forms a hot and dense plasma of the fill gas surrounded by the metal plasma. Its ejection along the axis provides the impulse needed for propulsion. In a nonnuclear version, the fill gas could be xenon or hydrogen. Its unique energy density scaling could potentially lead to a neutron-deficient nuclear fusion drive based on the proton-boron avalanche fusion reaction by lining the tube with solid decaborane. In order to explore the inherent potential of this idea as a scalable space propulsion engine, this paper discusses its theoretical foundations and outlines the first iteration of a conceptual engineering design study for a proof-of-concept experiment based on the UNU-ICTP Plasma Focus facility at the Nanyang Technological University, Singapore. Full article
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21 pages, 558 KB  
Review
Advances in the Prevention of Shipping-Related Air Pollution
by Yordan Garbatov and Petar Georgiev
Energies 2024, 17(23), 5991; https://doi.org/10.3390/en17235991 - 28 Nov 2024
Cited by 6 | Viewed by 3235
Abstract
This review looks at the advancements in shipping-related air pollution prevention in the context of ship life cycle assessment and energy efficiency. It discusses which design option is best for implementing various strategies to lower greenhouse gas emissions. It covers logistics, digitization, environmental [...] Read more.
This review looks at the advancements in shipping-related air pollution prevention in the context of ship life cycle assessment and energy efficiency. It discusses which design option is best for implementing various strategies to lower greenhouse gas emissions. It covers logistics, digitization, environmental requirements, and the greenhouse gases produced. Among the issues for enhancing the propulsion system’s performance are air lubrication, ship hull optimization, and hull and propeller maintenance and cleaning. Alternative fuels, wind-assisted propulsion, and nuclear energy are given special attention. Energy-efficient design solutions, risk-based environmental ship design, and retrofitting older ships to improve energy efficiency are also covered. Several trends and recommendations for lowering shipping-related air pollution have been found in the review. Full article
(This article belongs to the Section B3: Carbon Emission and Utilization)
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17 pages, 24998 KB  
Article
Rare Earth Carbide (Nd-C and Ce-C) Synthesis and Characterization to Inform Phase Equilibrium in Advanced Nuclear Fuels
by Steven J. Cavazos, Sabiha Younus, Jesus Uresti-Mireles, Elizabeth S. Sooby and Markus H. A. Piro
Metals 2024, 14(12), 1322; https://doi.org/10.3390/met14121322 - 22 Nov 2024
Cited by 2 | Viewed by 1964
Abstract
As advances are being made regarding the performance of nuclear fuels, uranium carbides, and composites, such as (U,Zr)C and UO2 + UCx, have recently gained significant interest for deployment in nuclear space propulsion and high temperature gas-cooled reactors, respectively. However, [...] Read more.
As advances are being made regarding the performance of nuclear fuels, uranium carbides, and composites, such as (U,Zr)C and UO2 + UCx, have recently gained significant interest for deployment in nuclear space propulsion and high temperature gas-cooled reactors, respectively. However, the phase equilibria of several fission products in carbide systems remain unknown and may impact the overall fuel performance, specifically for particle nuclear fuels that are designed for commercial nuclear energy. Furthermore, comprehensive thermodynamic data on Rare Earth (RE) carbides, such as the Nd-C and Ce-C binary systems, remain limited. Presented in this study are the synthesis methods and characterizations of several Nd-C and Ce-C compositions. The findings from this research provide insights on the stability of RE-C binaries that form in irradiated nuclear fuels and address a critical knowledge gap in the current state of thermodynamics for two key RE-C systems. Full article
(This article belongs to the Section Crystallography and Applications of Metallic Materials)
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18 pages, 4138 KB  
Article
A Submersible Power Station: Part A Helium Power Conversion Unit
by Jon Serna, Eduardo Anselmi Palma, Stefania Romero, Dimitrios Fouflias and Pericles Pilidis
J. Mar. Sci. Eng. 2024, 12(11), 2101; https://doi.org/10.3390/jmse12112101 - 19 Nov 2024
Cited by 1 | Viewed by 1584
Abstract
Nuclear power continues to hold great promise in the green revolution, however public opinion regarding its deployment is mixed. A submersible nuclear power station concept is presented here that is expected to allay many concerns that are holding back the growth of nuclear [...] Read more.
Nuclear power continues to hold great promise in the green revolution, however public opinion regarding its deployment is mixed. A submersible nuclear power station concept is presented here that is expected to allay many concerns that are holding back the growth of nuclear power. This submersible can move under its own power during emergencies and routine maintenance. Being stationed at sea it is earthquake proof. In the case of a tsunami it could decouple from the coast and sail to a location several miles to deeper waters in less than 30 min. Furthermore, it could be built, commissioned, maintained, refueled and scrapped in a country like the UK. This makes it proliferation-proof, a key concern with the wider deployment of nuclear power. In the present evaluation the philosophy and the electric power generation capability of the submersible power station are investigated. This includes a pre-feasibility visualization of the design. An evaluation is carried out into fitting it in a submersible of a size similar to the largest existing nuclear submarines. These designs may enable it to deliver 0.6 to 1 GW of electrical power. Full article
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28 pages, 3599 KB  
Review
Review of the Regulatory Challenges and Opportunities for Maritime Small Modular Reactors in Republic of Korea
by Seon-Gon Kim, Sanghwan Kim, Jophous Mugabi and Jae-Ho Jeong
J. Mar. Sci. Eng. 2024, 12(11), 1978; https://doi.org/10.3390/jmse12111978 - 2 Nov 2024
Cited by 5 | Viewed by 8142
Abstract
Small Modular Reactors (SMRs) offer transformative potential for maritime propulsion by providing significant benefits such as reduced emissions, enhanced fuel efficiency, and greater operational autonomy. However, their integration into the maritime sector presents complex regulatory challenges due to the convergence of nuclear and [...] Read more.
Small Modular Reactors (SMRs) offer transformative potential for maritime propulsion by providing significant benefits such as reduced emissions, enhanced fuel efficiency, and greater operational autonomy. However, their integration into the maritime sector presents complex regulatory challenges due to the convergence of nuclear and maritime laws. A unified, harmonized regulatory framework is essential to ensure safety, radioactive waste management, and accident prevention. While initiatives led by the International Atomic Energy Agency (IAEA) and International Maritime Organization (IMO) are progressing, key gaps remain, particularly regarding maritime-specific risk assessments, emergency response protocols, and cross-border regulatory harmonization. Enhanced collaboration between regulatory bodies, pilot projects, and transparent engagement with stakeholders will be critical to refining safety protocols and accelerating regulatory alignment. Public acceptance remains a vital factor, requiring rigorous environmental impact assessments (EIAs) and transparent communication to build trust and align SMR-powered vessels with global sustainability objectives. While challenges persist, they also present opportunities for innovation and international cooperation. By addressing these regulatory and public acceptance challenges through coordinated efforts and policies, SMR propulsion can become a cornerstone of a more sustainable, efficient, and technologically advanced maritime sector. Successful deployment will position SMRs as a key component of the global energy transition, driving progress toward low-carbon shipping and a greener maritime industry. Full article
(This article belongs to the Special Issue Advanced Technologies for New (Clean) Energy Ships)
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27 pages, 3653 KB  
Review
Fundamental Understanding of Marine Applications of Molten Salt Reactors: Progress, Case Studies, and Safety
by Seongchul Park, Sanghwan Kim, Gazi A. K. M. Rafiqul Bari and Jae-Ho Jeong
J. Mar. Sci. Eng. 2024, 12(10), 1835; https://doi.org/10.3390/jmse12101835 - 14 Oct 2024
Cited by 7 | Viewed by 9465
Abstract
Marine sources contribute approximately 2% of global energy-related CO₂ emissions, with the shipping industry accounting for 87% of this total, making it the fifth-largest emitter globally. Environmental regulations by the International Maritime Organization (IMO), such as the MARPOL (International Convention for the Prevention [...] Read more.
Marine sources contribute approximately 2% of global energy-related CO₂ emissions, with the shipping industry accounting for 87% of this total, making it the fifth-largest emitter globally. Environmental regulations by the International Maritime Organization (IMO), such as the MARPOL (International Convention for the Prevention of Pollution from Ships) treaty, have driven the exploration of alternative green energy solutions, including nuclear-powered ships. These ships offer advantages like long operational periods without refueling and increased cargo space, with around 200 reactors already in use on naval vessels worldwide. Among advanced reactor concepts, the molten salt reactor (MSR) is particularly suited for marine applications due to its inherent safety features, compact design, high energy density, and potential to mitigate nuclear waste and proliferation concerns. However, MSR systems face significant challenges, including tritium production, corrosion issues, and complex behavior of volatile fission products. Understanding the impact of marine-induced motion on the thermal–hydraulic behavior of MSRs is crucial, as it can lead to transient design basis accident scenarios. Furthermore, the adoption of MSR technology in the shipping industry requires overcoming regulatory hurdles and achieving global consensus on safety and environmental standards. This review assesses the current progress, challenges, and technological readiness of MSRs for marine applications, highlighting future research directions. The overall technology readiness level (TRL) of MSRs is currently at 3. Achieving TRL 6 is essential for progress, with individual components needing TRLs of 4–8 for a demonstration reactor. Community Readiness Levels (CRLs) must also be addressed, focusing on public acceptance, safety, sustainability, and alignment with decarbonization goals. Full article
(This article belongs to the Special Issue Advanced Technologies for New (Clean) Energy Ships)
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