energies-logo

Journal Browser

Journal Browser

Nuclear Engineering and Nuclear Fuel Safety

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: 20 August 2025 | Viewed by 295

Special Issue Editor


E-Mail Website
Guest Editor
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
Interests: nuclear energy science and engineering; nuclear technology and applications; high-performance numerical calculation methods and program development for molten salt reactors; modeling and simulation of molten salt reactors; digital twin of molten salt reactors; thorium-based molten salt reactor nuclear energy system

Special Issue Information

Dear Colleagues,

Advancements in nuclear engineering and nuclear fuel safety are pivotal to the sustainable and secure utilization of nuclear energy. Recent developments focus on enhancing reactor resilience, improving fuel performance, and integrating innovative technologies to ensure environmental sustainability.

Accident-Tolerant Fuels (ATFs): ATFs are designed to withstand extreme conditions, such as loss-of-coolant accidents (LOCAs) or reaction-initiated accidents (RIAs), better than traditional fuels. Research aims to develop fuels that can tolerate loss of active cooling for extended periods, thereby preventing or delaying the release of radionuclides during accidents.

Small Modular Reactors (SMRs): SMRs offer a promising pathway for safer, more flexible nuclear power generation. These reactors are designed to be cost-effective, safer, and quicker to construct compared to traditional nuclear power plants. Their modular nature allows for factory production and standard transportation, potentially reducing costs and construction timescales.

Integration of Artificial Intelligence (AI) and Computational Modeling: Innovations in computational modeling and AI are revolutionizing safety protocols by enabling real-time monitoring and predictive maintenance of nuclear systems. AI models can simulate reactor behavior, improving safety, design, performance, and fuel loading.

Closed Fuel Cycles and Advanced Reprocessing: Research into closed fuel cycles and advanced reprocessing techniques aims to minimize radioactive waste and optimize resource utilization. The Advanced Fuel Cycle Initiative (AFCI) focuses on nuclear fuel recycling and waste management to enable the safe, secure, economic, and sustainable expansion of nuclear energy.

Passive Safety Systems and Advanced Cooling Technologies: The integration of passive safety systems and advanced cooling technologies further ensures the reliability of next-generation nuclear reactors. These systems can operate without human intervention, enhancing reactor safety and efficiency.

Generation IV Reactors: Generation IV reactors, including Molten Salt Reactors (MSRs), represent a major leap forward in nuclear technology. MSRs use molten salts as both fuel and coolant, providing enhanced safety features and the potential for efficient fuel recycling. They operate at higher temperatures and lower pressures, which reduces the risk of overheating and catastrophic failure. Furthermore, MSRs can use thorium as a fuel source, which is more abundant and offers additional safety benefits, such as a lower risk of nuclear proliferation and the generation of less long-lived radioactive waste.

As the global demand for clean energy grows, these advancements underscore the importance of nuclear engineering in achieving a low-carbon future while maintaining the highest safety standards.

Prof. Dr. Maosong Cheng
Guest Editor

Manuscript Submission Information

Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All submissions that pass pre-check are peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.

Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Energies is an international peer-reviewed open access semimonthly journal published by MDPI.

Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • nuclear engineering
  • nuclear fuel safety
  • accident-tolerant fuels (ATFs)
  • small modular reactors (SMRs)
  • integration of artificial intelligence (AI) and computational modeling
  • closed fuel cycles and advanced reprocessing
  • passive safety systems and advanced cooling technologies
  • generation IV reactors

Benefits of Publishing in a Special Issue

  • Ease of navigation: Grouping papers by topic helps scholars navigate broad scope journals more efficiently.
  • Greater discoverability: Special Issues support the reach and impact of scientific research. Articles in Special Issues are more discoverable and cited more frequently.
  • Expansion of research network: Special Issues facilitate connections among authors, fostering scientific collaborations.
  • External promotion: Articles in Special Issues are often promoted through the journal's social media, increasing their visibility.
  • e-Book format: Special Issues with more than 10 articles can be published as dedicated e-books, ensuring wide and rapid dissemination.

Further information on MDPI's Special Issue policies can be found here.

Published Papers (1 paper)

Order results
Result details
Select all
Export citation of selected articles as:
18 pages, 5702 KiB  
Article
Applicability Analysis of Reduced-Order Methods with Proper Orthogonal Decomposition for Neutron Diffusion in Molten Salt Reactor
by Zhengyang Zhou, Ming Lin, Maosong Cheng, Yuqing Dai and Xiandi Zuo
Energies 2025, 18(8), 1893; https://doi.org/10.3390/en18081893 - 8 Apr 2025
Viewed by 170
Abstract
The high-dimensional integral–differential nature of the neutron transport equation and the complexity of nuclear reactors result in high computational costs. A set of reduced-order modeling frameworks based on Proper Orthogonal Decomposition (POD) is developed to improve the computational efficiency for neutron diffusion calculations [...] Read more.
The high-dimensional integral–differential nature of the neutron transport equation and the complexity of nuclear reactors result in high computational costs. A set of reduced-order modeling frameworks based on Proper Orthogonal Decomposition (POD) is developed to improve the computational efficiency for neutron diffusion calculations while maintaining accuracy, especially for small samples. For modal coefficient calculations, three methods—Galerkin, radial basis function (RBF), and Deep Neural Network (DNN)—are introduced and analyzed for molten salt reactors. The results show that all three reduced-order models achieve sufficient accuracy, with neutron flux L2 errors below 1% and delayed neutron precursor (DNP) L2 errors below 2.4%, while the acceleration ratios exceed 800. Among these, the POD–Galerkin model demonstrates superior performance, achieving average L2 errors of less than 0.00658% for neutron flux and 1.01% for DNP concentration, with an acceleration ratio of approximately 1800 and excellent extrapolation ability. The POD–Galerkin reduced-order model significantly enhances the computational efficiency for solving neutron multi-group diffusion equations and DNP conservation equations in molten salt reactors while preserving the solution accuracy, making it ideal for a liquid fuel molten salt reactor in the case of small samples. Full article
(This article belongs to the Special Issue Nuclear Engineering and Nuclear Fuel Safety)
Show Figures

Figure 1

Back to TopTop