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Advanced Nuclear Energy Systems: Design and Engineering Innovations

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

Deadline for manuscript submissions: 15 April 2026 | Viewed by 570

Special Issue Editor


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Guest Editor
Department of Nuclear Energy and Radiochemistry, AGH University, al. Mickiewicza 30, 30-059 Krakow, Poland
Interests: advanced nuclear reactor systems—HTGRs, LFRs, MSRs, and ADS; innovative core and fuel cycle design; monte carlo system development and reactor physics modeling; self-regulating and load-following reactor technologies

Special Issue Information

Dear Colleagues,

This Special Issue focuses on cutting-edge research and technological developments that are shaping the future of nuclear reactor design and system engineering. As advanced nuclear energy systems move from concept to reality, there is a growing demand for innovations that enhance performance, safety, and operational flexibility.

We invite original research and reviews that explore novel reactor designs, core and fuel architectures, advanced fuel cycles, and the integration of emerging technologies in system engineering. Topics related to thermal hydraulics, passive safety, material performance under extreme conditions, and innovative fuel utilization strategies are especially welcome. Contributions that demonstrate engineering-driven solutions to current design challenges are of particular interest.

Multi-physics modeling, predictive simulations, and digital engineering tools—including digital twins—are also welcome, particularly when they support or inform innovative design approaches.

This Special Issue aims to provide a platform for showcasing the latest progress in nuclear system design, encouraging cross-disciplinary collaboration and supporting the development of next-generation nuclear technologies.

Topics of interest include the following:

  • Advanced reactor concepts (SMRs, HTGRs, MSRs, fast reactors);
  • Core and fuel design innovations;
  • Advanced fuel cycle strategies and reprocessing technologies;
  • Passive safety systems and self-regulating mechanisms;
  • Multi-physics and system-level modeling;
  • Thermal-hydraulics and neutronics;
  • Materials and structural design for high-performance environments;
  • Digital twins and smart reactor technologies;
  • Simulation-driven design and engineering methods.

Prof. Dr. Jerzy Cetnar
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 250 words) can be sent to the Editorial Office for assessment.

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

  • advanced nuclear reactor design
  • small modular reactors (SMRs)
  • high-temperature gas-cooled reactors (HTGRs)
  • molten salt reactors (MSRs)
  • fast neutron reactors
  • nuclear core and fuel design
  • advanced nuclear fuel cycles
  • passive safety in nuclear reactors
  • reactor thermal hydraulics
  • multi-physics simulation
  • digital twins for nuclear systems

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Published Papers (2 papers)

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Research

18 pages, 1557 KB  
Article
Preliminary Study of Transient Simulations in the MSRE Primary Loop with Modelica/TRANSFORM
by Chenrui Mao, Jian Guo, Yang Zou and Rui Yan
Energies 2026, 19(1), 13; https://doi.org/10.3390/en19010013 - 19 Dec 2025
Abstract
Compared to conventional solid-fueled reactors, the liquid fuel transport in molten salt reactors (MSRs) leads to a strong coupling between thermal-hydraulics and neutronics. To enable system-level analysis of MSR, this study focuses on the main loop of the Molten Salt Reactor Experiment (MSRE). [...] Read more.
Compared to conventional solid-fueled reactors, the liquid fuel transport in molten salt reactors (MSRs) leads to a strong coupling between thermal-hydraulics and neutronics. To enable system-level analysis of MSR, this study focuses on the main loop of the Molten Salt Reactor Experiment (MSRE). A system model is developed using the open-source, multiphysics modeling platform Modelica/TRANSFORM. The model is validated against ORNL experimental data under various conditions, including zero-power pump start/stop, natural circulation. In addition, the xenon transport behavior is compared with predictions from a two-region analytical model. Results indicate that the number of discretized core nodes significantly influences the estimation of delayed neutron precursor (DNP) losses due to fuel circulation. The applicability of the ANSI/ANS-5.1 decay heat model, originally developed for light water reactors, is confirmed to be conservative when applied to MSRE conditions. Finally, natural circulation behavior with decay heat transport is further analyzed. Full article
(This article belongs to the Special Issue Advanced Nuclear Energy Systems: Design and Engineering Innovations)
24 pages, 3309 KB  
Article
High-Fidelity Monte Carlo Modelling of the HTGR Fuel Cycle for Fuel Utilization Optimization and Nuclear Safety Assurance
by Jerzy Cetnar
Energies 2025, 18(24), 6410; https://doi.org/10.3390/en18246410 - 8 Dec 2025
Viewed by 330
Abstract
This paper presents a numerical study of fuel cycle performance and time–space characteristics of a research-scale high temperature gas-cooled reactor (HTGR) using high-fidelity Monte Carlo simulations with continuous-energy and double-heterogeneity modeling. Three core geometries (V1, V2, V3) and three fuel enrichment levels (5%, [...] Read more.
This paper presents a numerical study of fuel cycle performance and time–space characteristics of a research-scale high temperature gas-cooled reactor (HTGR) using high-fidelity Monte Carlo simulations with continuous-energy and double-heterogeneity modeling. Three core geometries (V1, V2, V3) and three fuel enrichment levels (5%, 8%, 12%) were analyzed with axial batch refueling strategies. Results show a strong dependence of fuel utilization on geometry and enrichment. The V2 configuration achieves the best performance, with sub-cycle lengths up to 550 days and fuel utilization over 91% at 12% enrichment. V1 and V3 yield shorter cycles but maintain stable power and temperature profiles. In all cases, fuel temperature remained below 1200 K, ensuring a wide safety margin. The similarity of power distributions for different enrichments indicates that a single core design can accommodate various fuel types without compromising safety. These findings support the selection of V2 as a reference configuration for a future HTGR research reactor. Full article
(This article belongs to the Special Issue Advanced Nuclear Energy Systems: Design and Engineering Innovations)
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