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Nuclear Fuel and Fuel Cycle Technology

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

Deadline for manuscript submissions: 10 June 2026 | Viewed by 2402

Special Issue Editors


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Guest Editor
Research Centre Rez (CVR), Husinec-Rez, Czech Republic
Interests: nuclear technology; nuclear fuel; nuclear energy; fuel cycle

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Guest Editor
Department of Mechanical, Energy, Management and Transport Engineering (DIME), University of Genoa, Via all'Opera Pia, 15A, 16145 Genova, GE, Italy
Interests: nuclear energy; nuclear technology; innovative nuclear fuel cycles; neutronics; CFD; advanced nuclear systems; energy scenarios; nuclear hydrogen production; HTR; LFR; GFR; ADS; SMR; nuclear space reactors
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Guest Editor
Department of Energy, Polytechnic of Milan, Via La Masa 34, 20156 Milan, Italy
Interests: nuclear energy; nuclear technology; nuclear fuel; modeling and simulation; irradiation experiment

Special Issue Information

Dear Colleagues,

Nuclear fuel and fuel cycle technology remain pivotal for advancing safe, efficient, and sustainable nuclear energy systems. As the global demand for clean and reliable energy intensifies, the continuous improvement of fuel materials, fuel cycle strategies, and reactor performance becomes increasingly crucial. Recent advancements in nuclear fuel research have focused on enhancing fuel efficiency, minimizing waste generation, and improving the sustainability of nuclear power through innovative closed and open fuel cycle approaches.

This Special Issue aims to gather high-quality original research articles and comprehensive reviews that explore state-of-the-art developments in nuclear fuel materials, advanced fuel cycles, and novel fuel designs. We invite contributions that address key challenges and opportunities in the following areas:

  • Innovative nuclear fuel materials: development of accident-tolerant and advanced technology fuels (ATFs), high-assay low-enriched uranium (HALEU), and other advanced fuel compositions that enhance performance and safety.
  • Advanced fuel cycle strategies: optimization of fuel utilization in both open and closed fuel cycles, including new methodologies for spent fuel recycling and reprocessing.
  • Innovative fuel designs: research on next-generation fuel geometries and materials to improve thermal performance, longevity, and safety margins in both conventional and advanced reactors.
  • Fuel recycling and waste management: novel approaches for reprocessing spent fuel, reducing high-level radioactive waste, and improving the sustainability of nuclear energy.
  • Experimental methods and computational models: the use of advanced experimental techniques, simulations, and theoretical frameworks to optimize fuel behavior, neutron economy, and fuel cycle performance.

This Special Issue provides a platform for researchers, industry professionals, and policymakers to exchange ideas and insights that support the safety, efficiency, and long-term sustainability of nuclear energy systems. By fostering interdisciplinary collaboration and highlighting innovative approaches, this collection aims to contribute to the future development of resilient, economically viable, and environmentally responsible nuclear fuel technologies.

We welcome submissions that offer novel perspectives, experimental breakthroughs, and comprehensive analyses that push the boundaries of nuclear fuel research. Both original research articles and in-depth review papers are encouraged.

Dr. Vincenzo Romanello
Dr. Guglielmo Lomonaco
Dr. Davide Pizzocri
Guest Editors

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

  • closed and advanced nuclear fuel cycles
  • advanced and innovative nuclear fuels
  • sustainability of nuclear energy
  • nuclear waste minimization
  • sustainable resource exploitation

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Published Papers (2 papers)

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Research

20 pages, 2577 KB  
Article
MSR Fuel and Thermohydraulic: Modeling of Energy Well Experimental Loop in TRACE Code
by Giacomo Longhi, Guglielmo Lomonaco, Tomáš Melichar and Guido Mazzini
Energies 2026, 19(4), 1098; https://doi.org/10.3390/en19041098 - 21 Feb 2026
Viewed by 555
Abstract
The transition toward carbon-neutral energy systems has revived interest in nuclear technologies, particularly small and micro modular reactors (SMRs and MMRs) as flexible, safe and efficient alternatives to conventional large-scale power plans. In the Czech Republic, Centrum výzkumu Řez (CVŘ) is developing Energy [...] Read more.
The transition toward carbon-neutral energy systems has revived interest in nuclear technologies, particularly small and micro modular reactors (SMRs and MMRs) as flexible, safe and efficient alternatives to conventional large-scale power plans. In the Czech Republic, Centrum výzkumu Řez (CVŘ) is developing Energy Well (EW), a molten salt-cooled micro modular reactor concept employing FLiBe (Fluoride Lithium Beryllium) as primary and secondary coolant and a supercritical CO2 (sCO2) tertiary loop. A dedicated experimental facility was built to reproduce EW operating conditions and provide critical data on thermohydraulic behavior, fuel properties and heat-transfer mechanisms. This paper presents the development and assessment of a TRACE (TRAC/RELAP Advanced Computational Engine) model of the experimental facility, including specific methodologies for the main heater and the heat exchanger. Model accuracy was assessed through comparison with experimental commissioning data. The simulations demonstrated overall model consistency, especially regarding the heat exchanger and the main heater general performances, while some discrepancies were observed inside the main heater graphitic core. Other discrepancies were observed along the loop, mainly resulting from modeling simplifications and lack of information regarding certain experimental loop phenomena. In particular, the pressure calculation showed large inconsistencies mainly connected to the complexity of pressure measurements in molten salt circuits and the lack of specific head loss correlations. This study also helped identify broader issues in both the code (persistent error in generating CO2 property tables and instabilities resulting from FLiBe interactions with non-condensable gases) and the experimental loop (defect in the heat exchanger filling and uncertainties on sensors location), also contributing to resolving sensor-related inconsistencies in the facility. Results confirm TRACE as a reliable tool for modeling molten salt systems, regarding the temperature distribution and the heat transfer. However, depending on the specific experimental case, this paper introduces specific limitations, such as some inconsistencies in the pressure drops distribution, in order to support the future development of TRACE code. Beyond technical advances, this work provides unique experimental data and fosters international collaboration in advancing SMR and molten salt reactor technologies. Full article
(This article belongs to the Special Issue Nuclear Fuel and Fuel Cycle Technology)
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18 pages, 3812 KB  
Article
Advancements in PARCS/TRACE Coupling and Simulation of Rod Ejection Accident in VVER-1000 Nuclear Reactor
by Gianluca Nesti, Guido Mazzini, Antonio Dambrosio and Matteo D’Onorio
Energies 2025, 18(20), 5500; https://doi.org/10.3390/en18205500 - 18 Oct 2025
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Abstract
As the global energy demand continues to grow and the pursuit of clean and sustainable resources intensifies, nuclear energy stands out as a secure, reliable, and low-emission solution. The complexity of nuclear power plant behavior under various operating conditions necessitates advanced simulation tools [...] Read more.
As the global energy demand continues to grow and the pursuit of clean and sustainable resources intensifies, nuclear energy stands out as a secure, reliable, and low-emission solution. The complexity of nuclear power plant behavior under various operating conditions necessitates advanced simulation tools capable of capturing the interplay between multiple physical phenomena. Among these, multi-physics coupling, particularly between neutronics and thermal hydraulics, is a well-established approach for accurately modeling transient scenarios with strong feedback effects. In this context, PARCS and TRACE codes, developed by the U.S. Nuclear Regulatory Commission, are widely used for coupled neutronic/thermal-hydraulic analyses and can be operated via the SNAP graphical interface. However, the current version of SNAP does not support automatic coupling for hexagonal core geometries, such as those found in VVER-type reactors. To address this limitation, a dedicated tool was developed to facilitate the coupling process between PARCS and TRACE for hexagonal cores. The proposed methodology was tested through the simulation of a rod ejection accident in a VVER-1000 reactor, demonstrating the validity of the methodology and confirming that the multi-physics approach provides more accurate, best-estimate results. Full article
(This article belongs to the Special Issue Nuclear Fuel and Fuel Cycle Technology)
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