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Energies
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Latest Theoretical, Technological, and Experimental Advances in Fusion Devices
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Latest Theoretical, Technological, and Experimental Advances in Fusion Devices

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

Deadline for manuscript submissions: closed (31 August 2022) | Viewed by 10207
Submit your paper and select the Journal “Energies” and the Special Issue “Latest Theoretical, Technological, and Experimental Advances in Fusion Devices” via: https://susy.mdpi.com/user/manuscripts/upload?journal=energies. Please contact the guest editor or the journal editor ([email protected]) for any queries.

Special Issue Editor

Dr. Vincenzo Paolo Loschiavo

E-Mail Website
Guest Editor
Department of Engineering, University of Sannio, 82100 Benevento, Italy
Interests: nuclear fusion; plasma modeling and control; computational electromagnetics; optimization and thermomechanical analyses in tokamaks; magnet design; energy harvesting

Special Issue Information

Dear Colleagues,

Nuclear fusion represents one of the most promising answers to worldwide energy issues: it is CO2-free, practically inexhaustible, safe, and only produces short-living radioactive waste. It is the energy powering the Sun and stars. The engineering and design of present and future devices still has to face several technical challenges, often involving tightly coupled multiphysics problems. Candidate solutions for them are under development, but the next stage is to demonstrate that they will also work at the scale of a reactor.

The aim of this Special Issue, titled “Latest Theoretical, Technological, and Experimental Advances in Fusion Devices”, of the International Open Access journal Energies, which is an SSCI and SCIE journal (2019 IF= 2.702), is to present innovative theoretical and technological solutions together with experimental results contributing to advance the development of fusion facilities.

Papers selected for this Special Issue are subject to a rigorous peer review procedure with the aim of fast and wide dissemination of research results, developments, and applications.

I am writing to warmly invite you to submit your original work to this Special Issue. I look forward to receiving your outstanding contribution.

Dr. Vincenzo Paolo Loschiavo
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

  • advances in fusion technology and engineering
  • design of magnets for fusion devices
  • advances in applied superconductivity
  • plasma heating and current drive systems technologies
  • plasma scenario design, optimization, and control
  • solutions for power exhaust management and integrated control
  • plasma detachment modelling and control
  • plasma alternative magnetic configurations
  • plasma facing components
  • plasma-material interactions
  • progress in blanket design (shielding, breeding, and liquid metals)
  • materials and nuclear technologies
  • thermal, hydraulic, and stress analyses in fusion devices
  • thermomechanical analyses and design of components for fusion devices
  • design and management of experimental facilities
  • safety and reliability issues in nuclear fusion
  • design and development of diagnostics
  • system analysis and model integration
  • technologies for tritium extraction and fuel cycle

Published Papers (6 papers)

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Research

13 pages, 6740 KiB  
Article
Effectiveness of the Chebyshev Approximation in Magnetic Field Line Tracking
by Raffaele Albanese, Andrea Gaetano Chiariello, Raffaele Fresa, Antonio Iaiunese, Raffaele Martone and Pasquale Zumbolo
Energies 2022, 15(20), 7619; https://0-doi-org.brum.beds.ac.uk/10.3390/en15207619 - 15 Oct 2022
Cited by 2 | Viewed by 797
Abstract
The tracking of magnetic field lines can be very expensive, in terms of computational burden, when the field sources are numerous and have complex geometries, especially when accuracy is a priority, because an evaluation of the field is required in many situations. In [...] Read more.
The tracking of magnetic field lines can be very expensive, in terms of computational burden, when the field sources are numerous and have complex geometries, especially when accuracy is a priority, because an evaluation of the field is required in many situations. In some important applications, the computational cost can be significantly reduced by using a suitable approximation of the field in the integrated regions. This paper shows how Chebyshev polynomials are well-suited for field interpolation in magnetic field-line tracking, then discusses the conditions in which they are most appropriate, and quantifies the effectiveness of parallel computing in the approximation procedures. Full article
(This article belongs to the Special Issue Latest Theoretical, Technological, and Experimental Advances in Fusion Devices)
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31 pages, 11067 KiB  
Article
A Fast Matrix Compression Method for Large Scale Numerical Modelling of Rotationally Symmetric 3D Passive Structures in Fusion Devices
by Francesca Cau, Andrea Gaetano Chiariello, Guglielmo Rubinacci, Valentino Scalera, Antonello Tamburrino, Salvatore Ventre and Fabio Villone
Energies 2022, 15(9), 3214; https://0-doi-org.brum.beds.ac.uk/10.3390/en15093214 - 27 Apr 2022
Cited by 2 | Viewed by 1471
Abstract
This paper illustrates the development of a recursive QR technique for the analysis of transient events, such as disruptions or scenario evolution, in fusion devices with three-dimensional conducting structures using an integral eddy current formulation. An integral formulation involves the solution, at each [...] Read more.
This paper illustrates the development of a recursive QR technique for the analysis of transient events, such as disruptions or scenario evolution, in fusion devices with three-dimensional conducting structures using an integral eddy current formulation. An integral formulation involves the solution, at each time step, of a large full linear system. For this reason, a direct solution is impractical in terms of time and memory consumption. Moreover, typical fusion devices show a symmetric/periodic structure. This can be properly exploited when the plasma and other sources possess the same symmetry/periodicity of the structure. Indeed, in this case, the computation can be reduced to only a single sector of the overall structure. In this work the periodicity and the symmetries are merged in the recursive QR technique, exhibiting a huge decrease in the computational cost. Finally, the proposed technique is applied to a realistic large-scale problem related to the International Thermonuclear Experimental Reactor (ITER). Full article
(This article belongs to the Special Issue Latest Theoretical, Technological, and Experimental Advances in Fusion Devices)
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14 pages, 5952 KiB  
Article
Plasma Scenarios for the DTT Tokamak with Optimized Poloidal Field Coil Current Waveforms
by Antonio Castaldo, Raffaele Albanese, Roberto Ambrosino and Flavio Crisanti
Energies 2022, 15(5), 1702; https://0-doi-org.brum.beds.ac.uk/10.3390/en15051702 - 24 Feb 2022
Cited by 9 | Viewed by 1823
Abstract
In the field of nuclear fusion, the power exhaust problem is still an open issue and represents one of the biggest problems for the realization of a commercial fusion power plant. According to the “European Fusion Roadmap”, a dedicated facility able to investigate [...] Read more.
In the field of nuclear fusion, the power exhaust problem is still an open issue and represents one of the biggest problems for the realization of a commercial fusion power plant. According to the “European Fusion Roadmap”, a dedicated facility able to investigate possible solutions to heat exhaust is mandatory. For this purpose, the mission of the Divertor Tokamak Test (DTT) tokamak is the study of different solutions for the divertor. This paper presents the plasma scenarios for standard and alternative configurations in DTT. The Single Null scenario is described in detail. The alternative configurations are also presented, showing the good flexibility of the machine. Full article
(This article belongs to the Special Issue Latest Theoretical, Technological, and Experimental Advances in Fusion Devices)
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11 pages, 5850 KiB  
Article
Preliminary Design of a Heat Pipe-Cooled Blanket for CFETR
by Dianle Wang and Yun Guo
Energies 2021, 14(21), 6879; https://0-doi-org.brum.beds.ac.uk/10.3390/en14216879 - 21 Oct 2021
Cited by 2 | Viewed by 1519
Abstract
Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, the design, production, processing, and accident maintenance of blankets are all huge challenges for traditional water/gas-cooled blankets. Blankets are the bridge for heat transfer and tritium production. A [...] Read more.
Blankets are a difficult problem for fusion engineering design. Because of the complex flow channels, the design, production, processing, and accident maintenance of blankets are all huge challenges for traditional water/gas-cooled blankets. Blankets are the bridge for heat transfer and tritium production. A high-performance blanket with simplified structure is obviously beneficial for engineering, safety, and the economy. In this study, gravity heat pipes instead of coolant flow channels are adopted to remove the heat. Compared with coolant-cooled systems, heat pipes may be simpler and more reliable. The in-vessel and in-box loss of coolant accident (LOCA) will not occur because there is no coolant in the blanket. Moreover, a damaged heat pipe may be replaced easily compared to a damaged water-cooled blanket. In this study, a hypothetical heat pipe-cooled blanket for the China Fusion Engineering Test Reactor (CFETR) was proposed and one module of the blanket was analyzed by numerical simulation. The results were compared with those of a water-cooled blanket, and the temperature distribution of the heat pipe-cooled blanket is more uniform. This study verified the preliminary feasibility of heat pipe-cooled blankets and provided a fresh idea for blanket design. Full article
(This article belongs to the Special Issue Latest Theoretical, Technological, and Experimental Advances in Fusion Devices)
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15 pages, 6379 KiB  
Article
Cost Assessment of a Tokamak Fusion Reactor with an Inventive Method for Optimum Build Determination
by Gahyung Jo, Jae-Min Kwon, Ara Cho, Hyun-Kyung Chung and Bong-Guen Hong
Energies 2021, 14(20), 6817; https://0-doi-org.brum.beds.ac.uk/10.3390/en14206817 - 18 Oct 2021
Cited by 3 | Viewed by 2049
Abstract
An inventive method was applied to determine the minimum major radius, R0, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses were carried out [...] Read more.
An inventive method was applied to determine the minimum major radius, R0, and the optimum build of a tokamak fusion reactor that simultaneously meets all physics, engineering, and neutronics constraints. With a simple cost model, tokamak systems analyses were carried out over ranges of system parameters to find an optimum build of a tokamak fusion reactor at minimum cost. The impact of a wide range of physics parameters and advanced engineering elements on costs were also addressed. When a central solenoid was used to ramp up a plasma current, design solutions with a cost of electricity (COE) between 109 and 140 mills/kWh, direct capital cost between 5000 and 6000 M/USD, and net electric power, Pe between 1000 and 1600 MW could be found with a minimum R0 between 6.0 and 7.0 m, and fusion power, Pfusion between 2000 and 2800 MW. When the plasma current was driven by a non-inductive external system, the system size and costs could be reduced further; a COE between 98 and 130 mills/kWh, direct capital cost between 4000 and 5000 M$, and Pe between 1000 and 1420 MW could be found with a minimum R0 between 5.1 and 6.7 m, and Pfusion between 2000 and 2650 MW. Full article
(This article belongs to the Special Issue Latest Theoretical, Technological, and Experimental Advances in Fusion Devices)
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13 pages, 5982 KiB  
Article
Oxidation Experiments and Kinetics Analysis of Nuclear Graphite ET-10 by Gas Analysis and Microstructure Observation
by Yumeng Zhao, Yujie Dong, Yangping Zhou, Zhengcao Li and Zuoyi Zhang
Energies 2021, 14(19), 6392; https://0-doi-org.brum.beds.ac.uk/10.3390/en14196392 - 06 Oct 2021
Cited by 4 | Viewed by 1633
Abstract
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance and mechanical properties where the ability of oxidation resistance is usually concerned. Although the excellent performance of new graphite ET-10 was revealed by previous experiments regarding the [...] Read more.
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance and mechanical properties where the ability of oxidation resistance is usually concerned. Although the excellent performance of new graphite ET-10 was revealed by previous experiments regarding the accident conditions of a fission reactor, further studies are needed to oxidize the graphite under the conditions recommended by the ASTM D7542 standard. A test facility was designed and developed to oxidize the cylindrical specimen with a 10 L/min airflow. According to oxidation rates and microstructures of specimens, the chemical kinetics-controlled regime was determined as 675–750 °C, where the activation energy was obtained as 172.52 kJ/mol. The experiment results revealed the excellent ability of graphite ET-10 for oxidation resistance with lower oxidation rates and longer oxidation times compared with some mainstream graphite. The main reasons are the low contents of some impurities and the binder and the low active surface area due to the non-impregnation baking process undertaken to produce graphite with coal tar pitch coke. It should be noted that the evolution of oxidation behavior at the bottom part of the specimen (facing the airflow) was quicker than that at the upper part of the specimen. We also suggest that the abundance of oxygen supply and the good linearity of the Arrhenius plot are prerequisites of the chemical kinetics-controlled regime rather than sufficient conditions. Full article
(This article belongs to the Special Issue Latest Theoretical, Technological, and Experimental Advances in Fusion Devices)
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