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Applied Sciences
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Breeding Blanket: Design, Technology and Performance
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Breeding Blanket: Design, Technology and Performance

A special issue of Applied Sciences (ISSN 2076-3417). This special issue belongs to the section "Materials Science and Engineering".

Deadline for manuscript submissions: closed (10 November 2021) | Viewed by 14434

Special Issue Editors

Dr. Bradut E. Ghidersa

E-Mail Website
Guest Editor
Karlsruher Institut für Technologie (KIT), Institut für Neutronenphysik und Reaktortechnik (INR), Postfach 3640, D-76021 Karlsruhe, Germany
Interests: high heat flux testing of fusion-related components; breeding blanket and divertor technology; thermal–hydraulic modelling; heat pipes
Dr. Lorenzo Boccaccini

E-Mail Website
Guest Editor
Karlsruher Institut für Technologie (KIT), Institut für Neutronenphysik und Reaktortechnik (INR), Postfach 3640, D-76021 Karlsruhe, Germany
Interests: high heat flux testing of fusion related components; breeding blanket and divertor technology; thermal-hydraulic modelling; heat pipes

Special Issue Information

Dear Colleagues,

A prerequisite for establishing fusion power as one of the sources for low-carbon electricity generation is the demonstration of the capability of future fusion powerplants to achieve tritium self-sufficiency and to efficiently produce electricity; both these functions are related to breeding blanket systems, a key component in the transition from ITER to the first generation of nuclear reactor. The future DEMOnstration fusion power plant should be the first to show that, with a breeding blanket system, it is possible to deliver several hundred megawatts of electrical energy in net and operate in a closed fuel cycle. With ITER construction moving forward, the DEMO projects are transitioning from a preconceptual to conceptual phase, moving towards the beginning of an engineering phase in about ten years.

New material developments and novel manufacturing processes have made their way into blanket design, raising the hopes for more cost-effective designs that still benefit from the high cooling capabilities of complex structures. The presence of the test blanket modules (TBM) program in ITER has also brought about a paradigm change in the way the breeding blanket concepts are developed and nuclear licensing, with quality and qualification requirements now being an important part of the process.

This Special Issue aims to provide an overview of the current status of breeding blanket designs as well as the main related technological aspects.

Original research articles and reviews are welcome. The research areas may include (but are not limited to) the following:

  • Breeding blanket concepts;
  • Specific material development and qualification including both functional and structural materials;
  • Blanket manufacturing technologies;
  • Modelling in terms of thermal–hydraulic aspects, material behavior
    and electromagnetic effects;
  • Tritium production and control;
  • Safety aspects.

We look forward to receiving your contributions.

Dr. Bradut E. Ghidersa
Dr. Lorenzo Boccaccini
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 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. Applied Sciences 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 2400 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

  • breeding blanket
  • DEMO
  • CFETR
  • JADEMO
  • K-DEMO
  • IFPP
  • ITER-TBM
  • tritium self-sufficiency
  • breeding materials
  • MHD

Published Papers (7 papers)

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Editorial

Jump to: Research

3 pages, 169 KiB  
Editorial
Special Issue on “Breeding Blanket: Design, Technology and Performance”
by Bradut-Eugen Ghidersa and Lorenzo Virgilio Boccaccini
Appl. Sci. 2022, 12(20), 10295; https://doi.org/10.3390/app122010295 - 13 Oct 2022
Viewed by 728
Abstract
A prerequisite for establishing fusion power as one of the sources for low-carbon electricity generation is the demonstration of the capability of future fusion power plants in achieving tritium self-sufficiency and its capability of efficiently producing electricity; both these functions are related to [...] Read more.
A prerequisite for establishing fusion power as one of the sources for low-carbon electricity generation is the demonstration of the capability of future fusion power plants in achieving tritium self-sufficiency and its capability of efficiently producing electricity; both these functions are related to breeding blanket systems, a key component in the transition from ITER to the first generation of nuclear reactors [...] Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)

Research

Jump to: Editorial

9 pages, 2863 KiB  
Article
Design of the Test Section for the Experimental Validation of Antipermeation and Corrosion Barriers for WCLL BB
by Marco Utili, Ciro Alberghi, Luigi Candido, Fabio Di Fonzo, Francesca Papa and Alessandro Venturini
Appl. Sci. 2022, 12(3), 1624; https://doi.org/10.3390/app12031624 - 03 Feb 2022
Cited by 5 | Viewed by 1519
Abstract
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction. Several technologies were investigated as antipermeation and corrosion [...] Read more.
Tritium permeation into the Primary Heat Transfer System (PHTS) of DEMO and ITER reactors is one of the challenging issues to be solved in order to demonstrate the feasibility of nuclear fusion power plants construction. Several technologies were investigated as antipermeation and corrosion barriers to reduce the tritium permeation flux from the breeder into the PHTS. Within this frame, alumina coating manufactured by Pulsed Laser Deposition (PLD) and Atomic Layer Deposition (ALD) are two of the main candidates for the Water Cooled Lithium Lead (WCLL) Breeder Blanket (BB). In order to validate the performance of the coatings on relevant WCLL BB geometries, a mock-up was designed and will be characterized in an experimental facility operating with flowing lithium-lead, called TRIEX-II. The present work aims to illustrate the preliminary engineering design of a WCLL BB mock-up in order to deeply investigate permeation of hydrogen isotopes through PHTS water pipes. The permeation tests are planned in the temperature range between 330 and 500 °C, with hydrogen and deuterium partial pressure in the range of 1–1000 Pa. The hydrogen isotopes transport analysis carried out for the design and integration of the mock-up in TRIEX-II facility is also shown. Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)
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13 pages, 2727 KiB  
Article
Best-Estimate for System Codes (BeSYC): A New Software to Perform Best-Estimate Plus Uncertainty Analyses with Thermal-Hydraulic and Safety System Codes for Both Fusion and Fission Scenarios
by Bruno Gonfiotti, Michela Angelucci, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci and Robert Stieglitz
Appl. Sci. 2022, 12(1), 311; https://doi.org/10.3390/app12010311 - 29 Dec 2021
Cited by 2 | Viewed by 1055
Abstract
The development and the validation of old and new software in relevant DEMO reactor conditions have been exploited in the latest years within the EUROfusion Consortium. The aim was to use—if possible—the software already validated for fission reactors and to fill the gaps [...] Read more.
The development and the validation of old and new software in relevant DEMO reactor conditions have been exploited in the latest years within the EUROfusion Consortium. The aim was to use—if possible—the software already validated for fission reactors and to fill the gaps with new ad-hoc software. As contribution to this effort, the Karlsruhe Institute of Technology (KIT) developed and tested a novel software to apply the Best-Estimate Model Calibration and Prediction through Experimental Data Assimilation methodology to the system codes RELAP5-3D, MELCOR 1.8.6, and MELCOR 2.2. This software is called Best-estimate for SYstem Codes (BeSYC), and it is developed as a MATLAB App. The application is in charge of applying the mathematical framework of the methodology, writing and executing the code runs required by the methodology, and printing the obtained results. The main goal of BeSYC is to wrap up the methodology in a software suitable to be used by any user through a simple graphical user interface. Albeit developed in the fusion research context, BeSYC can be applied to any reactor/scenario type supported by the specific system code. The goals of BeSYC, the mathematical framework, the main characteristics, and the performed verification and validation activities are described in this paper. Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)
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17 pages, 13152 KiB  
Article
Post-Test Numerical Analysis of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions with the MELCOR Fusion Code
by Michela Angelucci, Bruno Gonfiotti, Bradut-Eugen Ghidersa, Xue Zhou Jin, Mihaela Ionescu-Bujor, Sandro Paci and Robert Stieglitz
Appl. Sci. 2022, 12(1), 187; https://doi.org/10.3390/app12010187 - 24 Dec 2021
Cited by 3 | Viewed by 1886
Abstract
The validation of numerical tools employed in the analysis of incidental transients in a fusion reactor is a topic of main concern. KIT is taking part in this task providing both experimental data and by performing numerical analysis in support of the main [...] Read more.
The validation of numerical tools employed in the analysis of incidental transients in a fusion reactor is a topic of main concern. KIT is taking part in this task providing both experimental data and by performing numerical analysis in support of the main codes used for the safety analyses of the Helium Cooled Pebble Bed (HCPB) blanket concept. In recent years, an experimental campaign has been performed in the KIT-HELOKA facility to investigate the behavior of a First Wall Mock-Up (FWMU) under Loss Of Flow Accident (LOFA) conditions. The aim of the experimental campaign was twofold: to check the expected DEMO thermal-hydraulics conditions during normal and off-normal conditions and to provide robust data for code validation. The present work is part of these validation efforts, and it deals with the analysis of the LOFA experimental campaign with the system code MELCOR 1.8.6 for fusion. A best-estimate methodology has been used in support of this analysis to ease the distinction between user’s assumptions and code limitations. The numerical analyses are here described together with their goals, achievements, and lesson learnt. Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)
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31 pages, 11701 KiB  
Article
Experimental Investigation of a Helium-Cooled Breeding Blanket First Wall under LOFA Conditions and Pre-Test and Post-Test Numerical Analysis
by Bradut-Eugen Ghidersa, Bruno Gonfiotti, André Kunze, Valentino Di Marcello, Mihaela Ionescu-Bujor, Xue Zhou Jin and Robert Stieglitz
Appl. Sci. 2021, 11(24), 12010; https://doi.org/10.3390/app112412010 - 16 Dec 2021
Cited by 5 | Viewed by 1784
Abstract
The experimental investigation of a prototypical set-up simulating a loss of flow accident in a helium-cooled breeding blanket first wall mock-up under typical heat load conditions is presented. The experimental campaign reproduces the expected DEMO thermal-hydraulics conditions during normal and off-normal situations and [...] Read more.
The experimental investigation of a prototypical set-up simulating a loss of flow accident in a helium-cooled breeding blanket first wall mock-up under typical heat load conditions is presented. The experimental campaign reproduces the expected DEMO thermal-hydraulics conditions during normal and off-normal situations and aims at providing some insight into the fast transients associated with the loss of flow in the blanket first wall. The experimental set-up and the definition of the experimental matrix are discussed, including pre-test analysis performed in support of these activities. The major experimental results are discussed, and a procedure of using the acquired data for validating and calibrating the RELAP-3D model of the mock-up is introduced. All these activities contributed to the creation of a relevant theoretical and practical experience that can be used in further studies concerning incidental transients in real-plant scenarios in the framework of DEMO plant fusion safety activities. Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)
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47 pages, 22193 KiB  
Article
Technological Processes for Steel Applications in Nuclear Fusion
by Michael Rieth, Michael Dürrschnabel, Simon Bonk, Ute Jäntsch, Thomas Bergfeldt, Jan Hoffmann, Steffen Antusch, Esther Simondon, Michael Klimenkov, Carsten Bonnekoh, Bradut-Eugen Ghidersa, Heiko Neuberger, Jörg Rey, Christian Zeile, Gerald Pintsuk and Giacomo Aiello
Appl. Sci. 2021, 11(24), 11653; https://doi.org/10.3390/app112411653 - 08 Dec 2021
Cited by 10 | Viewed by 2500
Abstract
Plasma facing components for energy conversion in future nuclear fusion reactors require a broad variety of different fabrication processes. We present, along a series of studies, the general effects and the mutual impact of these processes on the properties of the EUROFER97 steel. [...] Read more.
Plasma facing components for energy conversion in future nuclear fusion reactors require a broad variety of different fabrication processes. We present, along a series of studies, the general effects and the mutual impact of these processes on the properties of the EUROFER97 steel. We also consider robust fabrication routes, which fit the demands for industrial environments. This includes heat treatment, fusion welding, machining, and solid-state bonding. Introducing and following a new design strategy, we apply the results to the fabrication of a first-wall mock-up, using the same production steps and processes as for real components. Finally, we perform high heat flux tests in the Helium Loop Karlsruhe, applying a few hundred short pulses, in which the maximum operating temperature of 550 °C for EUROFER97 is finally exceeded by 100 K. Microstructure analyses do not reveal critical defects or recognizable damage. A distinct ferrite zone at the EUROFER/ODS steel interface is detected. The main conclusions are that future breeding blankets can be successfully fabricated by available industrial processes. The use of ODS steel could make a decisive difference in the performance of breeding blankets, and the first wall should be completely fabricated from ODS steel or plated by an ODS carbon steel. Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)
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27 pages, 9350 KiB  
Article
The DEMO Water-Cooled Lead–Lithium Breeding Blanket: Design Status at the End of the Pre-Conceptual Design Phase
by Pietro Arena, Alessandro Del Nevo, Fabio Moro, Simone Noce, Rocco Mozzillo, Vito Imbriani, Fabio Giannetti, Francesco Edemetti, Antonio Froio, Laura Savoldi, Simone Siriano, Alessandro Tassone, Fernando Roca Urgorri, Pietro Alessandro Di Maio, Ilenia Catanzaro and Gaetano Bongiovì
Appl. Sci. 2021, 11(24), 11592; https://doi.org/10.3390/app112411592 - 07 Dec 2021
Cited by 53 | Viewed by 3846
Abstract
The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) [...] Read more.
The Water-Cooled Lead–Lithium Breeding Blanket (WCLL BB) is one of the two blanket concept candidates to become the driver blanket of the EU-DEMO reactor. The design was enacted with a holistic approach. The influence that neutronics, thermal-hydraulics (TH), thermo-mechanics (TM) and magneto-hydro-dynamics (MHD) may have on the design were considered at the same time. This new approach allowed for the design team to create a WCLL BB layout that is able to comply with different foreseen requirements in terms of integration, tritium self-sufficiency, and TH and TM needs. In this paper, the rationale behind the design choices and the main characteristics of the WCLL BB needed for the EU-DEMO are reported and discussed. Finally, the main achievements reached during the pre-conceptual design phase and some remaining open issues to be further investigated in the upcoming conceptual design phase are reported as well. Full article
(This article belongs to the Special Issue Breeding Blanket: Design, Technology and Performance)
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