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Advanced Composites and Coatings for Nuclear Applications
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Advanced Composites and Coatings for Nuclear Applications

A special issue of Coatings (ISSN 2079-6412). This special issue belongs to the section "Ceramic Coatings and Engineering Technology".

Deadline for manuscript submissions: closed (31 March 2022) | Viewed by 9100

Special Issue Editor

Dr. Cédric Sauder

E-Mail Website
Guest Editor
CEA, Service de Recherches Métallurgiques Appliquées, Université Paris-Saclay, 91191 Gif-sur-Yvette, France
Interests: ceramic composites; carbon; coatings; fibers; corrosion

Special Issue Information

Dear Colleagues,

Nuclear applications are for structural materials probably one of the most challenging. They have to whithstand severe nominal and accidental operating conditions. Moreover, they must allow safety maintenance operations, waste reprocessing and decontamination processes even after the end of operation. The main objective in this industry is always to improve the safety and the development of new composites materials and/or coatings is a great opportunity to achieve new designs and concepts.

This aim of this Special Issue is to publish original articles, critical reviews, as well as perspectives, from leading research in both academia and industry on all aspects related to recent advances in design, processing and development of composites and coatings for nuclear applications. The contributions on the new concepts, characterizations, simulation and the behavior in nominal and accidental conditions of materials are also welcome.

In particular, the topics of interest of this special issue includes, but are not limited to, the following:

  • Advanced coatings for nuclear applications
  • Composites for nuclear applications
  • Post-irradiation examination of composites or coatings
  • Corrosion behavior of composites or coatings in severe environment
  • New methods for coatings characterization
  • Tailoring the deposition process for nuclear applications
  • Additive manufacturing methods for composites processing
  • Evaluation of Complex Concentrated Alloys as coatings
  • Simulation/prediction of mechanical behavior of composites
  • Diffusion in coatings

Dr. Cédric Sauder
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. Coatings is an international peer-reviewed open access monthly 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

  • Coatings
  • Composites
  • Deposition and infiltration processes
  • Mechanical and microstructural characterization
  • Corrosion and post-irradiation behavior

Published Papers (6 papers)

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Research

28 pages, 23647 KiB  
Article
High-Temperature Interdiffusion of Tantalum and Niobium with SiC for Processing Hybrid Metal/CMC Components
by James Braun, Cédric Sauder, Christine Guéneau, Fiqiri Hodaj and Fanny Balbaud-Célérier
Coatings 2022, 12(7), 887; https://doi.org/10.3390/coatings12070887 - 22 Jun 2022
Cited by 2 | Viewed by 1504
Abstract
To ensure the leak tightness of SiC/SiC composites cladding, niobium and tantalum have been retained as liner/coating materials for their high melting point, ductility and weldability; however, their chemical compatibility at high temperatures towards SiC remains to be assessed. In the literature, large [...] Read more.
To ensure the leak tightness of SiC/SiC composites cladding, niobium and tantalum have been retained as liner/coating materials for their high melting point, ductility and weldability; however, their chemical compatibility at high temperatures towards SiC remains to be assessed. In the literature, large discrepancies in the composition of the reaction zone and the kinetics were noticed between some metallic liners and SiC. In this work, diffusion couple experiments between Nb and Ta with SiC and SiC/SiC were conducted at high temperatures (1050–1500 °C) to determine the diffusion paths and the reaction kinetics in order to estimate the lifetime of such coatings in nominal conditions. A detailed analysis of the interaction area was conducted as a function of temperature by a combination of experimental characterizations and thermodynamic calculations. No significant difference in the sandwich cladding materials was observed. The interfacial reactivity was found to be strongly higher than expected from literature data. C and Si were evidenced as the main diffusing species in the Nb/SiC and Ta/SiC systems. From the reaction layer thickness extrapolation in gas-cooled fast reactor operating conditions, niobium but especially tantalum have been approved as liner material in hybrid CMC/metal cladding materials from a chemical compatibility point of view. Full article
(This article belongs to the Special Issue Advanced Composites and Coatings for Nuclear Applications)
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19 pages, 7931 KiB  
Article
Oxidation of Silicon Carbide Composites for Nuclear Applications at Very High Temperatures in Steam
by Martin Steinbrueck, Mirco Grosse, Ulrike Stegmaier, James Braun and Christophe Lorrette
Coatings 2022, 12(7), 875; https://doi.org/10.3390/coatings12070875 - 21 Jun 2022
Cited by 8 | Viewed by 2007
Abstract
Single-rod oxidation and quench experiments at very high temperatures in steam atmosphere were conducted with advanced, nuclear grade SiCf/SiC CMC cladding tube segments. A transient experiment was performed until severe local degradation of the sample at maximum temperature of approximately 1845 [...] Read more.
Single-rod oxidation and quench experiments at very high temperatures in steam atmosphere were conducted with advanced, nuclear grade SiCf/SiC CMC cladding tube segments. A transient experiment was performed until severe local degradation of the sample at maximum temperature of approximately 1845 °C. The degradation was caused by complete consumption of the external CVD-SiC sealcoat, resulting in steam access to the fiber–matrix composite with less corrosion resistance. Approaching these very high temperatures was accompanied by accelerated gas release mainly of H2 and CO2, the formation of surface bubbles and white smoke. Three one-hour isothermal tests at 1700 °C in steam with final water flooding and one three-hour experiment with fast cool-down in Ar atmosphere were run under nominally identical conditions. All isothermally tested samples survived the tests without any macroscopic degradation. The mechanical performance of these quenched clad segments was not significantly affected, while maintaining a high capability to tolerate damages. Despite these harsh exposure conditions, load transfer between SiC fibers and matrix remained efficient, allowing the composites to accommodate deformation. Full article
(This article belongs to the Special Issue Advanced Composites and Coatings for Nuclear Applications)
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22 pages, 9853 KiB  
Article
Radiation Effect in Ti-Cr Multilayer-Coated Silicon Carbide under Silicon Ion Irradiation up to 3 dpa
by Ryo Ishibashi, Yasunori Hayashi, Huang Bo, Takao Kondo and Tatsuya Hinoki
Coatings 2022, 12(6), 832; https://doi.org/10.3390/coatings12060832 - 14 Jun 2022
Cited by 3 | Viewed by 1761
Abstract
Replacement of conventional Zircaloy fuel cladding with silicon carbide (SiC) fuel cladding is expected to significantly decrease the amount of hydrogen generated from fuel claddings by the reaction with steam during severe accidents. One of their critical issues addressed regarding practical application has [...] Read more.
Replacement of conventional Zircaloy fuel cladding with silicon carbide (SiC) fuel cladding is expected to significantly decrease the amount of hydrogen generated from fuel claddings by the reaction with steam during severe accidents. One of their critical issues addressed regarding practical application has been hydrothermal corrosion. Thus, the corrosion resistant coating technology using a Ti-Cr multilayer was developed to suppress silica dissolution from SiC fuel cladding into reactor coolant under normal operation. The effect of radiation on adhesion of the coating to SiC substrate and its microstructure characteristics were investigated following Si ion irradiation at 573 K up to 3 dpa for SiC. Measurement of swelling in pure Ti, pure Cr and SiC revealed that the maximum inner stress attributed to the swelling difference was generated between the coating and SiC substrate by irradiation of 1 dpa. No delamination and cracking were observed in cross-sectional specimens of the coated SiC irradiated up to 3 dpa. According to analyses using transmission electron microscopy, large void formation and cascade mixing due to irradiation were not observed in the coating. The swelling in the coating at 573 K was presumed to be caused by another mechanism during radiation such as point defects rather than void formation. Full article
(This article belongs to the Special Issue Advanced Composites and Coatings for Nuclear Applications)
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16 pages, 9288 KiB  
Article
Assessment of the Potential Diffusion Barriers between Tungsten and Silicon Carbide for Nuclear Fusion Application
by Yina Du, Baopu Wang, Yansong Zhong and Tatsuya Hinoki
Coatings 2022, 12(5), 639; https://doi.org/10.3390/coatings12050639 - 6 May 2022
Cited by 2 | Viewed by 2181
Abstract
A tungsten (W) material is a candidate for the first wall and silicon carbide (SiC) composites are candidates for the structural materials applied in nuclear fusion. SiC fiber-reinforced W composites are also developed for nuclear fusion applications. An effective diffusion barrier is required [...] Read more.
A tungsten (W) material is a candidate for the first wall and silicon carbide (SiC) composites are candidates for the structural materials applied in nuclear fusion. SiC fiber-reinforced W composites are also developed for nuclear fusion applications. An effective diffusion barrier is required to prevent reaction between W and SiC. Therefore, in this work, advanced ceramics coatings, such as oxides (ZrO2, TiO2 and Er2O3), nitrides (ZrN and TiN), carbides (TiC and ZrC) were chosen to assess abilities to suppress the reactions. Various films were coated on a CVD (chemical vapor deposition)-SiC plate using the dipping method. Additionally, nitrides coatings prepared by the sputtering method were also investigated in this work. Then evaluations were carried out by joining the coated CVD-SiC plates with W foils. Only the multi-dipped Er2O3 coating and the sputtered nitrides worked well compared with the other coatings. For the other oxide coatings, reactions were identified between oxides and SiC, and for the dipped nitrides and carbides films, cracks were observed on the coating, generated from the coefficient of thermal expansion (CTE) mismatch with the SiC substrate and volume change for the oxides changing to nitrides and carbides. This work provides suggestions about choosing an appropriate interface material between SiC and W. Full article
(This article belongs to the Special Issue Advanced Composites and Coatings for Nuclear Applications)
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9 pages, 4793 KiB  
Article
Development of Liquid Phase Sintering Silicon Carbide Composites for Light Water Reactor
by Tatsuya Hinoki, Fumihisa Kano, Sosuke Kondo, Yoshiyuki Kawaharada, Yumiko Tsuchiya, Moonhee Lee and Hiroyuki Sakai
Coatings 2022, 12(5), 623; https://doi.org/10.3390/coatings12050623 - 3 May 2022
Cited by 3 | Viewed by 1771
Abstract
Silicon carbide composites are expected for light water reactors. The objective is to understand the steam oxidation behavior and the high-temperature water corrosion behavior of the liquid phase sintering silicon carbide and to develop the liquid phase sintering silicon carbide composites, which are [...] Read more.
Silicon carbide composites are expected for light water reactors. The objective is to understand the steam oxidation behavior and the high-temperature water corrosion behavior of the liquid phase sintering silicon carbide and to develop the liquid phase sintering silicon carbide composites, which are stable at the high-temperature water conditions in normal operation and the high-temperature steam conditions in a severe accident. The steam oxidation experiments were carried out at 1200 and 1400 °C. The high-temperature water corrosion experiments were carried out at 320 and 360 °C. The formation of the silicate, which is expected to have excellent resistance to the steam, was confirmed following the steam exposure at 1400 °C. High-temperature water corrosion resistance was improved by the formation of Yttrium Aluminum Garnet at the grain boundary. The particle-dispersion silicon carbide composite tubes with the modified condition were developed, and the thermal shock experiments from 1200 °C to ambient temperature were carried out. The composite tubes showed excellent oxidation and thermal shock resistance. The particle-dispersion liquid phase sintering silicon carbide composites with the modified condition are promising materials for light water reactors. Full article
(This article belongs to the Special Issue Advanced Composites and Coatings for Nuclear Applications)
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15 pages, 7813 KiB  
Article
Influence of Texture and Thickness of Pyrocarbon Coatings as Interphase on the Mechanical Behavior of Specific 2.5D SiC/SiC Composites Reinforced with Hi-Nicalon S Fibers
by Emilien Buet, James Braun and Cédric Sauder
Coatings 2022, 12(5), 573; https://doi.org/10.3390/coatings12050573 - 22 Apr 2022
Cited by 11 | Viewed by 2373
Abstract
In the framework of SiC/SiC composite development for nuclear applications, the influence of pyrocarbon interphase texture and thickness on the mechanical behavior both on as-processed materials and on irradiated materials is a major concern. Thus, the PyC interphase influence has to be clearly [...] Read more.
In the framework of SiC/SiC composite development for nuclear applications, the influence of pyrocarbon interphase texture and thickness on the mechanical behavior both on as-processed materials and on irradiated materials is a major concern. Thus, the PyC interphase influence has to be clearly addressed to define its optimal chemical vapor infiltration processing parameters. For this purpose, specific 2.5D SiC/SiC composites reinforced with Hi-Nicalon S fibers and with two kinds of PyC texture and thickness were produced. Transmission electronic microscopy allowed PyC thickness and microstructure/texture characterizations, whereas push-out and tensile tests were employed as experimental mechanical procedures. The original result is that PyC nature directly influences the interfacial shear stress and failure mode of the weakest interface, regardless of the PyC thickness within the studied range. Adhesive failure or cohesive failure are highlighted depending on the PyC CVI deposition mechanisms. Similar post-irradiation characterizations will be required to assess the role of irradiation on the PyC microstructure/texture evolution and mechanical behavior of these materials. Full article
(This article belongs to the Special Issue Advanced Composites and Coatings for Nuclear Applications)
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