Special Issue "Corrosion and Materials Degradation under Irradiation: From Understanding to Mitigation…"

A special issue of Corrosion and Materials Degradation (ISSN 2624-5558).

Deadline for manuscript submissions: 31 July 2022 | Viewed by 3022

Special Issue Editor

Prof. Dr. Bernard Normand
E-Mail Website
Guest Editor
INSA Lyon, University of Lyon, MATEIS Laboratory, 7 av. Jean Capelle, F-69 621 Villeurbanne Cedex, Lyon, France
Interests: corrosion science; coatings; electrochemistry; tribocorrosion

Special Issue Information

Dear Colleagues,

You are invited to submit papers presenting your scientific and technological contributions concerning one of the biggest materials’ issue for nuclear plant structural integrity assessment and life extension.

Due to its complexity, corrosion is a fascinating scientific discipline. The economic stakes involved are enormous. Each Awareness Corrosion Day on April 24th, proposed by the World Corrosion Organization (WCO), is there to remind us of this. It concerns all areas of human activities. Considering the field of nuclear energy, we must also bear in mind the safety of people and infrastructure. This shows how crucial the involvement of corrosionists in the nuclear industry is. In fact, it has never been more crucial at a time when the energy transition makes it necessary to extend the operating life of power plants until the level of renewable energy necessary for humanity’s better living has been brought into service.

Today, the most operational decarbonized energy on the planet remains nuclear energy, whatever one may say.

Thus, it is natural that a journal such as Corrosion and Degradation of Materials should devote a Special Issue dedicated to highlighting the complexity of understanding, mastering and developing new knowledge in the field of corrosion under irradiation and the means to control it. The specificity of this mode of degradation does not consist in considering a specific corrosion mode only, but in considering a systemic approach which consists in identifying the synergy effects between the different damage factors. It is therefore not a question of characterizing the maintenance of the structural properties of a material or understanding the type of corrosion involved, but of quantifying the aggravating factor that contributes to the outburst of the degradation phenomenon exacerbated by irradiation.

In this Special Issue, the most committed specialists in the field have agreed to share their experience with us by illustrating with their work all the advances on the various points of the subject. Thus, this Special Issue will start with a paper detailing the effect of simultaneous irradiation and corrosion across several material/coolant systems proposed by Gary Was et al. (University of Michigan-USA). Damien Féron et al. (CEA-France) will develop the effects of irradiation on changes in solution chemistry, linked to the effects of radiolysis (to be confirmed). Digby D. Macdonald et al. (University of California-USA) will prolong the presentation of the effect of radiolysis on the passivity. Tetsuo Shoji et al. (Tohoku University-Japan) will consider the role of hydrogen on the oxidation of metal. Passive materials are widely used in the nuclear field; however, the behaviour of steels under gamma-ray irradiation in the nuclear field should not be underestimated. This topic will be discussed by Yutaka Watanabe et al. (Tohoku University-Japan). Beyond the work to understand the mechanisms of damage under irradiation, Tom Devine et al. (University of California-USA) will present their original work on how to inhibit the incorporation of irradiation product into passive film by adding aqueous zinc ions to PWR water. Because considering irradiation corrosion studies without addressing the issue of waste management would make this Special Issue an unfinished job, Fraser King et al. (Integrity Corrosion Consulting Ltd.-Canada) will develop the issue of radiation effects on nuclear waste canister materials.

You are invited to complete the list of these subjects. Many topics also have to be developed in term of methodology, ballistic effect of irradiations, IASCC, strategy of prevention or monitoring, etc. Thank you for letting us discover your recent work.

Prof. Dr. Bernard Normand
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. Corrosion and Materials Degradation is an international peer-reviewed open access quarterly 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 1000 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.

Published Papers (2 papers)

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Research

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Article
Baseline Examinations and Autoclave Tests of 65 and 100 dpa Flux Thimble Tube O-Ring Specimens
Corros. Mater. Degrad. 2021, 2(2), 248-273; https://doi.org/10.3390/cmd2020014 - 25 May 2021
Cited by 1 | Viewed by 1182
Abstract
This paper describes the methods and results of analytical TEM examinations and autoclave testing of two highly-irradiated flux thimble tube materials harvested from a commercial pressurized water reactor. The materials are cold-worked 316L, and accumulated 65 dpa and 100 dpa of radiation dose. [...] Read more.
This paper describes the methods and results of analytical TEM examinations and autoclave testing of two highly-irradiated flux thimble tube materials harvested from a commercial pressurized water reactor. The materials are cold-worked 316L, and accumulated 65 dpa and 100 dpa of radiation dose. To set the baseline for a broader study, the materials were examined in the as-irradiated condition and tested as O-ring specimens at relatively high constant loads in simulated PWR water conditions. Tests were also conducted with elevated hydrogen. For a given load, more rapid cracking was associated with higher radiation dose, and with the elevated hydrogen. Full article
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Review

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Review
A Review of the Effect of Irradiation on the Corrosion of Copper-Coated Used Fuel Containers
Corros. Mater. Degrad. 2021, 2(4), 678-707; https://doi.org/10.3390/cmd2040037 - 17 Nov 2021
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Abstract
Radiation induced corrosion is one of the possible modes of materials degradation in the concept of long-term management of used nuclear fuel. Depending on the environmental conditions surrounding the used fuel container, a range of radiolysis products are expected to form that could [...] Read more.
Radiation induced corrosion is one of the possible modes of materials degradation in the concept of long-term management of used nuclear fuel. Depending on the environmental conditions surrounding the used fuel container, a range of radiolysis products are expected to form that could impact the corrosion of the copper coating. For instance, γ-radiolysis of pure water produces molecular oxidants such as H2O2 and the radiolysis of humid air produces compounds such as NOx and HNO3. This review is confined to a discussion of the effect of γ-radiation on the corrosion of copper-coated containers. A simplified mixed-potential model is also presented to calculate the extent of copper corrosion by using the steady-state concentration of H2O2 generated during the first 300 years of emplacement, when the radiation field is significant. Full article
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Planned Papers

The below list represents only planned manuscripts. Some of these manuscripts have not been received by the Editorial Office yet. Papers submitted to MDPI journals are subject to peer-review.


 


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