Mechanical Behavior of Reactor Structural Materials

A special issue of Metals (ISSN 2075-4701).

Deadline for manuscript submissions: closed (31 March 2023) | Viewed by 5224

Special Issue Editors


E-Mail Website
Guest Editor
Idaho National Laboratory, Idaho Falls, ID 83402, USA
Interests: mechanical behavior; radiation effects; electron microscopy

E-Mail Website
Guest Editor
Idaho National Laboratory, Idaho Falls, ID 83402, USA
Interests: microscopy; mechanical properties; irradiation damage

Special Issue Information

The world faces a critical challenge in terms of meeting the ever-increasing global energy demand for economic prosperity. Meanwhile, we must mitigate the effects of climate change by increasing the share of clean energy production. Thus, nuclear energy has become an essential option for producing carbon-free energy with a potential capacity to ensure global energy security. To produce sustainable, economical, safe, and proliferation-resistant nuclear energy, the life-time extension of current reactor fleets and successful design and deployment of advanced nuclear reactor systems are critical. To this end, we need to identify and develop structural materials that can withstand harsh conditions in the reactor core, such as stress, high temperature, corrosion medium, and radiation. In contrast to present-generation light water reactors (LWR), advanced reactors operate at much higher temperatures (500–1000 °C), produce heavier irradiation damage on materials (up to 200 displacements per atom, dpa), and have extreme corrosive environments. Such conditions alter the physical and chemical characteristics of materials that deteriorate their performance, leading to unwarranted reactor shutdowns, low efficiency, and safety issues. Among the various material selection and design criteria for reactor structural materials, their mechanical behavior under harsh conditions stands out as a critical factor that can affect the integrity of reactor structural components. The rector structural materials are subjected to a combination of embrittlement, fatigue, creep, and stress corrosion cracking degradation modes aggravated by severe radiation damage. This Special Issue aims to disseminate research articles focusing on the latest developments in the mechanical behavior of the reactor structural materials field.

Dr. Boopathy Kombaiah
Dr. Colin Judge
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. Metals 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

  • irradiation
  • mechanical behavior
  • deformation mechanisms
  • reactor structural materials
  • microstructure

Benefits of Publishing in a Special Issue

  • Ease of navigation: Grouping papers by topic helps scholars navigate broad scope journals more efficiently.
  • Greater discoverability: Special Issues support the reach and impact of scientific research. Articles in Special Issues are more discoverable and cited more frequently.
  • Expansion of research network: Special Issues facilitate connections among authors, fostering scientific collaborations.
  • External promotion: Articles in Special Issues are often promoted through the journal's social media, increasing their visibility.
  • e-Book format: Special Issues with more than 10 articles can be published as dedicated e-books, ensuring wide and rapid dissemination.

Further information on MDPI's Special Issue polices can be found here.

Published Papers (2 papers)

Order results
Result details
Select all
Export citation of selected articles as:

Research

14 pages, 3773 KiB  
Article
Micropillar Compression of Additively Manufactured 316L Stainless Steels after 2 MeV Proton Irradiation: A Comparison Study between Planar and Cross-Sectional Micropillars
by Ching-Heng Shiau, Miguel Pena, Yongchang Li, Sisi Xiang, Cheng Sun, Michael D. McMurtrey and Lin Shao
Metals 2022, 12(11), 1843; https://doi.org/10.3390/met12111843 - 28 Oct 2022
Cited by 2 | Viewed by 1795
Abstract
A micropillar compression study with two different techniques was performed on proton-irradiated additively manufactured (AM) 316L stainless steels. The sample was irradiated at 360 °C using 2 MeV protons to 1.8 average displacement per atom (dpa) in the near-surface region. A comparison study [...] Read more.
A micropillar compression study with two different techniques was performed on proton-irradiated additively manufactured (AM) 316L stainless steels. The sample was irradiated at 360 °C using 2 MeV protons to 1.8 average displacement per atom (dpa) in the near-surface region. A comparison study with mechanical test and microstructure characterization was made between planar and cross-sectional pillars prepared from the irradiated surface. While a 2 MeV proton irradiation creates a relatively flat damage zone up to 12 µm, the dpa gradient by a factor of 2 leads to significant dpa uncertainty along the pillar height direction for the conventional planar technique. Cross-sectional pillars can significantly reduce such dpa uncertainty. From one single sample, three cross-sectional pillars were able to show dpa-dependent hardening. Furthermore, post-compression transmission electron microscopy allows the determination of the deformation mechanism of individual micropillars. Cross-sectional micropillar compression can be used to study radiation-induced mechanical property changes with better resolution and less data fluctuation. Full article
(This article belongs to the Special Issue Mechanical Behavior of Reactor Structural Materials)
Show Figures

Figure 1

36 pages, 5909 KiB  
Article
Swelling and He-Embrittlement of Austenitic Stainless Steels and Ni-Alloys in Nuclear Reactors
by Malcolm Griffiths, Steven Xu and Juan Eduardo Ramos Nervi
Metals 2022, 12(10), 1692; https://doi.org/10.3390/met12101692 - 10 Oct 2022
Cited by 4 | Viewed by 2811
Abstract
Rate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical properties and the dimensional stability. He-stabilised cavity accumulation [...] Read more.
Rate theory models have been developed for the swelling and He-embrittlement of austenitic stainless steels and Ni-alloys in nuclear reactors. The models illustrate how microstructure evolution during irradiation affects the rate of change of mechanical properties and the dimensional stability. He-stabilised cavity accumulation on grain boundaries, which causes brittle failure at low stresses and strains known as He-embrittlement, is shown to be strongly dependent on the irradiation temperature and the rate of production of Frenkel pairs and He atoms. The results show that the accumulation of cavities on grain boundaries falls into two regimes: (i) that dictated by matrix bubble swelling at low temperatures; and (ii) that dictated by matrix void swelling at high temperatures. Full article
(This article belongs to the Special Issue Mechanical Behavior of Reactor Structural Materials)
Show Figures

Figure 1

Back to TopTop