Radiation Damage in Metallic Nuclear Reactor Materials

A special issue of Metals (ISSN 2075-4701). This special issue belongs to the section "Structural Integrity of Metals".

Deadline for manuscript submissions: closed (30 April 2024) | Viewed by 694

Special Issue Editors


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Guest Editor
Applied Ion Beam Physics Laboratory, Institute of Modern Physics, Fudan University, Shanghai 200433, China
Interests: irradiation damage; cluster dynamics; helium bubble

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Guest Editor
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
Interests: irradiation damage; defects characterization; nanoindentation

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Guest Editor
State Key Laboratory of Nuclear Physics and Technology, Department of Technical Physics, School of Physics, Peking University, Beijing 100871, China
Interests: nuclear materials; radiation damage; TEM

Special Issue Information

Dear Colleagues,

Metallic nuclear reactor materials are critical for containment of nuclear fuel and fission products, as well as reliable and thermodynamically efficient production of electrical energy from nuclear reactors. In reactors, high fluxes of high-energy neutrons severely damage properties of these metallic materials by producing numerous irradiation defects in materials, leading to degradations of material properties like element segregation, void swelling, hardening and embrittlement of irradiated materials. Irradiation damage in metallic nuclear reactor materials has been identified as one of the serious issues challenging the stable and safe operation of nuclear reactors. Understanding the damage behaviors of metallic nuclear reactor materials and unveiling the underlying damage mechanisms are key to evaluating the performance of metallic materials currently serving in various nuclear reactors. This understanding is also beneficial for development of new-generation irradiation- tolerant nuclear reactor materials.

In this Special Issue, emphasize will be placed on formation and evolution mechanisms of various types of irradiation-induced defects, as well as the relationship between defects evolution and property alternations of irradiated metallic materials. Advanced techniques for characterizing irradiation defects, new theoretical methodologies for evaluating defect energetics and models simulating defects evolutions will also be covered. Review works related with current status and developments in understanding of irradiation damage in metallic materials serving in various types of reactors are welcome.

This Special Issue of Metals provide a communication and discussion platform covering a broad range of up-to-date findings and progress related to various aspects of irradiation damage in Metallic nuclear reactor materials. We are look forward to receiving your contributions.

Dr. Jie Gao
Dr. Zhenbo Zhu
Dr. Jinlong Du
Guest Editors

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Keywords

  • irradiation damage
  • metallic material
  • property degradation
  • defect characterization
  • theoretical simulation

Published Papers (1 paper)

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Research

16 pages, 2471 KiB  
Article
Investigation of Irradiation Hardening and Effectiveness of Post-Irradiation Annealing on the Recovery of Tensile Properties of VVER-1000 Realistic Welds Irradiated in the LYRA-10 Experiment
by Mathilde Laot, Viviam Marques Pereira, Theo Bakker, Elio d’Agata, Oliver Martin and Murthy Kolluri
Metals 2024, 14(8), 887; https://doi.org/10.3390/met14080887 (registering DOI) - 3 Aug 2024
Viewed by 325
Abstract
Assessing the embrittlement and hardening of reactor pressure vessel steels is critical for the extension of the service lifetime of nuclear power plants. This paper summarises the tensile test results on the irradiation behaviour of realistic VVER-1000 welds from the STRUMAT-LTO project. The [...] Read more.
Assessing the embrittlement and hardening of reactor pressure vessel steels is critical for the extension of the service lifetime of nuclear power plants. This paper summarises the tensile test results on the irradiation behaviour of realistic VVER-1000 welds from the STRUMAT-LTO project. The welds were irradiated at the HFR (Petten, the Netherlands) to a fluence of up to 1.087 × 1020 n·cm−2, and their irradiation hardening was studied by means of tensile testing. The four grades, with different Mn and Ni contents, show different hardening behaviours. The highest degree of irradiation hardening is observed for the weld that has the highest combined Ni + Mn content. The results show that there is a synergetic effect of Mn and Ni on the irradiation hardening behaviour of the VVER-1000 welds. Besides irradiation hardening, the effectiveness of post-irradiation annealing treatments on the recovery of the tensile properties is studied in the present work. Post-irradiation annealing treatments conducted at 418 °C and at 475 °C proved to be effective for three of the four investigated welds. For the realistic weld with the highest combined Ni + Mn, only the annealing at 475 °C led to the complete recovery of the tensile properties. Full article
(This article belongs to the Special Issue Radiation Damage in Metallic Nuclear Reactor Materials)
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