An approach to combine neutron and ion irradiation data to accelerate material qualification for nuclear reactors

Stephen Taller, Yiren Chen, Rongjie Song, Wei Ying Chen, Andrea Jokisaari

Research output: Contribution to journalReview articlepeer-review

1 Scopus citations

Abstract

Next-generation nuclear power plants are generally characterized by higher operating temperatures, increased neutron fluences and energies, and distinct corrosive coolant environments versus the existing light water reactor fleet. Whether using existing materials in new environments, newly developed materials tailored for these environments, or new manufacturing methods, the traditional decades-long approach for materials qualification does not facilitate rapid deployment. Ion irradiation has demonstrated success in reproducing material microstructure and select property evolution resulting from neutron irradiation with three to four orders of magnitude reduction in time and cost, making it an ideal candidate for accelerated irradiation testing. Because microstructure has a large impact on bulk material properties, limited neutron irradiation data at lower damage levels can in principle be combined with accelerated ion testing results and modeling and simulation to form an accurate prediction of microstructure evolution and select properties under different neutron irradiation conditions and at higher damage levels. The objective of this work is to present a conceptual framework of specific steps to fulfill several technical challenges associated with qualifying materials for performance in radiation environments on an accelerated time frame. A brief review of the regulatory landscape for materials in nuclear environments is presented, followed by additional overviews to understand the current state of the art for correlation of materials properties across radiation environments using experimental and computational methodologies. Finally, the roles of academia, national laboratories, and industry in the advancement of this accelerated materials qualification framework are discussed as a path forward, with possible case studies presented.

Original languageEnglish
Article number155385
JournalJournal of Nuclear Materials
Volume603
DOIs
StatePublished - Jan 2025

Funding

This manuscript has been authored by UT-Battelle, LLC, under contract DE-AC05-00OR22725, UChicago Argonne LLC under contract DE-AC02-06CH11357, and Battelle Energy Alliance LLC under contract DE-AC07-05ID14517 with the US Department of Energy (DOE). The US government retains and the publisher, by accepting the article for publication, acknowledges that the US government retains a nonexclusive, paid-up, irrevocable, worldwide license to publish or reproduce the published form of this manuscript, or allow others to do so, for US government purposes. DOE will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (https://www.energy.gov/doe-public-access-plan). This research was supported by the Transformational Challenge Reactor and Advanced Materials and Manufacturing Technologies programs supported by the DOE NE. The authors would like to express their sincere gratitude to Professor Gary S. Was at the University of Michigan for his invaluable technical discussions and input. We also extend our appreciation to Rob Tregoning, Eric Focht, Christopher Ulmer, Dan Widrevitz, and others within the NRC Office of Nuclear Regulatory Research and Office of Nuclear Reactor Regulation for their continued engagement, detailed explanations, and vital insights.

FundersFunder number
U.S. Department of Energy
Office of Nuclear Energy
UChicago Argonne LLCDE-AC02-06CH11357
Battelle Energy Alliance LLCDE-AC07-05ID14517

    Keywords

    • Ion irradiation
    • Materials
    • Materials qualification
    • Neutron irradiation
    • Radiation damage

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