Author
Francis A. Garner
Other affiliations: Pacific Northwest National Laboratory, National Research Nuclear University MEPhI
Bio: Francis A. Garner is an academic researcher from Texas A&M University. The author has contributed to research in topics: Swelling & Irradiation. The author has an hindex of 35, co-authored 218 publications receiving 4677 citations. Previous affiliations of Francis A. Garner include Pacific Northwest National Laboratory & National Research Nuclear University MEPhI.
Topics: Swelling, Irradiation, Creep, Helium, Microstructure
Papers published on a yearly basis
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TL;DR: In this article, it was shown that the steady-state swelling rate of bcc steels is inherently much lower than that of fcc and that the creep compliance of the two types of alloys also differs only by a factor of about two.
455 citations
TL;DR: In this article, the crystal structures of MgAl 2 O 4 spinel single crystals irradiated to high neutron fluences (> 5 x 10 26 n/m 2 (E n > 0.1 MeV)), were examined by neutron diffraction.
154 citations
TL;DR: In this article, a cold worked 316SS baffle bolt was extracted from the Tihange pressurized water reactor and sectioned at three different positions, and microstructural characterization revealed that small faulted dislocation loops and cavities were visible at each position.
141 citations
TL;DR: In this article, the effect of irradiation on the tensile and fracture toughness properties of candidate tritium materials, 316L and 304L stainless steel (annealed), modified (Mod) 9Cr-1Mo steel, and Alloy 718 (precipitation hardened), was measured on various materials irradiated at the Los Alamos Neutron Science Center accelerator.
115 citations
TL;DR: In this paper, the influence of void swelling on the depth-dependent defect imbalance between vacancies and interstitials has been investigated using the Boltzmann transport equation (BTE) method, and it was shown that void swelling does not depend solely on the local dose level.
101 citations
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TL;DR: In this article, the three major materials challenges for the current and next generation of water-cooled fission reactors are centered on two structural materials aging degradation issues (corrosion and stress corrosion cracking of structural materials and neutron-induced embrittlement of reactor pressure vessels), along with improved fuel system reliability and accident tolerance issues.
1,633 citations
TL;DR: In this paper, an emerging class of nanostructured ferritic alloys (NFAs) have been proposed for high-performance structural alloys with outstanding properties that are sustained under long-term service in ultrasevere environments.
Abstract: Advanced fission and future fusion energy will require new high-performance structural alloys with outstanding properties that are sustained under long-term service in ultrasevere environments, including neutron damage producing up to 200 atomic displacements per atom and, for fusion, 2000 appm of He. Following a brief description of irradiation damage and damage resistance, we focus on an emerging class of nanostructured ferritic alloys (NFAs) that show promise for meeting these challenges. NFAs contain an ultrahigh density of Y-Ti-O-enriched dispersion-strengthening nanofeatures (NFs) that, along with fine grains and high dislocation densities, provide remarkably high tensile, creep, and fatigue strength. The NFs are stable under irradiation up to 800°C and trap He in fine-scale bubbles, suppressing void swelling and fast fracture embrittlement at lower temperatures and creep rupture embrittlement at high temperatures. The current state of the development and understanding of NFAs is described, along wi...
1,021 citations
TL;DR: Preliminary radiation damage experiments substantiate the prediction that fluorites are inherently more radiation resistant than pyrochlores, and may permit the chemical durability and radiation tolerance of potential hosts for actinides and radioactive wastes to be tailored.
Abstract: The radiation performance of a variety of complex oxides is predicted on the basis of a material's propensity to accommodate lattice point defects. The calculations indicate that a particular class of oxides possessing the fluorite crystal structure should accept radiation-induced defects into their lattices far more readily than a structurally similar class of oxides based on the pyrochlore crystal structure. Preliminary radiation damage experiments substantiate the prediction that fluorites are inherently more radiation resistant than pyrochlores. These results may permit the chemical durability and radiation tolerance of potential hosts for actinides and radioactive wastes to be tailored.
847 citations
TL;DR: In this article, a strategy for designing high-performance radiation-resistant materials is based on the introduction of a high, uniform density of nanoscale particles that simultaneously provide good high temperature strength and neutron radiation damage resistance.
844 citations
Pacific Northwest National Laboratory1, University of Michigan2, Royal Institution3, Lawrence Livermore National Laboratory4, Massachusetts Institute of Technology5, Kyushu University6, Institute for Transuranium Elements7, Pennsylvania State University8, Los Alamos National Laboratory9, University of Cambridge10, Australian Nuclear Science and Technology Organisation11, Oak Ridge National Laboratory12
TL;DR: A comprehensive review of the state-of-the-art of radiation effects in crystalline ceramics that may be used for the immobilization of high-level nuclear waste and plutonium is provided in this article.
Abstract: This review provides a comprehensive evaluation of the state-of-knowledge of radiation effects in crystalline ceramics that may be used for the immobilization of high-level nuclear waste and plutonium. The current understanding of radiation damage processes, defect generation, microstructure development, theoretical methods, and experimental methods are reviewed. Fundamental scientific and technological issues that offer opportunities for research are identified. The most important issue is the need for an understanding of the radiation-induced structural changes at the atomic, microscopic, and macroscopic levels, and the effect of these changes on the release rates of radionuclides during corrosion.
834 citations