Design of Radiation Tolerant Nanostructured Metallic Multilayers-Reference-Cited by-同舟云学术

Design of Radiation Tolerant Nanostructured Metallic Multilayers

Published:2012-08-24 Issue:4 Volume:134 Page:
ISSN:0094-4289
Container-title:Journal of Engineering Materials and Technology
language:en
Short-container-title:

Author:

Zhang X.¹,Fu E. G.,Li Nan,Misra A.,Wang Y.-Q.²,Shao L.³,Wang H.⁴

Affiliation:

1. Department of Mechanical Engineering, Materials Science and Engineering Program, Texas A&M University, College Station, TX 77843-3123 e-mail:

2. Materials Physics and Application Division, Los Alamos National Laboratory, Los Alamos, NM 87545

3. Department of Nuclear Engineering, Texas A&M University, College Station, TX 77843-3128

4. Department of Electrical Engineering, Texas A&M University, College Station, TX 77843-3128

Abstract

We review He ion induced radiation damage in several metallic multilayer systems, including Cu/V, Cu/Mo, Fe/W, and Al/Nb up to a peak dose of several displacements per atom (dpa). Size dependent radiation damage is observed in all systems. Nanolayer composites can store a very high concentration of He. Layer interfaces promote the recombination of opposite type of point defects and hence reduce the accumulative defect density, swelling, and lattice distortion. Interfaces also alleviate radiation hardening substantially. The chemical stability of interfaces is an important issue when considering the design of radiation tolerant nanolayer composites. Immiscible and certain miscible systems possess superior stability against He ion irradiation. Challenge and future directions are briefly discussed.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science

Link

http://asmedigitalcollection.asme.org/materialstechnology/article-pdf/doi/10.1115/1.4006979/6133736/041010_1.pdf

Reference71 articles.

1. Microstructure of Neutron-Irradiated Iron Before and After Tensile Deformation;J. Nucl. Mater.,2006

2. Deformation Microstructure of Neutron-Irradiated Pure Polycrystalline Metals;J. Nucl. Mater.,2004

3. Defect Accumulation in fcc and bcc Metals and Alloys Under Cascade Damage Conditions—Towards a Generalisation of the Production Bias Model;J. Nucl. Mater.,2000

4. Simulation of Damage Production and Accumulation in Vanadium;J. Nucl. Mater.,2000

5. Significant Differences in Defect Accumulation Behaviour Between fcc and bcc Crystals Under Cascade Damage Conditions;J. Nucl. Mater.,1995

Cited by 56 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Enhanced Multifaceted Properties of Nanoscale Metallic Multilayer Composites;Materials;2024-08-12

2. Effect of non-clustering element C and Mo on irradiation-induced clustering in reactor pressure vessel steels;Acta Materialia;2024-05

3. Extraordinary radiation tolerance of a Ni nanocrystal-decorated carbon nanotube network encapsulated in amorphous carbon;Journal of Materials Science & Technology;2023-08

4. Recent Progress on Interfaces in Nanomaterials for Nuclear Radiation Resistance;ChemNanoMat;2022-12-09

5. Deformation mechanisms in crystalline-amorphous high-entropy composite multilayers;Materials Science and Engineering: A;2022-07