@article{ebea0e2013fc4c53b0c4ce638fefabf2,
title = "The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: Bcc Nb particles and nanometric Nb clusters embedded in hcp Zr",
abstract = "A potential factor dominating the obstacle strength of second phase precipitate particles in dispersion strengthening is the crystallographic mismatch between the matrix phase and the second phase; however, yet this concept has not been fully assessed by experiments and simulations. In the present study, we experimentally investigated the obstacle strength of body centered cubic (bcc) Nb particles and nanometric Nb clusters embedded in hexagonal close packed (hcp) Zr matrix. The bcc Nb is softer than the hcp Zr in terms of shear modulus, whereas from a crystallographic viewpoint, the bcc Nb particles can be nonshearable, strong obstacles because the slip plane inside the particles is not parallel with that in the matrix. Although the bcc Nb is thermodynamically the stable configuration for Nb atoms precipitating from the Zr matrix, in the very early stage of solute agglomeration, the crystal structure of Nb nanoclusters is possibly hcp rather than bcc. The obstacle strength (α) was no greater than 0.5 for the Nb nanoclusters, whereas 0.85 ≤ α ≤ 1 for the coarse bcc Nb particles; α = 1 was obtained with the Taylor factor (M) of 5.5 and α = 0.85 with M = 6.5, respectively. These results indicate that the bcc Nb particles are strong obstacles, and that the Nb nanoclusters are weak obstacles.",
keywords = "Atom probe tomography, Fuel cladding, Irradiation, Nanoindentation, Precipitation hardening, Zirconium alloys",
author = "Y. Matsukawa and Yang, {H. L.} and K. Saito and Y. Murakami and T. Maruyama and T. Iwai and K. Murakami and Y. Shinohara and T. Kido and T. Toyama and Z. Zhao and Li, {Y. F.} and S. Kano and Y. Satoh and Y. Nagai and H. Abe",
note = "Funding Information: We are grateful to Mitsubishi Nuclear Fuel Co. Ltd. for supplying fuel cladding tube. This study was partly sponsored by the Ministry of Education, Culture, Sports, Science & Technology (MEXT) of JAPAN, under the Strategic Promotion Program for Basic Nuclear Research entitled “Study on hydrogenation and radiation effects in advanced nuclear fuel cladding materials” and a program entitled “R&D of nuclear fuel cladding materials and their environmental degradations for the development of safety standards” entrusted to Tohoku University by the MEXT. This study was carried out partly under the Cooperative Research Program of the Oarai Center of the Institute for Materials Research, Tohoku University. We are grateful to Dr. Masahiko Hatakeyama and Ms. Yasuko Nozawa for instrumental support. Y. Nagai was partly supported by the MEXT Grant-in-Aid for Scientific Research (A) ( 21246142 ) and also by the funding for Nuclear Research available through screening and counseling by the Atomic Energy Commission of Japan. Y. Matsukawa was supported by the MEXT Grant-in-Aid for Young Scientists (A) ( 22686058 ) and by the 23rd Research Promotion Grant of the Iron & Steel Institute of Japan (ISIJ). Publisher Copyright: {\textcopyright} 2015 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.",
year = "2016",
month = jan,
day = "1",
doi = "10.1016/j.actamat.2015.09.038",
language = "English",
volume = "102",
pages = "323--332",
journal = "Acta Materialia",
issn = "1359-6454",
publisher = "Elsevier Limited",
}