Results 11 to 20 of about 324 (179)

Effects of Zr on high temperature deformation and dynamic precipitation of laves phase in Fe–13Cr–5Al–2Mo–0.5Nb–0.4Ta alloy

Results in Physics, 2021
High temperature deformation of Fe–13.5Cr–4.7Al–2.0Mo–0.70Nb–0.40Ta (FeCrAl) and Fe–13.5Cr–4.7Al–2.0Mo–0.45Nb–0.4Ta–0.11Zr (FeCrAl–Zr) alloys was performed at temperatures of 800–1100 °C with the strain rates of 0.01–10 s−1, and the constitutive model ...
Wenbo Liu, Zhe Liu, Huiqun Liu, Qing Wang, Ruiqian Zhang   +4 more
doaj   +1 more source

Effect of trace Y on mechanical and oxidation properties of FeCrAl alloy cladding

He jishu, 2023
BackgroundFeCrAl alloy cladding, as an accident tolerant fuel (ATF) mid-term commercial technology approach, has received extensive attention.PurposeThis study aims to investigate the effect of trace Y on the internal pressure burst and oxidation ...
LIU Yang, MA Haibin, WU Lixiang, GUO Daxi, YAN Jun, YANG Rongkun, REN Qisen, XUE Jiaxiang   +7 more
doaj   +1 more source

Shielded magnetic small-angle neutron scattering for characterization of radioactive samples. [PDF]

J Appl Crystallogr
The study presents a novel shielded magnetic small‐angle neutron scattering (SM‐SANS) technique using lead shielding to facilitate the nanoscale characterization of clustering and precipitation in highly radioactive nuclear materials. By comparing the results with atom probe tomography, the research demonstrates that SM‐SANS effectively quantifies ...
Field KG, Massey CP, Smith KR, Briggs SA, Zhang D, Littrell KC.   +5 more
europepmc   +2 more sources

Data-driven predictive modeling of FeCrAl oxidation

Materials Letters: X, 2023
FeCrAl alloys are among the most promising candidates for accident-tolerant fuel cladding material in light water nuclear reactors. Despite their high-temperature oxidation resistance in corrosive environments coupled with their hydrothermal corrosion ...
Indranil Roy, Subhrajit Roychowdhury, Bojun Feng, Sandipp Krishnan Ravi, Sayan Ghosh, Rajnikant Umretiya, Raul B. Rebak, Daniel M. Ruscitto, Vipul Gupta, Andrew Hoffman   +9 more
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On the delamination of FeCrAl ODS alloys [PDF]

Materials Science and Engineering: A, 2009
The authors acknowledge financial support from the Spanish Ministerio de Educación y Ciencia in the form of a Coordinated Project in the Energy Area of Plan Nacional 2006 (ENE2006-15170- C02). Moreover, one of the authors (J. Ch) gratefully acknowledges the contribution of Ms. C. Pe˜na for her help with the fractographic work.
Chao, Jesús, Capdevila, Carlos, González-Carrasco, José Luis   +2 more
openaire   +2 more sources

Ion Irradiation Defects and Hardening in FeCrAl Alloy

Metals, 2022
The self-ion irradiation experiments of FeCrAl and Y−FeCrAl alloys are carried out at 330 °C to 1–10 displacements per atom (dpa). The formation of dislocation loops in these alloys is investigated by transmission electron microscopy (TEM) and nano-indentation tests are used to assess the irradiation hardening.
Fang Li, Yunxiang Long, Daxi Guo, Liping Guo, Wenbin Lin, Yiheng Chen, Lei Li, Qisen Ren, Yehong Liao   +8 more
openaire   +2 more sources

Outstanding 1200 °C Oxidation Resistance in a Novel Multi-Principal Element Alloy via Lattice Distortion-Induced Diffusion Suppression. [PDF]

Adv Sci (Weinh)
The unique lamellar structure of the eutectic alloy promotes selective oxidation of Al initially, while lattice distortion‐induced diffusion suppression slows oxide growth during steady state. Combining these strategies, a Multi‐Principal Element Alloy with excellent oxidation resistance at 1200℃ was designed.
Zhang X, Lv W, Wang X, Jia C, Zhou Y, Qiu K, Wang J.   +6 more
europepmc   +2 more sources

Microstructure dependent burst behavior of oxide dispersion–strengthened FeCrAl cladding

Materials & Design, 2023
Oxide dispersion–strengthened (ODS) FeCrAl alloys are an advanced cladding material that combines the high-temperature steam oxidation resistance of conventional wrought FeCrAl with the irradiation resistance and high-temperature strength of ...
Caleb P. Massey, Kenneth A. Kane, Ryan T. Sweet, Samuel B. Bell, Sebastien N. Dryepondt, James Burns, Andrew T. Nelson   +6 more
doaj   +1 more source

Effect of Cr and Al on Elastic Constants of FeCrAl Alloys Investigated by Molecular Dynamics Method

Metals, 2022
The FeCrAl alloy system is recognized as one of the candidate materials for accident-tolerant fuel (ATF) cladding in the nuclear power industry due to its high oxidation resistance under irradiation and high-temperature environments.
Hui Dai, Miaosen Yu, Yibin Dong, Wahyu Setyawan, Ning Gao, Xuelin Wang   +5 more
doaj   +1 more source

Preparation and Properties Study of Cr on FeCrAl Cladding Materials

Frontiers in Materials, 2021
FeCrAl alloy is a promising candidate material for the fourth-generation reactor core cladding material. Adjustment of the Cr content is one of the effective ways to obtain enhanced performance for the FeCrAl alloy. In this work, Fe–xCr–6Al alloy (11 ≤ x
Peng Wang, Yingjie Qiao, Wen Qi, Shiyu Du, Shiyu Du, Zhen Liu, Zhen Liu, Fanping Meng, Xiaohong Zhang, Kun Wang, Qiuwu Li, Zhaoding Yao, Chengying Bai, XiaoDong Wang   +13 more
doaj   +1 more source