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CORC

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Diffusion and oxidation behavior of Cr-ZrN coated Zr alloy accident tolerant fuel cladding materials at high temperature 期刊论文
Surface and Coatings Technology, 2023, 期号: 1, 页码: 130246
作者:  Diffusion and oxidation behavior of Cr-ZrN coated Zr alloy accident tolerant fuel cladding materials at high temperature;  Yining Ding;  Fen Zhao;  Panpan Sun;  Lunlin Shang
收藏  |  浏览/下载：0/0  |  提交时间：2024/01/04
Effects of Nb addition and heat treatment on the microstructure, mechanical property and internal friction behavior of FeCrAlMo cladding alloys 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2022, 卷号: 572
作者:  Wang, H.;  Gao, Y. X.;  Sun, M.
收藏  |  浏览/下载：60/0  |  提交时间：2022/12/23
Preliminary Multi-Physics Performance Analysis and Design Evaluation of UO2 Fuel for LBE-Cooled Subcritical Reactor of China Initiative Accelerator Driven System 期刊论文
FRONTIERS IN ENERGY RESEARCH, 2021, 卷号: 9, 页码: 17
作者:  Wang, Guan;  Gu, Long;  Yun, Di
收藏  |  浏览/下载：17/0  |  提交时间：2021/12/13
Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding 期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 卷号: 84, 页码: 230-238
作者:  Zhang, Zijian;  Han, En-Hou;  Xiang, Chao
收藏  |  浏览/下载：42/0  |  提交时间：2021/10/15
In situ transmission electron microscopy study and molecular dynamics simulation of dislocation loop evolution in FeCrAl alloys under Fe+ irradiation 期刊论文
MATERIALS TODAY ENERGY, 2021, 卷号: 21, 页码: 12
作者:  Li, Y. P.;  Yu, M. S.;  Ran, G.;  Gao, N.;  Chen, Y.
收藏  |  浏览/下载：14/0  |  提交时间：2021/12/08
Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program 期刊论文
FRONTIERS IN ENERGY RESEARCH, 2021, 卷号: 9, 页码: 9
作者:  Yuan, He;  Wang, Guan;  Yu, Rui;  Tao, Yujie;  Wang, Zhaohao
收藏  |  浏览/下载：15/0  |  提交时间：2021/12/08
Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings 期刊论文
ANNALS OF NUCLEAR ENERGY, 2021, 卷号: 156, 页码: 9
作者:  Song Ligang;  Huang Bo;  Li JH(李江华);  Ma Xianfeng;  Liu Min
收藏  |  浏览/下载：100/0  |  提交时间：2021/05/17
Strengthening mechanism of Nb addition in Fe-13Cr-4.5Al-2Mo alloys assessed by internal friction measurement 期刊论文
Journal of Nuclear Materials, 2020, 卷号: 542
作者:  H. Wang;  Y.X. Gao;  M. Sun;  H.Y. Yang;  G. Li
收藏  |  浏览/下载：46/0  |  提交时间：2020/10/27
Defective structures in FeCrAl alloys from first principles calculations 期刊论文
JAPANESE JOURNAL OF APPLIED PHYSICS, 2020, 卷号: 59, 期号: 4
作者:  Shi, Diwei;  Song, Jiexi;  Liu, Zhen;  Li, Hanchao;  Bu, Moran
收藏  |  浏览/下载：68/0  |  提交时间：2020/12/16
Feasibility of an innovative long-life molten chloride-cooled reactor 期刊论文
NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 4, 页码: -
作者:  Lin, M;  Cheng, MS;  Dai, ZM
收藏  |  浏览/下载：6/0  |  提交时间：2021/09/06
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