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浏览/检索结果: 共332条，第1-10条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择提交时间升序提交时间降序发表日期升序发表日期降序题名升序题名降序作者升序作者降序 Diffusion and oxidation behavior of Cr-ZrN coated Zr alloy accident tolerant fuel cladding materials at high temperature 期刊论文  OAI收割 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：4/0  |  提交时间：2024/01/04 Effects of Zn injection on corrosion behavior and crud deposition of FeCrAl fuel cladding under subcooled nuclear boiling condition in high-temperature pressurized water 期刊论文  OAI收割 CORROSION SCIENCE, 2023, 卷号: 211, 页码: 16 作者:  Xue, Chaochao;  Zhang, Ziyu;  Tan, Jibo;  Wu, Xinqiang;  Han, En-Hou   |  收藏  |  浏览/下载：9/0  |  提交时间：2023/05/09 FeCrAl fuel cladding  Corrosion behavior  Crud deposition  Zn injection  Subcooled nuclear boiling   Effects of Nb addition and heat treatment on the microstructure, mechanical property and internal friction behavior of FeCrAlMo cladding alloys 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2022, 卷号: 572 作者:  Wang, H.;  Gao, Y. X.;  Sun, M.;  Li, G.;  He, K.   |  收藏  |  浏览/下载：35/0  |  提交时间：2022/12/23 Nb containing fecralmo alloys  Internal friction  Laves phase  Pinning effect  Strengthening mechanism   A novel approach on designing ultrahigh burnup metallic TWR fuels: Upsetting the current technological limits 期刊论文  OAI收割 MRS BULLETIN, 2022, 页码: 11 作者:  Feng, Linna;  Xu, Yuwen;  Qiu, Jie;  Liu, Xiang;  Wen, Chunyang   |  收藏  |  浏览/下载：8/0  |  提交时间：2023/05/09 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  OAI收割 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：33/0  |  提交时间：2021/12/13 CiADS  subcritical reactor  LBE  UO2 fuel  performance analysis  FUTURE code   Irradiation behaviors of two novel single-phase bcc-structure high-entropy alloys for accident-tolerant fuel cladding 期刊论文  OAI收割 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：34/0  |  提交时间：2021/10/15 High-entropy alloy  Accident-tolerant fuel cladding  Helium-ion irradiation  Microstructure  Irradiation hardening   In situ transmission electron microscopy study and molecular dynamics simulation of dislocation loop evolution in FeCrAl alloys under Fe+ irradiation 期刊论文  OAI收割 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：23/0  |  提交时间：2021/12/08 In situ TEM observation  Loop reaction  Molecular dynamics simulation  Fuel cladding  Irradiation damage   Lead-Cooled Fast Reactor Annular UN Fuel Design and Development of Performance Analysis Program 期刊论文  OAI收割 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：25/0  |  提交时间：2021/12/08 UN fuel  annular fuel  fuel performance analysis  COMSOL  fast reactors   Effects of ion irradiation on Cr, CrN, and TiAlCrN coated Zircaloy-4 for accident tolerant fuel claddings 期刊论文  OAI收割 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：36/0  |  提交时间：2021/05/17 Accident tolerant fuel  Cladding coatings  Zircaloy-4  Au ion irradiation  Grain boundary   A damage-effect-involved phenomenological crystal plasticity model and computational methods for mechanical responses of FeCrAl alloys 期刊论文  OAI收割 MATERIALS TODAY COMMUNICATIONS, 2021, 卷号: 28 作者:  Zhang, Jingyu;  Ding, Shurong;  Du, Shiyu   |  收藏  |  浏览/下载：9/0  |  提交时间：2021/12/01 NEUTRON-IRRADIATED MODEL  TOLERANT FUEL SYSTEM  ORIENTATION DEPENDENCE  ANISOTROPIC DAMAGE  CLADDING MATERIALS  STAINLESS-STEEL  BCC IRON  DEFORMATION  BEHAVIOR  MICROSTRUCTURE