中国科学院机构知识库网格系统: 检索

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	In-beam creep of SiCf/SiC minicomposites under uniaxial tensile loading 期刊论文 OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 533, 页码: 7 作者: Chen, Jiachao; Jacques, Sylvain; Barthe, Marie-France; Zhang, Chonghong; Desgardin, Pierre \| 收藏 \| 浏览/下载：25/0 \| 提交时间：2022/01/18 SiCf/SiC composite High-temperature mechanical testing Irradiation creep Clamping system
	Ion-beam-assisted characterization of quinoline-insoluble particles in nuclear graphite 期刊论文 OAI收割 NUCLEAR SCIENCE AND TECHNIQUES, 2020, 卷号: 31, 期号: 10, 页码: - 作者: Huang, Q; Han, XQ; Liu, P; Li, JJ; Lei, GH \| 收藏 \| 浏览/下载：32/0 \| 提交时间：2021/09/06 TRANSMISSION ELECTRON-MICROSCOPY NEUTRON-IRRADIATION RAMAN-SPECTRA DAMAGE ENERGY IG-110 CREEP
	Excellent irradiation tolerance and mechanical behaviors in high-entropy metallic glasses 期刊论文 OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2019, 卷号: 527, 页码: 8 作者: Wang Y(王洋); Zhang K(张坤); Feng YH(冯义辉); Li YS(李炎森); Tang WQ(唐伟奇) \| 收藏 \| 浏览/下载：140/0 \| 提交时间：2020/03/11 High-entropy metallic glass Irradiation damage Serrated flow Creep behavior
	Microstructure modification and mechanical property improvement of reduced activation ferritic/martensitic steel by severe plastic deformation 期刊论文 OAI收割 MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 卷号: 712, 页码: 97-107 作者: Jin, XJ; Chen, SH; Rong, LJ; Rong, LJ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 72 Wenhua Rd, Shenyang 110016, Liaoning, Peoples R China. \| 收藏 \| 浏览/下载：21/0 \| 提交时间：2018/06/05 High-temperature Oxidation Martensitic Steel Attrition Treatment Fusion Application 9cr2wvta Steel Ferritic Steel Creep Behavior Alloys Irradiation
	Microstructure, hardness and modulus of carbon-ion-irradiated new SiC fiber (601-4) 期刊论文 OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 503, 页码: 91-97 作者: Huang, Q; Lei, GH; Liu, RD; Li, JJ; Yan, L \| 收藏 \| 浏览/下载：23/0 \| 提交时间：2018/09/06 Silicon-carbide Fibers Neutron-irradiation Matrix Composites Nicalon Fibers Raman-spectra Radiation Amorphization Damage Creep
	Microstructure and properties of fine-grained isotropic graphite based on mixed fillers for application in molten salt breeder reactor 期刊论文 OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 511, 期号: -, 页码: 318-327 作者: He, Z; Lian, PF; Song, JL; Zhang, DQ; Liu, ZJ \| 收藏 \| 浏览/下载：30/0 \| 提交时间：2019/12/17 LIQUID FLUORIDE SALT HIGH THERMAL-CONDUCTIVITY IRRADIATION-INDUCED CREEP NUCLEAR GRAPHITE NEUTRON-IRRADIATION NATURAL GRAPHITE INFILTRATION TECHNOLOGY PROTECTION EXPANSION
	Evolution of grain boundary carbides in thermal exposed Ti-modified alloy N 期刊论文 OAI收割 MATERIALS CHARACTERIZATION, 2017, 卷号: 133, 期号: -, 页码: 54-59 作者: Shen, L; Jiang, L; Liu, RD; Ye, XX; Zhang, WZ \| 收藏 \| 浏览/下载：25/0 \| 提交时间：2018/08/30 Molten-salt Reactor Austenitic Stainless-steel Hastelloy-n Rupture Irradiation Additions Creep Mc
	Effects of fuel particle size and fission-fragment-enhanced irradiation creep on the in-pile behavior in CERCER composite pellets 期刊论文 OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2016, 卷号: 482, 页码: 278-293 作者: Zhao, Yunmei; Ding, Shurong; Zhang, Xunchao; Wang, Canglong; Yang, Lei \| 收藏 \| 浏览/下载：62/0 \| 提交时间：2018/05/31 Particle size effect Fission-fragment-enhanced irradiation creep Numerical simulation Cracking mechanism
	SIMULATION OF THE IN-PILE BEHAVIORS EVOLUTION IN NUCLEAR FUEL RODS WITH THE IRRADIATION DAMAGE EFFECTS 期刊论文 OAI收割 ACTA MECHANICA SOLIDA SINICA, 2014, 卷号: 27, 页码: 551-567 作者: Gong, Xin; Jiang, Yijie; Ding, Shurong; Huo, Yongzhong; Wang, Canglong \| 收藏 \| 浏览/下载：121/0 \| 提交时间：2018/07/05 Irradiation Hardening Irradiation Creep Large-deformation Thermo-mechanical Coupling Fem