| کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن | 
|---|---|---|---|---|
| 1564718 | 1514168 | 2016 | 15 صفحه PDF | دانلود رایگان | 
عنوان انگلیسی مقاله ISI
												Neutron-irradiation creep of silicon carbide materials beyond the initial transient
												
											ترجمه فارسی عنوان
													خزش نیتروژن از مواد سیلیکون کاربید فراتر از گذشت اولیه 
													
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																																												موضوعات مرتبط
												
													مهندسی و علوم پایه
													مهندسی انرژی
													انرژی هسته ای و مهندسی
												
											چکیده انگلیسی
												Irradiation creep beyond the transient regime was investigated for various silicon carbide (SiC) materials. The materials examined included polycrystalline or monocrystalline high-purity SiC, nanopowder sintered SiC, highly crystalline and near-stoichiometric SiC fibers (including Hi-Nicalon Type S, Tyranno SA3, isotopically-controlled Sylramic and Sylramic-iBN fibers), and a Tyranno SA3 fiber-reinforced SiC matrix composite fabricated through a nano-infiltration transient eutectic phase process. Neutron irradiation experiments for bend stress relaxation tests were conducted at irradiation temperatures ranging from 430 to 1180 °C up to 30 dpa with initial bend stresses of up to â¼1 GPa for the fibers and â¼300 MPa for the other materials. Initial bend stress in the specimens continued to decrease from 1 to 30 dpa. Analysis revealed that (1) the stress exponent of irradiation creep above 1 dpa is approximately unity, (2) the stress normalized creep rate is â¼1 Ã 10â7 [dpaâ1 MPaâ1] at 430-750 °C for the range of 1-30 dpa for most polycrystalline SiC materials, and (3) the effects on irradiation creep of initial microstructures-such as grain boundary, crystal orientation, and secondary phases-increase with increasing irradiation temperature.
											ناشر
												Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Journal of Nuclear Materials - Volume 478, September 2016, Pages 97-111
											Journal: Journal of Nuclear Materials - Volume 478, September 2016, Pages 97-111
نویسندگان
												Takaaki Koyanagi, Yutai Katoh, Kazumi Ozawa, Kazuya Shimoda, Tatsuya Hinoki, Lance L. Snead, 
											