Acta Metall Sin  1994, Vol. 30 Issue (22): 448-452    DOI:

Current Issue | Archive | Adv Search |

BEHAVIOUR OF OXIDE DISPERSION STRENTHENED FERRITIC STEEL UNDER ELECTRON IRRADIATION

WAN Farong; HUANG Xuejun; KONG Feng;CHU Wuyang;XIAO Jimei(University of Science and Technology Beijing); TAKAHASHI Heishichiro(Hokkaido University; Japan)

WAN Farong; HUANG Xuejun; KONG Feng;CHU Wuyang;XIAO Jimei(University of Science and Technology Beijing); TAKAHASHI Heishichiro(Hokkaido University; Japan). BEHAVIOUR OF OXIDE DISPERSION STRENTHENED FERRITIC STEEL UNDER ELECTRON IRRADIATION. Acta Metall Sin, 1994, 30(22): 448-452.

Abstract References Related Articles Recommended Metrics Download:  PDF(337KB)  Export:  BibTeX | EndNote (RIS)       Abstract  The irradiation behaviour of the oxide dispersion strengthened ferritic steel, made in China, has been investigated by high voltage electron microscope. The results showed that voids formed under electron irradiation at temperature of 670-720 K.The void swelling is less than 0.1% in the specimens irradiated to a dose of 9 dpa at 720 K. At thg same time, electron diffraction rings were obeserved. These rings may results from the formation of micro oxide phases of Y2O3. Key words:  irradiation damage      fast breeder reactor      cladding material      irradiation swelling      Service E-mail this article Add to citation manager E-mail Alert RSS （） Articles by authors URL:  https://www.ams.org.cn/EN/     OR     https://www.ams.org.cn/EN/Y1994/V30/I22/448 1万发荣．金属材料的辐照损伤．北京:科学出版社,19932HuetJJ,Lercy．V．NuclTech,1974;24:2163AsanoK,KohnoY,KoyamaA,suzukiT,KusanagiH．JNuclMater,1988;155-157:9284KinoshitaH,AkasakaN,TakahashiH,ItohM,OnoseS．JNuclMater,1991;179—181:7225KinoshitaH,AkasakaN．JNuclMater,1992;191-194:8746黄学军,万发荣,褚武扬,肖纪美．海峡两岸学术会议论文集,北京:北京科技大学,19937WanF,TakahashiH,OhnukiS,NagasakiR．JNuclMater,1988;155-157:770 [1] LIU Wei, CHEN Wanqi, MA Menghan, LI Kailun. Review of Irradiation Damage Behavior of Tungsten Exposed to Plasma in Nuclear Fusion[J]. 金属学报, 2023, 59(8): 986-1000. [2] WEN Donghui, JIANG Beibei, WANG Qing, LI Xiangwei, ZHANG Peng, ZHANG Shuyan. Microstructure Evolution at Elevated Temperature and Mechanical Properties of MoNb-Modified FeCrAl Stainless Steel[J]. 金属学报, 2022, 58(7): 883-894. [3] Yucheng WU. Research Progress in Irradiation Damage Behavior of Tungsten and Its Alloys for Nuclear Fusion Reactor[J]. 金属学报, 2019, 55(8): 939-950. [4] HUANG Yuan KONG Deyue HE Fang WANG Yulin LIU Wenxi. PREPARATION OF Mo/Ag LAMINAR COMPOSITES BY USING IRRADIATION DAMAGE ALLOYING METHOD[J]. 金属学报, 2012, 48(10): 1253-1259. [5] LU Zheng. RADIATION-NDUCED EMBRITTLEMENT AND LIFE EVALUATION OF REACTOR PRESSURE VESSELS[J]. 金属学报, 2011, 47(7): 777-783. [6] SUN Chao TAN Jun YING Shihao LI Cong PENG Qian ZHAO Suqiong. PREDICTION OF CRITICAL TEMPERATURE FOR DELAYED HYDRIDE CRACKING IN IRRADIATED N18 ZIRCONIUM ALLOY[J]. 金属学报, 2010, 46(7): 805-809. [7] HU Benfu; HKINOSHITA Hiroshi; SAKAGUCHI Kisiki; TAKAHASHI Heishichiro. Radiation Damage Behavior of Carbide in Long Term Aging Treatmented Low Activation Austenitic Fe-Cr-Mn Alloy[J]. 金属学报, 2006, 42(3): 234-238 . [8] HU Benfu; TAKAHASHI; Heishichiro. Effects of Helium on Behavior of Point Defect Produced by Irradiation in Low Activation Fe-Cr-Mn(W,V) Alloys[J]. 金属学报, 2004, 40(9): 955-961 . [9] SUN Jiguang;CHEN Chaoqing;ZHANG Xishun (General Research institute for Nonferrous Metals; Beijing 100088)TIAN Yan;SHAN Bingquan;PAN Qingchun (Central Iron & Steel Research institute; Beijing 100081). PROPERTY OF RESISTANCE TO IRRADIATION DAMAGE OF ODS FERRITIC ALLOYS[J]. 金属学报, 1998, 34(11): 1210-1216. [10] WAN Farong;XIAO Jimei;YUAN Yi University of Science and Technology Beijing lecturer;Department of Material Physics;University of Science and Technology Beijing; Beijing 100083. MEASUREMENT OF VACANCY MIGRATION ENERGY BY ELECTRON IRRADIATION[J]. 金属学报, 1990, 26(2): 74-78. No Suggested Reading articles found! Viewed Full text Abstract Cited   Shared      Discussed