Acta Metall Sin  1998, Vol. 34 Issue (11): 1210-1216    DOI:

Current Issue | Archive | Adv Search |

PROPERTY OF RESISTANCE TO IRRADIATION DAMAGE OF ODS FERRITIC ALLOYS

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)

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. Acta Metall Sin, 1998, 34(11): 1210-1216.

Abstract References Related Articles Recommended Metrics Download:  PDF(2207KB)  Export:  BibTeX | EndNote (RIS)       Abstract  The property of resistance to irradiation swelling of oxide dispersion strengthened(ODS) ferritic alloys,prepared by mechanical alloying(MA), has been studied by means of electron and ion irradiation simulations.The results showed that ODS alloys are superior to austenitic alloys in the resistance to irradiation swelling and segregation. After high influx of 1.7×1017/cm2 argon ions implantation,bubbles were formed and the top of which chapped slightly on individual sections of the ODS material surface.In addition, ductile-to-brittle transition temperature(DBTT) of ODS alloys were higher than that of Fe-13%Cr alloy. There existed anisotropy of strength induced by rolling.Therefore,ductility of ODS needed to be enhanced. Key words:  oxide dispersion strengthening      ferritic alloy      irradiation damage      Received:  18 November 1998      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/Y1998/V34/I11/1210 1 Little E A.J Nucl Moter,1993;206:324 2单秉权,田耘,柳光祖,李华林,潘庆春.钢铁研究学报,1994;6(增刊):71(shan B Q,Tian Y,Liu G Z,Li H L,Pan Q C.J Iron Steel Res, 1994;6(sup):71) 3胡本芙,吴承健,高桥平七郎.金属学报,1995;31:A525(H B F, Wu C J,Takahashi H.Acta Metall Sin,1995;31:A525) 4田耘,潘庆春,柳光祖,单秉权,杨凤兰.金属学报,1998;34:1217(Tian Y, Pan Q C, Liu G Z,Shan B Q, Yang F L. Acta Metall Sin,1998;34:1217) 5井形直弘.核融合炉材料.东京:培风馆,1986:310(Igata N H.Materials for Fusion Reactors Tokyo:Pai Fu Kan Publishing House,1986:310) [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] 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. [3] Tao ZHANG, Wei YAN, Zhuoming XIE, Shu MIAO, Junfeng YANG, Xianping WANG, Qianfeng FANG, Changsong LIU. Recent Progress of Oxide/Carbide Dispersion Strengthened W-Based Materials[J]. 金属学报, 2018, 54(6): 831-843. [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] TIAN Yun;PAN Qingchun;LIU Guangzu;SHAN Bingquan;YANG Fenglan (Central Iron and Steel Research Institute; Beijing 100081). EFFECTS OF Ti ON STRENGTHENING OF ODS FERRITIC ALLOY FOR ADVANCED FBR CLADDING APPLICATION[J]. 金属学报, 1998, 34(11): 1217-1222. [10] HU Benfu;WU Chenglian(University of Science and Technology Beijing;Beijing 100083);TAKAHASHI Heishichiro(Faculty of Engineering;Hokkaido University;Sapporo;Japan)(Manuscript received 1995-02-10;in revised form 1995-06-15). BEHAVIOUR OF RESISTANCE TO IRRADIATED DAMAGE IN A NOVEL OXIDE DISPERSION STRENGTHENED FERRITIC STEEL(ODS STEEL)[J]. 金属学报, 1995, 31(11): 525-530. [11] 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[J]. 金属学报, 1994, 30(22): 448-452. [12] 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