An austenitic steel remaining ductile after neutron irradiation

被引:1
|
作者
Schafer, L
机构
[1] Forschungszentrum Karlsruhe, Inst. für Materialforschung II, D-76021 Karlsruhe
关键词
D O I
10.1016/0022-3115(96)00356-X
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Within the framework of the development of austenitic steels which are suited as materials for cladding tubes and core components of fast breeder reactors two heats were conceived and investigated with different priorities as regards their resistance to helium embrittlement (B801) and void swelling (F218). After in-pile irradiations with fast and mixed neutron fluxes, respectively, both steels exhibited a ductility higher by a factor of 5 than that of the 1.4970 reference steel, both in hot tensile and in creep rupture tests. Both steels are resistant to swelling in the tested region (neutron irradiation up to 40 dpa).
引用
收藏
页码:63 / 68
页数:6
相关论文
共 50 条
  • [41] IRRADIATION-PRODUCED DEFECTS IN AUSTENITIC STAINLESS STEEL
    BRAGER, HR
    STRAALSU.JL
    HOLMES, JJ
    BATES, JF
    METALLURGICAL TRANSACTIONS, 1971, 2 (07): : 1893 - +
  • [42] Irradiation behavior of nanostructured 316 austenitic stainless steel
    B. Radiguet
    A. Etienne
    P. Pareige
    X. Sauvage
    R. Valiev
    Journal of Materials Science, 2008, 43 : 7338 - 7343
  • [43] Irradiation behavior of nanostructured 316 austenitic stainless steel
    Radiguet, B.
    Etienne, A.
    Pareige, P.
    Sauvage, X.
    Valiev, R.
    JOURNAL OF MATERIALS SCIENCE, 2008, 43 (23-24) : 7338 - 7343
  • [44] Fatigue properties of ferritic/martensitic steel after neutron irradiation and helium implantation
    Nogami, Shuhei
    Hasegawa, Akira
    Yamazaki, Masanori
    NUCLEAR MATERIALS AND ENERGY, 2020, 24
  • [45] NEUTRON IRRADIATION EFFECTS IN AUSTENITIC STAINLESS STEELS AND A NIMONIC ALLOY
    BROOMFIELD, GH
    HARRIES, DR
    ROBERTS, AC
    JOURNAL OF THE IRON AND STEEL INSTITUTE, 1965, 203 : 502 - +
  • [46] Charpy impact test on A508-3 steel after neutron irradiation
    Lin, Yun
    Yang, Wen
    Tong, Zhenfeng
    Zhang, Changyi
    Ning, Guangsheng
    ENGINEERING FAILURE ANALYSIS, 2017, 82 : 733 - 740
  • [47] STUDY OF THE MICROSTRUCTURE OF A TITANIUM-316 STEEL AFTER AGING AND AFTER NEUTRON-IRRADIATION
    BRUN, G
    LENAOUR, J
    VOUILLON, M
    JOURNAL OF NUCLEAR MATERIALS, 1981, 101 (1-2) : 109 - 123
  • [48] Dependence of the concentration of point defects in the ChS-68 austenitic steel on the rate of their generation and temperature upon neutron irradiation
    Kozlov, A. V.
    PHYSICS OF METALS AND METALLOGRAPHY, 2009, 107 (06): : 534 - 541
  • [49] EFFECT OF NEUTRON IRRADIATION ON MICROSTRUCTURE AND PROPERTIES OF AUSTENITIC AlSi 321 STEEL, SUBJECTED TO EQUAL-CHANNEL ANGULAR PRESSING
    Shamardin, Valentin K.
    Goncharenko, Yuri D.
    Bulanova, Tatyana M.
    Karsakov, Aleksey A.
    Alexandrov, Igor V.
    Abramova, Marina M.
    Karavaeva, Marina V.
    REVIEWS ON ADVANCED MATERIALS SCIENCE, 2012, 31 (02) : 167 - 173
  • [50] Dependence of the concentration of point defects in the ChS-68 austenitic steel on the rate of their generation and temperature upon neutron irradiation
    A. V. Kozlov
    The Physics of Metals and Metallography, 2009, 107 : 534 - 541