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
来源：
JOURNAL OF NUCLEAR MATERIALS | 1996年 / 231卷 / 1-2期
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
  • [21] Neutron diffraction investigations of stresses in austenitic steel
    Balagurov, AM
    Bokuchava, GD
    Schreiber, J
    Taran, YV
    PHYSICA B, 1997, 234 : 967 - 968
  • [22] INITIATION OF DUCTILE FAILURE BY FRACTURED CARBIDES IN AN AUSTENITIC STAINLESS STEEL
    BARNBY, JT
    ACTA METALLURGICA, 1967, 15 (05): : 903 - &
  • [23] IRRADIATION INDUCED SWELLING IN AUSTENITIC STAINLESS STEEL
    HOLMES, JJ
    BRAGER, HR
    JOURNAL OF METALS, 1968, 20 (08): : A115 - &
  • [24] Influence of Radiation Porosity Created in Austenitic Steel upon Neutron Irradiation on the Concentration of Intrinsic Point Defects
    A. R. Isinbaev
    I. A. Portnykh
    A. V. Kozlov
    Physics of Metals and Metallography, 2020, 121 : 89 - 94
  • [25] Influence of Radiation Porosity Created in Austenitic Steel upon Neutron Irradiation on the Concentration of Intrinsic Point Defects
    Isinbaev, A. R.
    Portnykh, I. A.
    Kozlov, A. V.
    PHYSICS OF METALS AND METALLOGRAPHY, 2020, 121 (01): : 89 - 94
  • [26] FAST-NEUTRON IRRADIATION HARDENING OF AUSTENITIC STAINLESS-STEEL AT 250-DEGREES-C
    ELEN, JD
    FENICI, P
    JOURNAL OF NUCLEAR MATERIALS, 1992, 191 : 766 - 770
  • [27] MICROSTRUCTURAL EVOLUTION OF TITANIUM MODIFIED AUSTENITIC STAINLESS-STEEL AFTER FFTF IRRADIATION
    KOHNO, Y
    KOHYAMA, A
    KAYANO, H
    JOURNAL OF NUCLEAR MATERIALS, 1992, 191 : 742 - 747
  • [28] Effect of helium on grain boundary segregation of austenitic stainless steel after proton irradiation
    Dewi, K
    Hasegawa, A
    Otsuka, S
    Abe, K
    FUSION TECHNOLOGY, 2001, 39 (02): : 585 - 589
  • [29] Welding-induced mechanical properties in austenitic stainless steels before and after neutron irradiation
    Stoenescu, R.
    Schaeublin, R.
    Gavillet, D.
    Baluc, N.
    JOURNAL OF NUCLEAR MATERIALS, 2007, 360 (03) : 255 - 264
  • [30] Strain hardening and plastic instability properties of austenitic stainless steels after proton and neutron irradiation
    Byun, TS
    Farrell, K
    Lee, EH
    Hunn, JD
    Mansur, LK
    JOURNAL OF NUCLEAR MATERIALS, 2001, 298 (03) : 269 - 279
12345