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
  • [31] THE DOSE DEPENDENCE OF INERT GASES IRRADIATION HARDENING OF 316 AUSTENITIC STAINLESS STEEL AFTER LOW TEMPERATURE IRRADIATION
    Karpov, S. A.
    Tolstolutskaya, G. D.
    Voyevodin, V. N.
    Tolmachova, G. N.
    Kopanets, I. E.
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2018, (05): : 34 - 39
  • [32] DEFORMATION-BEHAVIOR OF AUSTENITIC STAINLESS-STEELS AFTER AND DURING NEUTRON-IRRADIATION
    EHRLICH, K
    JOURNAL OF NUCLEAR MATERIALS, 1985, 133 (AUG) : 119 - 126
  • [33] CASE OF THRESHOLD SATURATION AND IRRADIATION INDUCED CREEP IN AUSTENITIC 15CR-35NI STEEL DURING NEUTRON-IRRADIATION
    HERSCHBACH, K
    BERGMANN, HJ
    JOURNAL OF NUCLEAR MATERIALS, 1990, 175 (1-2) : 143 - 146
  • [34] Prediction of the effects of neutron irradiation on the Charpy ductile to brittle transition curve of an A508 pressure vessel steel
    Bouchet, C
    Tanguy, B
    Besson, J
    Bugat, S
    COMPUTATIONAL MATERIALS SCIENCE, 2005, 32 (3-4) : 294 - 300
  • [35] EFFECT OF NEUTRON IRRADIATION ON CHEMICAL CORROSION PROPERTIES OF AN AUSTENITIC 18-8 CHROMIUM-NICKEL STEEL
    HERBSLEB, G
    SCHWENK, W
    NUKLEONIK, 1968, 11 (05): : 228 - &
  • [36] Degradation of austenitic stainless steel (SS) light water ractor (LWR) core internals due to neutron irradiation
    Rao, Appajosula S.
    NUCLEAR ENGINEERING AND DESIGN, 2014, 269 : 78 - 82
  • [37] IRRADIATION ENHANCED DIFFUSION IN AUSTENITIC STAINLESS-STEEL
    STANLEY, JT
    COST, JR
    JOURNAL OF METALS, 1982, 35 (12): : A37 - A37
  • [38] Irradiation resistance of a nanostructured 316 austenitic stainless steel
    Rajan, P. B. Revathy
    Monnet, I.
    Hug, E.
    Etienne, A.
    Enikeev, N.
    Keller, C.
    Sauvage, X.
    Valiev, R.
    Radiguet, B.
    6TH INTERNATIONAL CONFERENCE ON NANOMATERIALS BY SEVERE PLASTIC DEFORMATION (NANOSPD6), 2014, 63
  • [39] ELEVATED TEMPERATURE IRRADIATION HARDENING IN AUSTENITIC STAINLESS STEEL
    HOLMES, JJ
    ROBBINS, RE
    BRIMHALL, JL
    MASTEL, B
    ACTA METALLURGICA, 1968, 16 (07): : 955 - &
  • [40] Grain refinement of austenitic stainless steel by laser irradiation
    Kyushu Institute of Technology, Japan
    不详
    Yosetsu Gakkai Ronbunshu, 2009, 4 (270-277):
12345