You are being redirected because this document is part of your ASTM Compass® subscription.
    This document is part of your ASTM Compass® subscription.


    Effects of Neutron Irradiation on Creep-Rupture Properties of Type 316 Stainless Steel Tubes

    Published: Jan 1969

      Format Pages Price  
    PDF (224K) 15 $25   ADD TO CART
    Complete Source PDF (9.6M) 15 $117   ADD TO CART


    The effects of irradiation in the Dounreay Fast Reactor and the Dounreay Materials Testing Reactor on the creep-rupture-properties of Type 316 stainless steel tubing were investigated. DFR irradiation produced a loss of rupture ductility but, in general, no change in creep strength in 650 C biaxial tests of solution-treated material. Cold-worked tubes suffered a loss of 550 C creep strength. Irradiation of solution-treated tubes at 650 C in DMTR caused a severe loss of high-temperature ductility and a tenfold reduction of creep rate both during and after irradiation. It is possible that an irradiation-induced carbide precipitation process is responsible for the increase of creep strength.


    stainless steel, tubes, solution-treated, cold-worked, creep tests, ductility, creep strength, carbide precipitation

    Author Information:

    Standring, J.
    Section Leader, Fuel Cladding Materials, United Kingdom Atomic Energy Authority, Reactor Materials Laboratory, Warrington, Lancashire

    Bell, I. P.
    Group Leader, Physics and Physical Metallurgy, UKAEA, Reactor Materials Lab.,

    Tickle, H.
    UKAEA, Reactor Materials Lab.,

    Glendinning, A.
    UKAEA, Reactor Materials Lab.,

    Committee/Subcommittee: E10.08

    DOI: 10.1520/STP41861S

    CrossRef ASTM International is a member of CrossRef.