SYMPOSIA PAPER Published: 01 January 1969

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


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.

Author Information

Standring, J.
Fuel Cladding Materials, United Kingdom Atomic Energy Authority, Reactor Materials Laboratory, Warrington, Lancashire, England
Bell, I., P.
Physics and Physical Metallurgy, UKAEA, Reactor Materials Lab.
Tickle, H.
UKAEA, Reactor Materials Lab.
Glendinning, A.
UKAEA, Reactor Materials Lab.
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Developed by Committee: E10
Pages: 414–428
DOI: 10.1520/STP41861S
ISBN-EB: 978-0-8031-6036-1
ISBN-13: 978-0-8031-6190-0