SYMPOSIA PAPER Published: 01 January 1970
STP26637S

Some Observations on the Structure and Tensile Properties of AISI Type 316 Steel as a Function of Fast Reactor Irradiation Temperature

Source

Solution treated AISI Type 316 steel strip specimens were irradiated in the Dounreay fast reactor to doses of 1.0 to 1.3 ×1022n/cm2 (total), 1.7 to 2.6 ×1021 n/cm2 (fission) within the following measured temperature ranges: 420 to 440, 500 to 513, 520 to 533, 560 to 570, and 645 to 650 C.

Transmission electron microscopy reveals the presence of voids after irradiation at all these temperatures. Distribution is uniform after irradiation at 420 to 440, 500 to 513, and 520 to 533 C. At higher temperatures it is uneven and concentration is so low that probably helium bubbles and not voids are being observed. From the temperature dependence of void concentration and average diameter it is deduced that the consequent density decrease is maximal after irradiation at 500 to 513 C.

Dislocation loops are present for irradiation at all but the highest temperature. They are interstitial and lie on {111} planes with Burgers vectors of the type a/3 ⟨111 ⟩. At 420 to 440 C all loops are faulted. As irradiation temperature increases, loop concentration decreases, and at 520 to 533 C a few unfaulted loops are observed. Yield stress increases estimated from loop and void concentrations are found to be in fair agreement with measured values.

Author Information

Barton, PJ
United Kingdom Atomic Energy Authority, Atomic Energy Research Establishment, Harwell, Didcot, Berkshire, England
Higgins, PRB
United Kingdom Atomic Energy Authority, Atomic Energy Research Establishment, Harwell, Didcot, Berkshire, England
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Details
Developed by Committee: E10
Pages: 362–374
DOI: 10.1520/STP26637S
ISBN-EB: 978-0-8031-4593-1
ISBN-13: 978-0-8031-0014-5