SYMPOSIA PAPER Published: 01 January 2000
STP12438S

Void-Induced Swelling and Embrittlement in the Russian EI-847 Stainless Steel at PWR-Relevant End-of-Life Conditions

Source

Void swelling has been proposed to eventually reach significant levels in some austenitic internals at PWR end-of-life conditions. A prevailing perception based on previously published data from fast reactors is that swelling will never reach significant levels at temperatures in the 330–372°C range, even at the 80–90 dpa level anticipated in PWR baffle-former components after 40 years of operation. Fast reactor data are presented in this paper that show that this perception is incorrect, at least for a niobium-stabilized 16Cr-15Ni steel used in Russian reactors for applications where 316 would be used in Western reactors. As a result of the large swelling levels reached in some cases, the steel becomes very brittle, as expected from fast reactor experience.

Author Information

Garner, FA
Pacific Northwest National Laboratory, Richland, WA, USA
Porollo, SI
Institute of Physics and Power Engineering, Obninsk, Russian Federation
Vorobjev, AN
Institute of Physics and Power Engineering, Obninsk, Russian Federation
Konobeev, YV
Institute of Physics and Power Engineering, Obninsk, Russian Federation
Dvoriashin, AM
Institute of Physics and Power Engineering, Obninsk, Russian Federation
Krigan, VM
Institute of Physics and Power Engineering, Obninsk, Russian Federation
Budylkin, NI
Bochvar's Institute of Nonorganic Materials, Moscow, Russian Federation
Mironova, EG
Bochvar's Institute of Nonorganic Materials, Moscow, Russian Federation
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Details
Developed by Committee: E10
Pages: 874–883
DOI: 10.1520/STP12438S
ISBN-EB: 978-0-8031-5419-3
ISBN-13: 978-0-8031-2852-1