Thermal Aging Phenomena in Cast Duplex Stainless Steels

Byun, T. S.; Yang, Y.; Overman, N. R.; Busby, J. T.

doi:10.1007/s11837-015-1709-9

Title: Thermal Aging Phenomena in Cast Duplex Stainless Steels

Journal Article · Thu Nov 12 00:00:00 EST 2015 · JOM. Journal of the Minerals, Metals & Materials Society

DOI:https://doi.org/10.1007/s11837-015-1709-9· OSTI ID:1261499

Byun, T. S. ^[1]; Yang, Y. ^[2]; Overman, N. R. ^[1]; Busby, J. T. ^[2]

Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

We used cast stainless steels (CASSs)for the large components of light water reactor (LWR) power plants such as primary coolant piping and pump casing. The thermal embrittlement of CASS components is one of the most serious concerns related to the extended-term operation of nuclear power plants. Many past researches have concluded that the formation of Cr-rich alpha-phase by Spinodal decomposition of delta-ferrite phase is the primary mechanism for the thermal embrittlement. Cracking mechanism in the thermally-embrittled duplex stainless steels consists of the formation of cleavage at ferrite and its propagation via separation of ferrite-austenite interphase. This article intends to provide an introductory overview on the thermal aging phenomena in LWR-relevant conditions. Firstly, the thermal aging effect on toughness is discussed in terms of the cause of embrittlement and influential parameters. Moreover, an approximate analysis of thermal reaction using Arrhenius equation was carried out to scope the aging temperatures for the accelerated aging experiments to simulate the 60 and 80 years of services. Further, an equilibrium precipitation calculation was performed for model CASS alloys using the CALPHAD program, and the results are used to describe the precipitation behaviors in duplex stainless steels. Our results are also to be used to guide an on-going research aiming to provide knowledge-based conclusive prediction for the integrity of the CASS components of LWR power plants during the service life extended up to and beyond 60 years.

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Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE)

Grant/Contract Number:: AC05-00OR22725; AC05-76RL01830

OSTI ID:: 1261499

Journal Information:: JOM. Journal of the Minerals, Metals & Materials Society, Vol. 68, Issue 2; ISSN 1047-4838

Publisher:: SpringerCopyright Statement

Country of Publication:: United States

Language:: English

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Cited by: 37 works

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