Published June 15, 2008 | Version v1
Journal article

Liquid metal embrittlement susceptibility of ferritic-martensitic steel in liquid lead alloys

  • 1. SCK-CEN - Belgian Nuclear Research Centre, Boeretang 200, B-2400 Mol (Belgium)

Description

The susceptibility of the ferritic-martensitic steels T91 and EUROFER97 to liquid metal embrittlement (LME) in lead alloys has been examined under various conditions. T91, which is currently the most promising candidate material for the high temperature components of the future accelerator driven system (ADS) was tested in liquid lead bismuth eutectic (LBE), whereas the reduced activation steel, EUROFER97 which is under consideration to be the structural steel for fusion reactors was tested in liquid lead lithium eutectic. These steels, similar in microstructure and mechanical properties in the unirradiated condition were tested for their susceptibility to LME as function of temperature (150-450 deg. C) and strain rate (1 x 10-3-1 x 10-6 s-1). Also, the influence of pre-exposure and surface stress concentrators was evaluated for both steels in, respectively, liquid PbBi and PbLi environment. To assess the LME effect, results of the tests in liquid metal environment are compared with tests in air or inert gas environment. Although both unirradiated and irradiated smooth ferritic-martensitic steels do not show any or little deterioration of mechanical properties in liquid lead alloy environment compared to their mechanical properties in gas as function of temperature and strain rate, pre-exposure or the presence of surface stress concentrators does lead to a significant decrease in total elongation for certain test conditions depending on the type of liquid metal environment. The results are discussed in terms of wetting enhanced by liquid metal corrosion or crack initiation processes

Availability note (English)

Available from http://dx.doi.org/10.1016/j.jnucmat.2008.02.008

Additional details

Identifiers

DOI
10.1016/j.jnucmat.2008.02.008;
PII
S0022-3115(08)00075-5;

Publishing Information

Journal Title
Journal of Nuclear Materials
Journal Volume
376
Journal Issue
3
Journal Page Range
p. 322-329
ISSN
0022-3115
CODEN
JNUMAM

Conference

Title
4. international workshop on materials for heavy liquid metal cooled reactors and related technologies
Dates
21-23 May 2007
Place
Rome (Italy)

INIS

Optional Information

Copyright
Copyright (c) 2008 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.