Prakt. Met. Sonderband 38 (2006) 141 
Corrosion of Different Steels in Lead Bismuth Eutectic 
P. Hosemann®®, S. Maloy?, N. Li 
Los Alamos National Naboratory, USA 
University of Leoben, Austria 
Abstract: 
Ferritic Martensitic steels are candidate materials for high dose nuclear applications in GenlV 
reactor concepts. These materials exhibit low swelling and relatively low radiation induced 
embrittlement. One specific GenlV concept of interest is the Lead Bismuth Eutectic (LBE) 
cooled fast reactor (LFR). To investigate the use of ferritic/martensitic (F/M) steels for LFRs, 
corrosion tests are needed to ensure their stability in this environment. The most common 
reactor steels (T91, HT9 and EP823) were tested in LBE as well as an ODS alloy (PM2000) 
which can be used for higher temperature applications. The characterization of the formed 
oxide layer during the experiment in this environment (535°C, 10®wt% oxygen in the LBE, 
2m/sec LBE velocity, 200, 400, and 600h) is shown using SEM/EDX/WDX, nano indention 
and X-ray photoelectron spectroscopy. 
Introduction: 
Liquid LBE and liquid lead are candidate coolants for Generation IV reactors and spallation 
neutron targets [1,2]. The advantages of using LBE or lead as a nuclear coolant are derived 
blichen from its physical properties such as high boiling temperature, low melting point, good thermal 
transport, low viscosity, low neutron capture and moderation, and high spallation neutron 
| yield. The disadvantage of using either LBE or lead is that it is an aggressive medium towards 
ch, die its container materials, particularly at high temperatures. To make these systems usable at 
ezielle temperatures above 400°C, materials have to be selected and tested that show no or low and 
predictable corrosion over a long period of time (>30 years). Because a 30-year test can not 
be performed easily, the corrosion mechanisms have to be understood so predictions can be 
ann im made. Since the main use of these materials is in an irradiation environment, only a select 
smacht few can be used. Austenitic steels, unstable alloys and strong aging materials as well as 
many others can not be used for this reason. Therefore, the focus of this study is on F/M 
steels. Since the licensing of steels in nuclear environment is a long process, the fastest way 
‚on der to get to usable materials for this application is to use already certified materials like T91, HT- 
9 and EP823. To look at advanced materials with improved high temperature properties, the 
ODS material PM2000 was also tested at a temperature at 535°C in LBE for 200h and 600h. 
sierung These experiments were performed in the DELTA Loop at Los Alamos National Laboratory 
rgebnis {LANL). 
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