Published 2012 | Version v1
Miscellaneous

Corrosion behavior of welds in oxygen containing liquid lead

  • 1. Karlsruhe Institute of Technology (Germany). Inst. for Pulsed Power and Microwave Technology

Description

Liquid lead (Pb) and lead-bismuth eutectic (LBE) have been considered as coolant and/or spallation target in future accelerator driven systems (ADS). Therefore, in the recent years a lot of corrosion experiments on conventional steels were carried out in these heavy liquid metals. Beside these experiments, also tests on welded joints are required. Therefore ferritic/martensitic (F/M) steels (P91, P92) as well as an ODS steel were joint with TIG (Tungsten-Inert-Gas), EB (Electron Beam) and friction stir welding. After that, specimens were exposed to 10-6 and 10-8wt% oxygen containing lead at 550 C for about 2000h. Weld regions having similar chemical composition and similar structure due to a heat treatment after the welding process show a corrosion behaviour under these conditions that is similar to that of the respective bulk material. (orig.)

Part of:
Annual meeting on nuclear technology 2012. Documentation

Additional details

Additional titles

Original title (English)
Jahrestagung Kerntechnik 2012. Dokumentation

Publishing Information

Imprint Title
Annual meeting on nuclear technology 2012. Documentation
Imprint Pagination
1411 p.
Journal Page Range
4 p.

Conference

Title
Annual meeting on nuclear technology 2012
Original Conference Title
Jahrestagung Kerntechnik 2012
Dates
22-24 May 2012
Place
Stuttgart (Germany)

Optional Information

Notes
Imprint:Jahrestagung Kerntechnik 2012. Dokumentation