Long-term corrosion of austenitic steels in flowing LBE at 400 °C and 10 −7 mass% dissolved oxygen in comparison with 450 and 550 °C-Reference-Cited by-同舟云学术

Long-term corrosion of austenitic steels in flowing LBE at 400 °C and 10 −7 mass% dissolved oxygen in comparison with 450 and 550 °C

Published:2016-01 Issue: Volume:468 Page:305-312
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Tsisar Valentyn,Schroer Carsten,Wedemeyer Olaf,Skrypnik Aleksandr,Konys Jürgen

Funder

NUSAFE

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference25 articles.

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3. Results of a New Production of Nuclear-Grade 1.4970 ‘15-15Ti’ Stainless Steel Fuel Cladding Tubes for GEN IV Reactors, Proceedings of the 22nd International Conference on Nuclear Engineering ICONE22;Delville,2014

4. Liquid Metal Corrosion Mechanisms: Corrosion of Reactor Materials,1962

5. Selective leaching of nickel and chromium from Type 316 austenitic steel in oxygen-containing lead–bismuth eutectic (LBE)

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