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Journal Articles Nuclear Engineering and Design Year : 2016

Impingement wastage experiments with 9Cr 1Mo steel

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Abstract

Steam Generator (SG) is one of the vital components of sodium cooled fast reactor (SFR). The main safety concern with SG is a probable sodium–water reaction. In case, one of its water/steam carrying tubes leaks, water/steam gets into contact with sodium causing sodium-water reaction, which is highly exothermic and producing corrosive NaOH and hydrogen. The ejecting reaction products at high temperature, impinges upon adjacent tubes by a process called impingement wastage. It could damage one of the neighboring tubes in a short time, if the detection and protection systems are failing. IGCAR and CEA carried out a collaborative study on impingement wastage of 9Cr 1Mo steel, which is one of the candidate materials for SFR SG tubes. The studies comprise of experimental works at IGCAR and simulation works with PROPANA code at CEA. This paper brings out the data and experience gained through this cooperative work.
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cea-02384008 , version 1 (28-11-2019)

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S. Kishore, François Beauchamp, Alexandre Allou, A. Ashok Kumar, S. Chandramouli, et al.. Impingement wastage experiments with 9Cr 1Mo steel. Nuclear Engineering and Design, 2016, 297, pp.104-110. ⟨10.1016/j.nucengdes.2015.11.024⟩. ⟨cea-02384008⟩

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