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Title: Control of molten salt corrosion of fusion structural materials by metallic beryllium

Abstract

A series of tests have been performed between 2001 and 2006 at the Safety and Tritium Applied Research facility of the Idaho National Laboratory to demonstrate chemical compatibility between the molten salt flibe (2LiF+BeF2 in moles) and fusion structural materials once suitable fluoride potential control methods are established. The tests adopted metallic beryllium contact as main fluoride potential control, and the results have been published in recent years. A further step was to expose two specimens of low activation ferritic/martensitic steel 9Cr-2W to static corrosion tests that include an active corrosion agent (hydrofluoric gas) in controlled conditions at 530 C, and the results of the tests are presented in this paper. The results confirmed the expected correlation of the HF recovery with the concentration of metallic impurities dissolved in the salt because of specimen corrosion. The metals concentration dropped to level close to the detectable limit when the beryllium rod was inserted and increased once the content of excess beryllium in the system had been consumed by HF reduction and specimens corrosion progressed. Metallographic analysis of the samples after 500 hours exposure in reactive conditions showed evidence of the formation of unstable chromium oxide layers on the specimens surface.

Authors:
; ; ;
Publication Date:
Research Org.:
Idaho National Laboratory (INL)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
953241
Report Number(s):
INL/JOU-07-16043
Journal ID: ISSN 0022-3115; JNUMAM; TRN: US0902728
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 386 - 388
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BERYLLIUM; BUILDING MATERIALS; CHROMIUM OXIDES; COMPATIBILITY; CORROSION; FLIBE; FLUORIDES; IDAHO; IMPURITIES; MOLTEN SALTS; SAFETY; STEELS; TRITIUM; corrosion; flibe; molten salt

Citation Formats

P. Calderoni, P. Sharpe, H. Nishimura, and T. Terai. Control of molten salt corrosion of fusion structural materials by metallic beryllium. United States: N. p., 2009. Web. doi:10.1016/j.jnucmat.2008.12.292.
P. Calderoni, P. Sharpe, H. Nishimura, & T. Terai. Control of molten salt corrosion of fusion structural materials by metallic beryllium. United States. doi:10.1016/j.jnucmat.2008.12.292.
P. Calderoni, P. Sharpe, H. Nishimura, and T. Terai. Wed . "Control of molten salt corrosion of fusion structural materials by metallic beryllium". United States. doi:10.1016/j.jnucmat.2008.12.292.
@article{osti_953241,
title = {Control of molten salt corrosion of fusion structural materials by metallic beryllium},
author = {P. Calderoni and P. Sharpe and H. Nishimura and T. Terai},
abstractNote = {A series of tests have been performed between 2001 and 2006 at the Safety and Tritium Applied Research facility of the Idaho National Laboratory to demonstrate chemical compatibility between the molten salt flibe (2LiF+BeF2 in moles) and fusion structural materials once suitable fluoride potential control methods are established. The tests adopted metallic beryllium contact as main fluoride potential control, and the results have been published in recent years. A further step was to expose two specimens of low activation ferritic/martensitic steel 9Cr-2W to static corrosion tests that include an active corrosion agent (hydrofluoric gas) in controlled conditions at 530 C, and the results of the tests are presented in this paper. The results confirmed the expected correlation of the HF recovery with the concentration of metallic impurities dissolved in the salt because of specimen corrosion. The metals concentration dropped to level close to the detectable limit when the beryllium rod was inserted and increased once the content of excess beryllium in the system had been consumed by HF reduction and specimens corrosion progressed. Metallographic analysis of the samples after 500 hours exposure in reactive conditions showed evidence of the formation of unstable chromium oxide layers on the specimens surface.},
doi = {10.1016/j.jnucmat.2008.12.292},
journal = {Journal of Nuclear Materials},
number = ,
volume = 386 - 388,
place = {United States},
year = {Wed Apr 01 00:00:00 EDT 2009},
month = {Wed Apr 01 00:00:00 EDT 2009}
}