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Enos, David; Bryan, Charles R.
Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA) (United States)2015
Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States). Funding organisation: USDOE National Nuclear Security Administration (NNSA) (United States)2015
AbstractAbstract
[en] Although the susceptibility of austenitic stainless steels to chloride-induced stress corrosion cracking is well known, uncertainties exist in terms of the environmental conditions that exist on the surface of the storage containers. While a diversity of salts is present in atmospheric aerosols, many of these are not stable when placed onto a heated surface. Given that the surface temperature of any container storing spent nuclear fuel will be well above ambient, it is likely that salts deposited on its surface may decompose or degas. To characterize this effect, relevant single and multi-salt mixtures are being evaluated as a function of temperature and relative humidity to establish the rates of degassing, as well as the likely final salt and brine chemistries that will remain on the canister surface.
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1 Oct 2015; 15 p; NACE Corrosion 2016; Vancouver, BC (Canada); 6-10 Mar 2016; OSTIID--1328657; AC04-94AL85000
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