Sodium aerosol behaviour with CONTAIN-LMR code

The prediction of nuclear aerosols behaviour associated with postulated accidents in in Sodium-cooled Fast Reactors (SFRs) is necessary for the assessment of the radiological consequences of these events and to optimize filter systems and as well as design safety adapted reactor components. As a consequence of the high chemical reactivity of sodium with air and steam, it would undergo sodium oxidation within the containment atmosphere. The exothermic nature of the chemical reactions determines to a large extent both particle size distribution and population. As a result, the radiological source term to the environment will then depend on in-containment Na-aerosol behavior. CONTAIN-LMR code can reproduce physical and chemical processes during sodium fires in case of a severe accident in a SFR. CONTAIN-LMR is a computer code to analyze physical and chemical phenomena, including modeling of the sodium fire and aerosol behavior, in the reactor containment after a severe accident. For the validation experiments with pool-sodium fire performed in the FAUNA facility at the former FZK have been used.



Gordeev, S, Hering, W., Schikorr, M., Stieglitz, R. Simulation of sodium aerosol behaviour with CONTAIN-LMR code. International Congress on Advances in Nuclear Power Plants, ICAPP 2014 Volume 2, 2014, Pages 889-894 Charlotte, NC; United States; 6 April 2014 through 9 April 2014; Code 107534

Gordeev, S., Hering, W., Schikorr, M., Stieglitz, R. Sensitivity analysis of contain-LMR calculations to the aerosol shape factors. International Congress on Advances in Nuclear Power Plants, ICAPP 2013: Nuclear Power - A Safe and Sustainable Choice for Green Future, Held with the 28th KAIF/KNS Annual Conference 2013, Pages 358-363 Jeju Island; South Korea; 14 April 2013 through 18 April 2013; Code 110977

Gordeev, S.,  Hering, W.,  Schikorr, M., Stieglitz, R. Validation of CONTAIN-LMR code for accident analysis of sodium-cooled fast reactor containments. International Congress on Advances in Nuclear Power Plants 2012, ICAPP 2012 Volume 3, 2012, Pages 2088-2095 Chicago, IL; United States; 24 June 2012 through 28 June 2012; Code 93719