Detection of coolant void in lead-cooled fast reactors

•We model the ALFRED LFR using different Monte-Carlo codes.•We study the impact on coolant void on the fission cross section in fission chambers.•We develop a methodology to detect coolant void.•We study the impact of detector fissile coating burn-up.•We conclude that the developed methodology may be an attractive complement to LFR monitoring. Previous work (Wolniewicz et al., 2013) has indicated that using fission chambers coated with 242Pu and 235U, respectively, can provide the means of detecting changes in the neutron flux that are connected to coolant density changes in a small lead-cooled fast reactor. Such density changes may be due to leakages of gas into the coolant, which, over time, may coalesce to large bubbles implying a high risk of causing severe damage of the core. By using the ratio of the information provided by the two types of detectors a quantity is obtained that is sensitive to these density changes and, to the first order approximation, independent of the power level of the reactor. In this work we continue the investigation of this proposed methodology by applying it to the Advanced LFR European Demonstrator (ALFRED) and using realistic modelling of the neutron detectors. The results show that the methodology may be used to detect density changes indicating the initial stages of a coalescence process that may result in a large bubble. Also, it is shown that under certain circumstances, large bubbles passing through the core could be detected with this methodology.