In the frame of the WCLL (water cooled lithium lead) programme, experimental and theoretical activities are devoted to study the interaction between the cooling water and lithium lead alloy. In case of large leakage, the interaction can lead to a pressurization of a blanket module which can challenge its integrity. Therefore, it is important to assess its consequences as accurately as possible. In order to make possible the modelling of the next LIFUS 5 experimental activity and to correctly understand the phenomena connected to a large break LOCA (loss of coolant accident) in the breeder zone in real conditions, a mathematical model has been tested on the BLAST experiences carried out at JRC-Ispra in the past years. A good fitting between experimental and modelling results has been obtained as shown in this paper.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Materials Science(all)
- Nuclear Energy and Engineering
- Mechanical Engineering
Sardain, P., Benamati, G., Ricapito, I., & Marbach, G. (2000). Modelling of the Pb17Li/water interaction within a blanket module. Fusion Engineering and Design, 51-52, 611 - 616. https://doi.org/10.1016/S0920-3796(00)00252-0