Facility Details: MISTEE

Organization / Localization: KTH-NPS
Facility Description: It consists of an interaction chamber, an induction melt furnace, an external trigger system, an operational control system, and data acquisition and visualization systems. The test section is a rectangular tank (180x130x250mm) with 4 view windows (70x150x24mm) with a 1kW immersion heater.
Test Identification: MISTEE-Al
SA-Related Topics / Phenomena: Spontaneous steam explosion. Melt fragmentation.
Measured Parameters: Steam explosion impulse. Melt fragmentaiton dynamic.
Modelling:  
Simulation Code:  
Experimental Research Program: (i) EU SAFEST; (ii) National program "Accident Phenomena of Risk Importance" (APRI) supported by consortium of SSM and NPPs in Sweden
Link to PIRT:  
References: [1] J.A. Zambaux, L. Manickam, R. Meignen, W. Ma, S. Bechta, S. Picchi. Study on thermal fragmentation characteristics of a superheated alumina droplet. Annals of Nuclear Energy 119 (2018) 352–361. [2] J.A. Zambaux, et al. Investigation of Material Effect Related to Steam Explosion in MESTEE (MISTEE-Al). Report SAFEST-DRI-D3.2.1.
[2] H. S. Park and T. N. Dinh, Ex-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors, Royal Institute of Technology, Sweden, April 2007
IP/Copyright Situation: None
Organization / Localization: KTH-NPS
Facility Description: It consists of an interaction chamber, an induction melt furnace, an external trigger system, an operational control system, and data acquisition and visualization systems. The test section is a rectangular tank (180x130x250mm) with 4 view windows (70x150x24mm) with a 1kW immersion heater.
Test Identification: MISTEE-Zr
SA-Related Topics / Phenomena: Zr droplet oxidation in water
Measured Parameters: Volume of hydrogen release. Zr oxidation degree.
Modelling:  
Simulation Code:  
Experimental Research Program: National program "Accident Phenomena of Risk Importance" (APRI) supported by consortium of SSM and NPPs in Sweden
Link to PIRT:  
References: [1] L. Manickam, Q. Guo, A. Komlev, W. Ma, S. Bechta. Oxidation of molten zirconium droplets in water. Nuclear Engineering and Design 354 (2019) 110225
[2] H. S. Park and T. N. Dinh, Ex-Vessel Coolability and Energetics of Steam Explosions in Nordic Light Water Reactors, Royal Institute of Technology, Sweden, April 2007
IP/Copyright Situation: None




Implemented as part of the Seaknot EU funded project (HORIZON-EURATOM-2021-NRT-01 under Grant Agreement No. 101060327) - WP2.6 UNIPI (2024-2026)