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Model validation of the ASTERIA-FBR code related to core expansion phase based on THINA experimental results

Jun 27, 2017, 5:30 PM
1h 30m
Poster Area (Yekaterinburg)

Poster Area


POSTER Track 3. Fast Reactor Safety Poster Session 1


Dr Tomoko Ishizu (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))


Mechanical consequences which might be caused by core disruptive accidents (CDAs) are one of the major concerns in FBR safety. Once a severe re-criticality occurs, core materials are vaporized creating a CDA bubble which consists of fuel vapor, steel vapor and fission gases. Rapid expansion of the CDA bubble drives a sodium slug of the upper plenum and threatens integrity of the shielding plug. Energy conversion from thermal energy to mechanical energy plays an important role for the boundary integrity during core expansion phase. This paper describes model validation study of ASTERIA-FBR* related to the thermal-to-mechanical energy conversion process, focusing on calculation models such as interfacial area model through the THINA** test simulation. As a result, it was found that the energy conversion process and its ratio were in good agreements with the experimental results. Mechanism of CDA bubble expansion and uncertainty brought by calculation models were also discussed. [References] *T.Ishizu,, “Development of Integrated Core Disruptive Accident Analysis Code for FBR –ASTERIA-FBR,” Proceedings of ICAPP’12, Chicago, USA, June 24-28, 2012, Paper 12100. **F. Huber,, “Experiments on the Behaviour of Thermite Melt Injected into Sodium –Final Report on the THINA Tests Results,” Proceedings of IAEA/IWGFR Technical Committee Meeting on Material-Coolant Interactions and Material Movement and Relocation in Liquid Metal Fast Reactors, 167-198, Oarai, Japan, 1994.

Country/Int. Organization


Primary author

Dr Tomoko Ishizu (Regulatory Standard and Research Department, Secretariat of Nuclear Regulation Authority (S/NRA/R))

Presentation materials