simulate severe accident conditions in a nuclear reactor by melting and solidifying prototypical corium
Concrete crack dimensions, pressure drop, gas temperature, aerosol concentration and composition.
~3033K for ~50 minutes. Ar-2%H2 reducing atmosphere
EURATOM 5th Framework Programme project relative
to the “Transnational Access to the PLINIUS platform”
References: [1] NEA, «Containment Code Validation Matrix», OECD Publishing, 2014, Paris
[2] S. Morandi et al., Aerosol retention in containment leak paths: indications for a code model in the light of COLIMA experimental results, Eur. Rev. Mtg., Severe Acc. Res., ERMSAR 2012, Cologne, Germany, March 2012.
[3] F. Parozzi et al., «Investigation on aerosol transport in containment cracks». Proceedings of the International Conference Nuclear Energy for New Europe 2005, Slovenia
[4] F. Parozzi, et al., «The COLIMA experiment on aerosol retention in containment leak paths under severe nuclear accidents», Nuclear Engineering and Design, vol. 261, p. 346-351, 2013,
https://doi.org/10.1016/j.nucengdes.2012.12.012.
[5] C. Journeau et al., «The PLINIUS/COLIMA CA-U3 test on fission-product aerosol release over a VVER-type corium pool»,
https://inis.iaea.org/collection/NCLCollectionStore/_Public/39/093/39093483.pdf
https://doi.org/10.1016/j.nucengdes.2010.01.008Comments: Comparison with ASTEC/ELSA