Main outcomes of OECD/NEA THAI-2 project and its use for code validation and containment safety assessment under accident conditions - IRSN - Institut de radioprotection et de sûreté nucléaire
Communication Dans Un Congrès Année : 2023

Main outcomes of OECD/NEA THAI-2 project and its use for code validation and containment safety assessment under accident conditions

Résumé

During a core-melt accident, apart from hydrogen, radioactive gases and aerosols are released into the containment, the behaviour of which is of significant importance for determining the radiological source term. The investigation on in-containment combustible gases and fission product behaviour was subject of the OECD/NEA THAI-2 project conducted during 2011 -2014. The project focused on experiments on hydrogen behaviour i.e., deflagration in the presence of spray and mitigation by passive autocatalytic recombiners (PAR), on the interaction of molecular iodine with reactive and non-reactive aerosol particles to assess the effect on a potential source term, and on the quantification of the release of gaseous iodine from a flashing jet, representing a PWR steam generator tube rupture during reactor shutdown. The project was supported by 11 countries involving safety organizations, research laboratories and industries.

The experimental programme of the OECD/NEA THAI-2 project strongly contributed to the validation and further development of advanced lumped parameter and computational fluid dynamic codes used for reactor applications by e. g. providing experimental data for code benchmark exercises. The present paper summarizes main findings of the project together with highlighting their importance for mitigation of hydrogen risk and source term related issues. Furthermore, use of project results by the project partners for code validation and reactor analyses towards management and mitigation of a severe accident in light water reactors is discussed with selected examples.

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irsn-04858196 , version 1 (29-12-2024)

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  • HAL Id : irsn-04858196 , version 1

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Gupta S., Freitag M., Liang Z., Funke F., Langrock G., et al.. Main outcomes of OECD/NEA THAI-2 project and its use for code validation and containment safety assessment under accident conditions. 20th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-20), American Nuclear Society (ANS), Aug 2023, Washignton DC, United States. ⟨irsn-04858196⟩

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