The Working Group on Analysis and Management of Accidents (WGAMA) held the first in-person meeting of the Task Group on the Update and Extension of the CSNI Code Validation Matrix (CCVM) for reactor coolant system and containment thermal-hydraulic phenomena, including for current and advanced water-cooled reactors and small modular reactors (SMRs), on 11–12 September 2025 at the OECD Nuclear Energy Agency (NEA) headquarters in Boulogne-Billancourt, France, and online.
A total of 42 participants from a wide range of institutions attended the event, reflecting the strong engagement and collaborative spirit of the CCVM community.
The meeting opened with welcoming remarks and an introduction by task group leader Fulvio Mascari (ENEA). The technical programme included:
- Reactor coolant system (RCS) topics led by Seok Kim (KAERI), covering reactor pressure vessel, chemistry, loops and pumps, steam generators, pressurisers, safety systems (active and passive), and integral system phenomena;
- Containment phenomena chaired by Ahmed BENTAIB (ASNR), with presentations on thermal-hydraulics, combustible gas behaviour, aerosol and fission product behaviour, and chemistry phenomena; and
- Reactor group sessions focusing on BWRX-300, LDR-50, BWR/ABWR, and other advanced reactor designs.
The meeting concluded with a summary of actions and decisions, and plans for continued progress, fostering in-depth technical exchanges and collaborative work.
The CCVM meeting marks a significant step forward in the international effort to advance code validation for both current and advanced nuclear technologies.
For more information, please contact:
- Martina ADORNI (NEA): martina.adorni@oecd-nea.org
