ACTIVITIES OF THE GIF SAFETY AND OPERATION PROJECT OF SODIUM-COOLED FAST REACTOR SYSTEMS

The Generation IV (GEN-IV) international forum is a framework for international co-operation in research and development for the next generation of nuclear energy systems. Within the GEN-IV sodium-cooled fast reactor (SFR) system arrangement, the SFR Safety and Operation (SO) project addresses the areas of safety technology and reactor operation technology developments. The aim of the SO project includes (1) analyses and experiments that support establishing safety approaches and validating performance of specific safety features, (2) development and verification of computational tools and validation of models employed in safety assessment and facility licensing, and (3) acquisition of reactor operation technology, as determined largely from experience and testing in operating SFR plants. The tasks in the SO topics are categorized into the following three work packages (WP): WP-SO-1 “Methods, Models and Codes” is devoted to the development of tools for the evaluation of safety. WP-SO-2 “Experimental Programs and Operational Experience” includes the operation, maintenance and testing experiences in experimental facilities and SFRs (e.g., Monju, Phenix, BN-600, EBR-II and CEFR), and WP-SO-3 “Studies of Innovative Design and Safety Systems” relates to safety technologies for GEN-IV reactors such as active and passive safety systems and other specific design features. This paper reports recent activities within the SO project.

YAMANO Hidemasa;  VASILE A.;  KANG Seok-Hun;  SUMMER Tyler;  TSIGE-TAMIRAT Haileyesus;  WANG Jin;  ASHURKO I.; 

2019-12-05

ASME

JRC113793

https://www.icone27.org/,    https://publications.jrc.ec.europa.eu/repository/handle/JRC113793,