Selected contributions from 1^th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology

Articles in the same Issue

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Editorial
6. Selected contributions from 1^th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
7. Technical Contributions/Fachbeiträge
8. Scientific codes developed and used at GRS – Nuclear simulation chain
9. Challenges on innovations of newly-developed safety analysis codes
10. Validation of system codes for plant application on selected experiments
11. Progress of Experimental Research on Nuclear Safety in NPIC
12. Severe accident research activities at Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
13. THAI experimental programme for containment safety assessment under severe accident conditions
14. A spray cooling technique for spent fuel assembly stored in pool
15. KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors
16. Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors
17. 10.3139/124.110680
18. Validation of the ATHLET-SC code by trans-critical transient data
19. Qualification of CFD-models for multiphase flows
20. The reactor dynamics code DYN3D
21. Critical flow phenomena and modeling in advanced nuclear safety technology
22. 10.3139/124.110682
23. Safety and security aspects in design of digital safety I&C in nuclear power plants
24. Thermohydraulic safety issues for liquid metal cooled systems
25. Design and safety analysis of the helium cooled solid breeder blanket for CFETR
26. Qualification of pebble fuel for HTGRs
27. High temperature reactors for cogeneration applications