Contents

Artikel in diesem Heft

1. Contents/Inhalt
2. Contents
3. Editorial
4. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2017
5. Technical Contributions/Fachbeiträge
6. SIMULATE5-HEX extension for VVER analyses
7. Application of discontinuity factors and group constants generated by SERPENT in the KIKO3 DMG code
8. “Full-Core” VVER-440 extended calculation benchmark
9. Calculation of “full core” VVER-1000 benchmark
10. Study of neutron-physical characteristics of VVER-1200 considering feedbacks using MCU Monte Carlo code
11. Advantages of VVER-440 fuel cycles with new fuel assemblies
12. A neutronics feasibility study on utilization of a thinned cladding fuel design at Loviisa NPP
13. Investigation of fuel cycles containing Generation IV reactors and VVER-1200 reactors
14. Calculations of spent fuel isotopic composition for fuel rod from VVER-440 fuel assembly benchmark using several evaluated nuclear data libraries
15. Simulation of standard temperature control indications at the outlet of a fuel assembly of VVER1000 reactor of Rostov NPP unit No. 2
16. Power transient calculations with VERONA
17. Physical startup tests calculations for Dukovany NPP using MOBY-DICK macrocode
18. Renewing the refueling neutron monitoring and reactivity measurement systems at Paks NPP
19. Hot channel calculation methodologies in case of VVER-1000/1200 reactors
20. Contribution to the validation of the VVER-1000 Temelin NPP computing model for the ATHLET/DYN3D coupled codes
21. Simulation of a hypothetical MSLB core transient in VVER-1000 with several stuck rods