Contents

Articles in the same Issue

1. Contents/Inhalt
2. Contents
3. Editorial
4. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2018
5. Technical Contributions/Fachbeiträge
6. Development of CASMO5 for VVER-1000/1200 analysis and preliminary validation using critical experiments
7. C-PORCA 7: a nodal diffusion reactor calculation code to support off-line and on-line core analysis at Paks nuclear power plant
8. Adaptation of the gas gap simplified model in DYN3D code to new types of fuel
9. A procedure for verification of Studsvik's spent nuclear fuel code SNF
10. Extension of nodal diffusion solver of Ants to hexagonal geometry
11. VVER-1000 fuel assembly model in CAD-based unstructured mesh for MCNP6
12. Fuel cycles with PK-3+ FAs for VVER-440 reactors
13. Prospects for implementation of VVER nuclear fuel enriched above 5%
14. Core loading optimisation in Slovak VVER-440 reactors
15. Statistical evaluation of C-15 cycles in Paks NPP, based on measured in-core data
16. Optimized 18-months low-leakage core loadings for uprated VVER-1000
17. Leningrad NPP-2 start-up loss of power test and its simulation with use of KORSAR/GP code
18. Assessment of the fuel assembly pin-by-pin model in the KORSAR/GP code
19. Comparative thermohydraulic analyses of VVER 1000 active core for two different construction types of assemblies
20. Analysis of uncontrolled dilution of boric acid concentration in the reactor VVER-1000/320
21. Applied study on optimizing the final disposal of Loviisa NPP spent fuel assemblies
22. Criticality safety analysis for GNS IQ® – The Integrated Quiver System for damaged fuel
23. Neutron balance in two-component nuclear energy system