Contents

Articles in the same Issue

1. Contents/Inhalt
2. Contents
3. Summaries/Kurzfassungen
4. Summaries
5. Editorial
6. Editorial
7. Technical Contributions/Fachbeiträge
8. Highly enriched alternatives of VVER-440 fuel assembly
9. “FULL-CORE” VVER-440 calculation benchmark
10. Development of approximation method to evaluate isotopic composition of burnt fuel
11. Fuel assembly burnup calculations for VVER fuel assemblies with the MONTE CARLO code SERPENT
12. Solution of the CB6 benchmark on VVER-440 final disposal using the Serpent reactor physics code
13. Development and verification of new nodal methods in the KIKO3DMG code
14. HPLWR fine mesh core analysis
15. Assessment of reactor scram effectiveness based on measured worth of separate CR groups
16. Engineering factors of the macrocode MOBY-DICK
17. CFD investigation of flow in the MATIS-H test facility
18. Investigation of the hot-channel calculation methodology in case of shroud-less assemblies
19. Assessment of the uncertainties of COBRA sub-channel calculations by using a PWR type rod bundle and the OECD NEA UAM and the PSBT benchmarks data
20. Comparison analysis of effectiveness of diagnostic methods of local coolant boiling in WWER core
21. Sensitivity of hydrodynamic parameters' distributions in VVER-1000 reactor pressure vessel (RPV) with respect to uncertainty of the local hydraulic resistance coefficients