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Published/Copyright: August 18, 2017
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Published Online: 2017-08-18
Published in Print: 2017-09-01

© 2017, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Editorial
  6. Research on the reactor physics and reactor safety of VVER reactors – AER Symposium 2016
  7. Technical Contributions/Fachbeiträge
  8. Physical startup tests for VVER-1200 of Novovoronezh NPP: advanced technique and some results
  9. Experimental study of asymmetric boron dilution at VVER-1000 of Kudankulam NPP and its simulation
  10. Study on the impact of transition from 3-batch to 4-batch loading at Loviisa NPP on the long-term decay heat and activity inventory
  11. New engineering safety factors for Loviisa NPP core calculations
  12. Development of fuel cycles with new fuel with 8.9 mm external diameter for VVER-440: Preliminary assessment of operating efficiency
  13. Investigation of circulating temperature fluctuations of the primary coolant in order to develop an enhanced MTC estimator for VVER-440 reactors
  14. Recalculating the steady state conditions of the V-1000 zero-power facility at Kurchatov Institute using Monte Carlo and nodal diffusion codes
  15. Start-up of a cold loop in a VVER-440, the 7th AER benchmark calculation with HEXTRAN-SMABRE-PORFLO
  16. Verification results of methodology for determining the weighted mean coolant temperature in the primary circuit hot legs of WWER-1000 reactor plants
  17. Advances in HELIOS2 nuclear data library
  18. ANDREA 2.2 and 2.3 – Advances in modelling of VVER cores
  19. CFD analyses of the rod bowing effect on the subchannel outlet temperature distribution
  20. A methodology for the estimation of the radiological consequences of a Loss of Coolant Accident
  21. Neutron balance as indicator of long-term resource availability in growing nuclear energy system
  22. Analysis of changes in the fuel component of the cost of electricity in the transition to a closed fuel cycle in nuclear power system
  23. Experimental and numerical thermal-hydraulics investigation of a molten salt reactor concept core
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