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Published/Copyright: April 6, 2013
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Kerntechnik
From the journal Kerntechnik Volume 71 Issue 4

Published Online: 2013-04-06
Published in Print: 2006-08-01

© 2006, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
  7. Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
  8. Determination of the exposure build-up factor in a slab using the LTSN method
  9. Lumped parameters analysis of the IAEA research reactor benchmark problem
  10. Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
  11. A finite element model for static strength analysis of CANDU fuel bundle
  12. Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
  13. Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
  14. Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
  15. Analyses of severe accident scenarios in RBMK-1500
https://doi.org/10.3139/124.060403

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
  7. Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
  8. Determination of the exposure build-up factor in a slab using the LTSN method
  9. Lumped parameters analysis of the IAEA research reactor benchmark problem
  10. Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
  11. A finite element model for static strength analysis of CANDU fuel bundle
  12. Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
  13. Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
  14. Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
  15. Analyses of severe accident scenarios in RBMK-1500
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