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April 6, 2013
Published Online: 2013-04-06
Published in Print: 2006-08-01
© 2006, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- The multipurpose thermalhydraulic test facility TOPFLOW: an overview on experimental capabilities, instrumentation and results
- Uncertainty in cross-section calculations for reactions induced by neutrons with energy above 0.1 MeV
- Determination of the exposure build-up factor in a slab using the LTSN method
- Lumped parameters analysis of the IAEA research reactor benchmark problem
- Assessment of the look-up table using the tubular and bundle CHF data and modification of the bundle correction factor
- A finite element model for static strength analysis of CANDU fuel bundle
- Effect of packing fraction variations on the multiplication factor in pebble-bed nuclear reactors
- Design of a dry cask storage system for spent LWR fuels: radiation protection, subcriticality, and heat removal aspects
- Radiological and thermal characteristics of CASTOR RBMK-1500 and CONSTOR RBMK-1500 casks for spent nuclear fuel storage at Ignalina Nuclear Power Plant
- Analyses of severe accident scenarios in RBMK-1500