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Aus der Zeitschrift Kerntechnik Band 71 Heft 4

"Summaries" Kerntechnik, vol. 71, no. 4, 2006, pp. 160-162. https://doi.org/10.3139/124.060403

(2006). Summaries. Kerntechnik, 71(4), 160-162. https://doi.org/10.3139/124.060403

(2006) Summaries. Kerntechnik, Vol. 71 (Issue 4), pp. 160-162. https://doi.org/10.3139/124.060403

"Summaries" Kerntechnik 71, no. 4 (2006): 160-162. https://doi.org/10.3139/124.060403

Summaries. Kerntechnik. 2006;71(4): 160-162. https://doi.org/10.3139/124.060403

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Published Online: 2013-04-06

Published in Print: 2006-08-01

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Artikel in diesem Heft

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 LTS_N 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

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https://doi.org/10.3139/124.060403

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 LTS_N 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