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April 5, 2013
Published Online: 2013-04-05
Published in Print: 2008-03-01
© 2008, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Analysis of the hydrogen behaviour in compartments of the Ignalina nuclear power plant
- Determination of the RBMK-1500 reactor passport characteristics
- Technical feasibility of using RU-43 fuel in the CANDU-6 reactors of the Cernavoda NPP
- Computational study of moderator flow and temperature fields in the calandria vessel of a heavy water reactor using the PHOENICS code
- Regulatory requirements on level 2 PSA in Germany and their associated potential to improve emergency management
- Dynamic structure response due to reactor cooling piping system failure
- Uncertainty in activation cross-section calculations at intermediate proton energies
- The LTSN solution of the transport equation for one-dimensional cartesian geometry with c = 1
- Application of the UN approximation to the neutron transport equation in slab geometry
- The reflected critical slab problem for one-speed neutrons with strongly anisotropic scattering
- The analytical representation of the fundamental mode in 1-D-geometry for the CANDLE burn-up phenomenon