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20. Oktober 2017
Published Online: 2017-10-20
Published in Print: 2017-10-26
© 2017, Carl Hanser Verlag, München
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Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Modelling Human Resource Requirements for the Nuclear Industry in Europe
- Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
- The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
- Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
- Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
- The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
- Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
- Anti-neutrino flux in a research reactor for non-proliferation application
- Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
- Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
- Internal and external hazards inside the containment in case of an emergency situation
- Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Modelling Human Resource Requirements for the Nuclear Industry in Europe
- Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis
- The integrity of NSSS and containment during extended station blackout for Kuosheng BWR plant
- Experimental investigation of effect of spacer on two phase turbulent mixing rate in subchannels of pressure tube type BWR
- Thermal-hydraulic analysis of research reactor core with different LEU fuel types using RELAP5
- The application of knowledge management and TRIZ for solving the safe shutdown capability of fire alarms in nuclear power plants
- Dose assessment for emergency workers in early phase of Fukushima Daiichi nuclear power plant accident
- Anti-neutrino flux in a research reactor for non-proliferation application
- Friction coefficient and limiter load test analysis by flexibility coefficient model of Hold-Down Spring of nuclear reactor vessel internals
- Robust observer based control for axial offset in pressurized-water nuclear reactors based on the multipoint reactor model using Lyapunov approach
- Internal and external hazards inside the containment in case of an emergency situation
- Slab albedo for linearly and quadratically anisotropic scattering kernel with modified FN method