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21. Mai 2019
Published Online: 2019-05-21
Published in Print: 2019-06-17
© 2019, Carl Hanser Verlag, München
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Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Revision of a CHF correlation for PWR under low pressure conditions with only dimensionless parameters as independent variables
- Experimental study on transient flow fluctuation characteristics in a 3 × 3 rod bundle under rolling condition
- The core shroud leakage analysis and study for Kuosheng nuclear power plant
- Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
- Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
- 10.3139/124.110984
- Control rod material effect on safety parameters of research reactors
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Technical Contributions/Fachbeiträge
- Revision of a CHF correlation for PWR under low pressure conditions with only dimensionless parameters as independent variables
- Experimental study on transient flow fluctuation characteristics in a 3 × 3 rod bundle under rolling condition
- The core shroud leakage analysis and study for Kuosheng nuclear power plant
- Coupling simulation of neutron kinetics core model with CFD of IPWR steam line break accident
- Numerical prediction of single-phase flow mixing characteristics in a 1/12th of the cross segment of a 54-rod bundle
- 10.3139/124.110984
- Control rod material effect on safety parameters of research reactors
