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Aus der Zeitschrift Kerntechnik Band 81 Heft 1

"Summaries" Kerntechnik, vol. 81, no. 1, 2016, pp. 4-7. https://doi.org/10.3139/124.016014

(2016). Summaries. Kerntechnik, 81(1), 4-7. https://doi.org/10.3139/124.016014

(2016) Summaries. Kerntechnik, Vol. 81 (Issue 1), pp. 4-7. https://doi.org/10.3139/124.016014

"Summaries" Kerntechnik 81, no. 1 (2016): 4-7. https://doi.org/10.3139/124.016014

Summaries. Kerntechnik. 2016;81(1): 4-7. https://doi.org/10.3139/124.016014

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Published Online: 2016-03-11

Published in Print: 2016-03-16

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Artikel in diesem Heft

Contents/Inhalt
Contents
Summaries/Kurzfassungen
Summaries
Technical Contributions/Fachbeiträge
Stability analysis of the Korean prototype Generation-IV sodium-cooled fast reactor using linear frequency domain approach
Validation of RELAP5 model of experimental test rig simulating the natural convection in MTR research reactors
Steady state and transient analyses of MNSR reactor using RELAP5 code
Protactinium-231 as a new fissionable material for nuclear reactors that can produce nuclear fuel with stable neutron-multiplying properties
Assessment of pin-by-pin fission rate distribution within MOX/UO₂ fuel assembly using MCNPX code
Influence on rewetting temperature and wetting delay during rewetting rod bundle by various radial jet models
Experimental and numerical investigation on natural convection heat transfer in nanofluids
Experimental studies in a single-phase parallel channel natural circulation system: preliminary results
Calculation of PDS-XADS core closed-loop transfer function by using feedback with the lumped-model
Calculation of nuclear reactivity using the generalised Adams-Bashforth-Moulton predictor corrector method

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https://doi.org/10.3139/124.016014

Contents/Inhalt
Contents
Summaries/Kurzfassungen
Summaries
Technical Contributions/Fachbeiträge
Stability analysis of the Korean prototype Generation-IV sodium-cooled fast reactor using linear frequency domain approach
Validation of RELAP5 model of experimental test rig simulating the natural convection in MTR research reactors
Steady state and transient analyses of MNSR reactor using RELAP5 code
Protactinium-231 as a new fissionable material for nuclear reactors that can produce nuclear fuel with stable neutron-multiplying properties
Assessment of pin-by-pin fission rate distribution within MOX/UO₂ fuel assembly using MCNPX code
Influence on rewetting temperature and wetting delay during rewetting rod bundle by various radial jet models
Experimental and numerical investigation on natural convection heat transfer in nanofluids
Experimental studies in a single-phase parallel channel natural circulation system: preliminary results
Calculation of PDS-XADS core closed-loop transfer function by using feedback with the lumped-model
Calculation of nuclear reactivity using the generalised Adams-Bashforth-Moulton predictor corrector method