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Published/Copyright: March 11, 2016
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Kerntechnik
From the journal Kerntechnik Volume 81 Issue 1

Published Online: 2016-03-11
Published in Print: 2016-03-16

© 2016, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Stability analysis of the Korean prototype Generation-IV sodium-cooled fast reactor using linear frequency domain approach
  7. Validation of RELAP5 model of experimental test rig simulating the natural convection in MTR research reactors
  8. Steady state and transient analyses of MNSR reactor using RELAP5 code
  9. Protactinium-231 as a new fissionable material for nuclear reactors that can produce nuclear fuel with stable neutron-multiplying properties
  10. Assessment of pin-by-pin fission rate distribution within MOX/UO2 fuel assembly using MCNPX code
  11. Influence on rewetting temperature and wetting delay during rewetting rod bundle by various radial jet models
  12. Experimental and numerical investigation on natural convection heat transfer in nanofluids
  13. Experimental studies in a single-phase parallel channel natural circulation system: preliminary results
  14. Calculation of PDS-XADS core closed-loop transfer function by using feedback with the lumped-model
  15. Calculation of nuclear reactivity using the generalised Adams-Bashforth-Moulton predictor corrector method
https://doi.org/10.3139/124.016014

Articles in the same Issue

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