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Veröffentlicht/Copyright: 26. März 2013
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Kerntechnik
Aus der Zeitschrift Kerntechnik Band 71 Heft 5-6

Published Online: 2013-03-26
Published in Print: 2006-11-01

© 2006, Carl Hanser Verlag, München

Artikel in diesem Heft

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Minor actinide burning in a CANDU thorium reactor
  7. Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS
  8. Thermal-hydraulic modeling of the onset of flow instability in MTR reactors
  9. 10.3139/124.100302
  10. 10.3139/124.100304
  11. Radiation transfer in inhomogeneous exponential media
  12. Neutron transport problems for extremely anisotropic scattering
  13. Milne problem for isotropic and linearly anisotropic scattering for specular and diffuse reflecting boundary conditions solved with the HN method
  14. ICDE-results on complete common cause failures in the light of results obtained with the POS model
  15. Modelling of the cumulative behaviour of Caesium and Strontium activities in nuclear fuel
  16. Analytical study of the closure flow inside the ETRR-2 core chimney
  17. Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor
https://doi.org/10.3139/124.060503

Artikel in diesem Heft

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Minor actinide burning in a CANDU thorium reactor
  7. Modeling of the TOSQAN test facility with the lumped parameter code COCOSYS
  8. Thermal-hydraulic modeling of the onset of flow instability in MTR reactors
  9. 10.3139/124.100302
  10. 10.3139/124.100304
  11. Radiation transfer in inhomogeneous exponential media
  12. Neutron transport problems for extremely anisotropic scattering
  13. Milne problem for isotropic and linearly anisotropic scattering for specular and diffuse reflecting boundary conditions solved with the HN method
  14. ICDE-results on complete common cause failures in the light of results obtained with the POS model
  15. Modelling of the cumulative behaviour of Caesium and Strontium activities in nuclear fuel
  16. Analytical study of the closure flow inside the ETRR-2 core chimney
  17. Minimizing radiation exposure for the reactor staff during the dismantling of a TRIGA research reactor
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