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Blankets – key element of a fusion reactor – functions, design and present state of development

  • K. Hesch , L. V. Boccaccini and R. Stieglitz
Published/Copyright: June 8, 2018
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Received: 2018-03-13
Published Online: 2018-06-08
Published in Print: 2018-06-18

© 2018, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Editorial
  4. 2nd Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
  5. Technical Contributions/Fachbeiträge
  6. Challenging issues and recent R&D activities for enhancing nuclear safety in Korea
  7. Necessary improvements of the GRS simulation chain for the simulation of light-water-cooled SMRs
  8. Scaling analysis of core pressure drop in reduced height integral test facility
  9. Criteria and comparison of thermal stratification between PRHR HX heating and ADS spraying process in IRWST based on a down-scaled experimental facility
  10. Numerical simulation of bubble growth on and departure from the heated surface by an improved lattice Boltzmann model
  11. Improvements of interfacial friction and heat transfer models for rectangular narrow channel reflood simulation based on RELAP5
  12. Proposal of a novel CHF correlation for PWR under low pressure conditions based on stepwise regression method
  13. Mechanistic prediction of post dryout heat transfer and rewetting
  14. Investigation of condensation process at COSMEA test facility with ATHLET code
  15. Research on thermal-hydraulic behavior in the spent fuel pool using a full-height experimental facility
  16. Experimental investigation on the distribution of spray water in a spent fuel-assembly simulator
  17. Wet resuspension modelling and validation
  18. Analysis code development for the direct reactor auxiliary cooling system of the pool-type sodium-cooled fast reactor
  19. Comparison of heat transfer models with databank of supercritical fluid
  20. Blankets – key element of a fusion reactor – functions, design and present state of development
  21. Preliminary steady and transient analysis for the CFETR helium cooled solid blanket system with RELAP
  22. A methodology for thermo-mechanical assessment of in-box LOCA events on fusion blankets and its application to EU DEMO HCPB breeding blanket
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