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Necessary improvements of the GRS simulation chain for the simulation of light-water-cooled SMRs

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Published/Copyright: June 8, 2018
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Kerntechnik
From the journal Kerntechnik Volume 83 Issue 3

Abstract

Small modular reactors (SMRs) are one interesting option for new builds in almost all countries worldwide continuing to use nuclear energy for commercial power generation. For asserting of legitimate nuclear safety and/or security interests German authorities require in this context own and independent expertise for the safety assessments. The Gesellschaft für Anlagen und Reaktorsicherheit (GRS) mbH, which is the main technical support organization in nuclear safety for the German federal government, has among others performed a study on Safety and International development of Small Modular Reactors (GRS-376) to identify essential issues of SMR safety as well as needs for adaption, improvement and validation of nuclear evidence tools developed and applied by GRS. For the light-water-cooled SMRs, which have (at least according to GRS) the best prospects for realization, selected results of this study will be presented.

Kurzfassung

Kleine modulare Reaktoren (SMRs) sind eine interessante Option für Neubauten speziell in den Ländern, die mit der kommerziellen Nutzung der Kernenergie zur Stromerzeugung fortfahren. Um legitime Interessen bzgl. der nuklearen Sicherheit bzw. Sicherung dieser Anlagen kompetent vertreten und international durchsetzen zu können, benötigen die deutschen Behörden eine eigene, unabhängige Expertise. Die Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) mbH ist die wichtigste nationale Sachverständigenorganisation der deutschen Bundesregierung. Sie hat in diesem Themenfeld die umfangreiche Studie Sicherheit und internationale Entwicklungen von kleinen modularen Reaktoren (GRS-376) erstellt und wichtige Fragen der Sicherheit von SMRs sowie weiteren Verbesserungs- und Validierungsbedarf für von der GRS in kerntechnischen Verfahren eingesetzte Simulationsprogramme identifiziert. Für die leichtwassergekühlten SMRs, die – zumindest nach Ansicht der GRS die besten Realisierungschancen besitzen – werden nachfolgend ausgewählte Ergebnisse dieser Studie präsentiert.

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References

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Received: 2018-01-20
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
https://doi.org/10.3139/124.110913

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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