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Steam drum level control studies of a natural circulation multi loop reactor

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Published/Copyright: January 8, 2014
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Kerntechnik
From the journal Kerntechnik Volume 78 Issue 6

Abstract

The proposed heavy water moderated and light water cooled pressure tube type boiling water reactor works on natural circulation at all power levels. It has parallel inter-connected loops with 452 boiling channels in the main heat transport system configuration. These multiple (four) interconnected loops influence the steam drum level control adversely through the common reactor inlet header. Alternate design studies made earlier for efficient control of SD levels have shown favorable results. This has lead to explore further the present scheme with the compartmentalization of CRIH into four compartments catering to four loops separately. The conventional 3-element level control has been found to be working satisfactorily. The interconnections between ECCS header and inlet header compartments have also increased the safety margin for various LOCA and design basis events. The paper deals with the SD level control aspects for this novel MHT configuration which has been analyzed for various PIEs (Postulated Initiating Events) and found to be satisfactory.

Kurzfassung

Der vorgeschlagene Schwerwasser-moderierte und Leichtwasser-gekühlte Siedewasserreaktor arbeitet mit Naturumlauf bei allen Leistungsstufen. Er hat parallele, mit einander verbundene Loops mit 453 Siedekanälen in der Hauptwärmetransport Systemkonfiguration. Diese multiplen, mit einander verbundenen Loops beeinflussen die Füllstandsregelung der Dampftrommel nachteilig durch den gemeinsamen Reaktor-Eintrittssammler. Verschiedene früher durchgeführte Auslegungsstudien für eine effektive Füllstandsregelung haben positive Ergebnisse gezeigt. Dies hat dazu geführt, das derzeitige Schema mit der Kompartimentierung des gemeinsamen Reaktor-Eintrittssammlers in vier Kompartimente, die die vier Loops getrennt versorgen. Die konventionelle Drei-Element-Füllstandsregelung arbeitet zufriedenstellend. Die gegenseitige Verbindung zwischen ECCS Sammler und Eintrittssammler-Kompartimenten haben auch den Sicherheitsspielraum für verschiedene LOCA und Auslegungsstörfälle erhöht. In dem Beitrag werden Fragestellungen der effektiven Füllstandsregelung für diese neue Hauptwärmetransport Systemkonfiguration behandelt, die für verschiedene PIEs (Postulated Initiating Events) analysiert wurde und als annehmbar gelten kann.

References

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Received: 2013-4-12
Published Online: 2014-01-08
Published in Print: 2013-12-19

© 2013, Carl Hanser Verlag, München

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  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Development of inflatable seals for the rotatable plugs of sodium cooled fast breeder reactors: a review – Part II: R&D necessities and development across the world
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  10. Calculation of the neutronic behavior of minor actinides burning in a thermal research reactor using the MCNPX 2.6 code
  11. Steam drum level control studies of a natural circulation multi loop reactor
  12. Analyses in regulatory practice
  13. Technical Notes/Technische Mitteilungen
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  15. Calculation of the critical thickness for one-speed neutrons in a reflected slab with backward and forward scattering using modified TN method
https://doi.org/10.3139/124.110359

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Development of inflatable seals for the rotatable plugs of sodium cooled fast breeder reactors: a review – Part II: R&D necessities and development across the world
  7. Analysis of radwaste management alternatives during dismantling of Ignalina NPP systems with low level contamination
  8. Calculation of excitation functions for the production of Cu and Co medical isotopes
  9. Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP
  10. Calculation of the neutronic behavior of minor actinides burning in a thermal research reactor using the MCNPX 2.6 code
  11. Steam drum level control studies of a natural circulation multi loop reactor
  12. Analyses in regulatory practice
  13. Technical Notes/Technische Mitteilungen
  14. Installation and measurement capacity of 3 × 592 GBq 241Am–Be neutron irradiation cell
  15. Calculation of the critical thickness for one-speed neutrons in a reflected slab with backward and forward scattering using modified TN method
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