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Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant

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Published/Copyright: June 26, 2015
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Kerntechnik
From the journal Kerntechnik Volume 80 Issue 3

Abstract

The feedback from the accident at the Fukushima-Daiichi nuclear power plant is crucial for defining and implementing measures for preventing accidents involving large releases of radioactive material at nuclear installations, including nuclear fuel cycle facilities. Following the lessons learned from this accident, assessment of the safety of nuclear fuel cycle facilities is essential to evaluate the robustness of the facilities' protection systems and components against the impact of extreme external events. A methodology to perform this safety assessment is presented, with discussions on possible preventive measures to be applied and mitigatory actions to be taken for further improvement of the robustness of nuclear fuel cycle facilities when subjected to extreme external events. Considerations in the assessment of multi-facility sites and use of a graded approach, commensurate with the facility's potential hazard, in application of the safety assessment methodology are also discussed.

Kurzfassung

Das Feedback nach dem Unfall im Kernkraftwerk Fukushima-Daiichi ist entscheidend für die Bestimmung und Umsetzung von Maßnahmen zur Vermeidung von Unfällen mit Freisetzung großer Mengen radioaktiver Stoffe bei kerntechnischen Anlagen. Nach den Erfahrungen aus diesem Unfall ist die Sicherheitsbewertung einer solchen Anlage von großer Bedeutung, insbesondere die Bewertung der Robustheit der Schutzsysteme der Anlage und ihrer Komponenten gegen die Aus-wirkungen extremer externer Ereignisse. Eine Methodik zur Durchführung dieser Sicherheitsbewertung wird vor-gestellt einschließlich der Diskussion möglicher Vorsorge-maßnahmen und Aktivitäten zur Schadensminderung, die zur Verbesserung der Robustheit der Anlage im Falle extremer externer Ereignisse führen. Ein abgestuftes Verfahren, entsprechend dem Gefahrenpotential der Anlage, wird bei der An-wendung der Methodik zur Sicherheitsbewertung ebenfalls diskutiert.

References

1 International Atomic Energy Agency: Safety of Fuel Cycle Facilities, IAEA Safety Standards Series No. NS-R-5 (Rev.1), IAEA, Vienna, 2014.Search in Google Scholar

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Received: 2015-01-23
Published Online: 2015-06-26
Published in Print: 2015-07-25

© 2015, Carl Hanser Verlag, München

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Improved data evaluation methodology for energy ranges with missing experimental data
  7. Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
  8. Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
  9. The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
  10. Development of a hydrogen diffusion gothic model of MARK III-containment
  11. Analysis of safety parameters for the MINERVE reactor
  12. Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
  13. Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
  14. Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
  15. Study of 60Co as gamma source in backscatter gamma densitometers
  16. Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
  17. Technical Notes
  18. Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
https://doi.org/10.3139/124.110486

Articles in the same Issue

  1. Contents/Inhalt
  2. Contents
  3. Summaries/Kurzfassungen
  4. Summaries
  5. Technical Contributions/Fachbeiträge
  6. Improved data evaluation methodology for energy ranges with missing experimental data
  7. Importance weighting of local flux measurements to improve reactivity predictions in nuclear systems
  8. Safety assessment of fuel cycle facilities following the lessons learned from the accident at the Fukushima-Daiichi nuclear power plant
  9. The ultimate response guideline simulation and analysis by using TRACE for Lungmen ABWR nuclear power plant
  10. Development of a hydrogen diffusion gothic model of MARK III-containment
  11. Analysis of safety parameters for the MINERVE reactor
  12. Nondestructive radioactive tracer technique in performance evaluation of organic based ion exchange materials Purolite NRW-4000 and Duolite A-378
  13. Neutronic performance of (ReprocessedU/Th)O2 fuel in CANDU 6 reactor
  14. Modelling study on production cross sections of 111In radioisotopes used in nuclear medicine
  15. Study of 60Co as gamma source in backscatter gamma densitometers
  16. Determination of activity concentration of natural and artificial radionuclides in sand samples from mediterranean coast of Antalya in Turkey
  17. Technical Notes
  18. Numerical solution of diffusion equation to study fast neutrons flux distribution for variant radii of nuclear fuel pin and moderator regions
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