Skip to main content
Log in

An old issue and a new challenge for nuclear reactor safety

  • Short Communication
  • Published:
Frontiers in Energy Aims and scope Submit manuscript

Abstract

Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: these are based on, among the other things, long lasting research and operational experience in the area of water cooled nuclear reactors (WCNR). Large break loss of coolant accident (LBLOCA) has been, so far, the orienting scenario within AA and a basis for the design of reactors. An incomplete vision for those technologies during the last few years is as follows: Progress in fundamentals was stagnant, namely in those countries where the WCNR were designed. Weaknesses became evident, noticeably in relation to nuclear fuel under high burn-up. Best estimate plus uncertainty (BEPU) techniques were perfected and available for application. Electronic and informatics systems were in extensive use and their impact in case of accident becomes more and more un-checked (however, quite irrelevant in case of LBLOCA). The time delay between technological discoveries and applications was becoming longer. The present paper deals with the LBLOCA that is inserted into the above context. Key conclusion is that regulations need suitable modification, rather than lowering the importance and the role of LBLOCA. Moreover, strengths of emergency core cooling system (ECCS) and containment need a tight link.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

References

  1. D’Auria F. Nuclear fission: from E. Fermi to Adm. Rickover, to industrial exploitation, to nowadays challenges. Journal of Advancement in Scientific and Engineering Research, 2019, 4(1): 17–30

    Google Scholar 

  2. US AEC. Interim Acceptance Criteria (IAC) for ECCS. Washington D.C., USA, 1971

  3. USNRC. Reactor safety study-an assessment of accident risk in U.S. commercial nuclear power plants, WASH-1400, NUREG-75/014, Washington D.C., USA, 1975

  4. IAEA. Deterministic safety analysis for nuclear power plants, SSG-2-rev1. Vienna, Austria, 2019

  5. Mazzantini O, Galassi G, D’Auria F. The role of nuclear thermal-hydraulics in the licensing of Atucha-II: the LBLOCA. Nuclear Engineering and Design, 2019, 351: 33–59

    Article  Google Scholar 

  6. USNRC. Regulatory Guide 1.222-Measuring breakaway oxidation behavior. Washington D.C., USA, 2018

  7. USNRC. Regulatory Guide 1.223-Determining post quench ductility, Washington. D.C., USA, 2018

  8. USNRC. Regulatory Guide 1.224-Preliminary draft (Draft was issued as DG-1263, dated March 2014), establishing analytical limits for zirconium-Alloy cladding material. Washington D.C., USA, 2018

  9. D’Auria F, Debrecin N, Glaeser H. Strengthening nuclear reactor safety and analysis. Nuclear Engineering and Design, 2017, 324: 209–219

    Article  Google Scholar 

  10. D’Auria F, Debrecin N, Glaeser H. The technological challenge for current generation nuclear reactors. Nuclear Energy and Technology, 2019, 5(3): 183–199

    Article  Google Scholar 

  11. Zhang J, Schneidesch C. Application of BEPU safety analysis methods to quantify margins in Belgian nuclear power plants. In: OECD/NEA/CSNI specialists meeting on transient thermal-hydraulics in water cooled nuclear reactors (SM-TH), Madrid, Spain, 2020

  12. Kim J, Cho S, Park J K, et al. Experimental study to assess effects of ballooning and fuel relocation on the coolability of fuel rod bundle. Nuclear Engineering and Design, 2018, 332: 1–10

    Article  Google Scholar 

  13. Glantz T, Taurines T, De Luze O, et al. DRACCAR: a multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients part one: general modeling description. Nuclear Engineering and Design, 2018, 339: 269–285

    Article  Google Scholar 

  14. Glantz T, Taurines T, Belon S, et al. DRACCAR: a multi-physics code for computational analysis of multi-rod ballooning, coolability and fuel relocation during LOCA transients. Part Two: overview of modeling capabilities for LOCA. Nuclear Engineering and Design, 2018, 339: 202–214

    Article  Google Scholar 

  15. D’Auria F. Best estimate plus uncertainty (BEPU): status and perspective. Nuclear Engineering and Design, 2019, 352: 110190

    Article  Google Scholar 

Download references

Acknowledgements

This paper was supported by the Institutional Funds of University of Pisa, Italy

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to F. D’Auria.

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

D’Auria, F. An old issue and a new challenge for nuclear reactor safety. Front. Energy 15, 854–859 (2021). https://doi.org/10.1007/s11708-021-0729-0

Download citation

  • Received:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s11708-021-0729-0

Keywords

Navigation