Open Access
EPJ Nuclear Sci. Technol.
Volume 7, 2021
Article Number 2
Number of page(s) 15
Published online 21 January 2021
  1. IEA/NEA (2015) Technology Roadmap: Nuclear Energy. Paris. [Google Scholar]
  2. UNFCCC Secretariat, Aggregate effect of the intended nationally determined contributions: an update (2016), [Google Scholar]
  3. IAEA (2018) Advances in Small Modular Reactor Technology Developments 2018 Edition. [Google Scholar]
  4. B. Petrovic, The integral inherently safe light water reactor, Nucl. Eng. Int. (2014), [Google Scholar]
  5. B. Petrovic, F. Rahnema, C. Deo, S. Garimella, P. Singh, K. Oh, C. Yi, D. Zhang, A. Manera, J. Lee, T. Downar, A. Ward, P. Ferroni, F. Franceschini, D. Salazar, B. Upadhyaya, M. Lish, I. Charit, A. Haghighat, M. Memmott, G. Boy, A. Ougouag, G. Parks, D. Kotlyar, M. Ricotti, Č. Nikola, D. Grgi, D. Pevec, M. Matijevi, N. Irvin, I2S-LWR concept update, in Proceedings of The 20th Pacific Basin Nuclear Conference , edited by H. Jiang (China Nuclear Power Engineering Co, Ltd, Beijing), (Springer, Singapore, 2016), pp. 153– 167 [Google Scholar]
  6. M.S. Ali, Evolution of the leak-before- break concept in nuclear plants: issues and resolutions in the process of regulatory actions, Nucl. Technol. 176, 442–451 (2011) [Google Scholar]
  7. R. Bourga, P. Moore, Y.-J. Janin, B. Wang, J. Sharples, Leak-before-break: global perspectives and procedures, Int. J. Press. Vessel. Pip. 129, 43–49 (2015) [CrossRef] [Google Scholar]
  8. P. Scott, R.J. Olson, G.M. Wilkowski, NUREG/CR-6765 Development of Technical Basis for Leak-Before-Break Evaluation Procedures (2002), Office of Nuclear Regulatory Research, USNRC, Washington DC, 20555-0001, [Google Scholar]
  9. T. Deighton, Liquid Moderated Nuclear Reactor. US 3,356,583 (1967) [Google Scholar]
  10. H. Neumann, Vom Forschungsreaktor zum ≫ Atomschiff ≪ OTTO HAHN, 1st edn. ed. (Verlag H.M. Hauschild, Bremen, Germany, 2009) [Google Scholar]
  11. J. Reinartz, Historie Als die Kernenergie “Ahoi” rief. NS Otto Hahn: Nuklearbetriebenes Forschungs-und Frachtschiff. atw Int. J. Nucl. Power 58, 652–656 (2013) [Google Scholar]
  12. IAEA, Stress Corrosion Cracking in Light Water Reactors: Good Practices and Lessons Learned, IAEA Nuclear Energy Series No. NP-T-3.13 (Vienna, 2011) [Google Scholar]
  13. D.C. Groeneveld, L.K.H. Leung, P.L. Kirillov, V.P. Bobkov, I.P. Smogalev, V.N. Vinogradov, X.C. Huang, E. Royer, The 1995 look-up table for critical heat flux in tubes, Nucl. Eng. Des. 163, 1–23 (1996) [CrossRef] [Google Scholar]
  14. B. Majborn, K. Brodersen, CF. Højerup, F. Heikel Vinther, editors, Risø National Laboratory Nuclear Safety Research Department Annual Progress Report 1992, Risø-R-679(EN) §3. 2. 6, p. 18, 1993 [Google Scholar]
  15. K. Hannerz, L. Nillson, T. Pedersen, C. Pind, The PIUS pressurized water reactor: aspects of plant operation and availability, Nucl. Technol. 91, 81–88 (1990) [CrossRef] [Google Scholar]
  16. J.M. Taylor, SECY-93-092-Issues pertaining to the advanced reactor (PRISM, MHTGR, and PIUS) and CANDU 3 designs and their relationship to current regulatory requirements (1993), [Google Scholar]
  17. F.W. Kleimola, Passive containment system for a nuclear reactor. US 3,984,282 (1976) [Google Scholar]
  18. N.M. Bonhomme, Containment for a water cooled and moderated nuclear reactor. US 9,502,142 (2016) [Google Scholar]
  19. G. Cénérino, Accidents graves des réacteurs à eau de production d'électricité, Rapport IRSN-2008/98-FR (2008) [Google Scholar]
  20. IAEA, Severe Accident Management Programmes for Nuclear Power Plants. Safety Guide No. NS-G-2.15, Safety Guide No. NS-G-2.15 (2009), [Google Scholar]
  21. USNRC, Standard review plan 19.0, NUREG-0800 (2015) [Google Scholar]
  22. H. Esmaili, M. Khatib-Rahbar, NUREG/CR-6849, ERI/NRC 046201. Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction for AP1000 (2004), [Google Scholar]
  23. IRSN, Eléménts de réfléxion sur la stratégié de réténtion d'un corium en cuve de réactéur (2015), [Google Scholar]
  24. T.G. Theofanous, C. Liu, S. Additon, S. Angelini, O. Kymäläinen, T. Salmassi, In-vessel coolability and retention of a core melt, DOE/ID-10460, VOLUME 1 (October 1996), [Google Scholar]

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