Open Access
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
Article Number 07015
Number of page(s) 8
Section Transient Systems and Analysis
Published online 22 February 2021
  1. A. Gallais-During, F. Delage, S. Béjaoui, S. Lemehov, J. Somers, D. Freis, W. Maschek, S. Van Til, E. D’Agata, C. Sabathier, “Outcomes of the PELGRIMM project on Am-bearing fuel in pelletized and spherepac forms”, Journal of Nuclear Materials, 512, pp. 214–226 (2018). [Google Scholar]
  2. A. Rineiski, C. Meriot, M. Marchetti, J. Krepel, “Core Safety Measures in ESFR-SMART”, Proceedings of the PHYSOR 2018, Cancun, Mexico, April 22-26, 2018 (2018). [Google Scholar]
  3. U. Imke, D. Struwe, H. Niwa, I. Sato, F. Camous, D. Moxon, “Status of the SAS4A-code development for consequence analysis of core disruptive accidents”, Proceedings of an International Topical Meeting. Sodium Cooled Fast Reactor Safety, Obninsk, Russia, October 1994, pp. 232–241 (1994). [Google Scholar]
  4. R. Kruessmann, A. Ponomarev, W. Pfrang, D. Struwe, J. Champigny, B. Carluec, D. Schmitt, D. Verwaerde, “Assessment of SFR reactor safety issues: Part II: Analysis results of ULOF transients imposed on a variety of different innovative core designs with SAS-SFR”, Nuclear Engineering and Design, 285, pp. 263–283 (2015). [Google Scholar]
  5. S. Kondo, Y. Tobita, K. Morira, N. Shirakawa, “SIMMER-III: an advanced computer program for LMFBR severe accident analysis” Proceedings of the International Conference on Design and Safety of Advanced Nuclear Power Plant (ANP’92), Tokyo, Japan, October 25–29, Vol. IV, pp. 40.5.1-40.5.11 (1992). [Google Scholar]
  6. H. Yamano, S. Fujita, Y. Tobita, I. Sato, H. Niwa, “Development of a three-dimensional CDA analysis code: SIMMER-IV and its first application to reactor case”, Nuclear Engineering and Design, 238(1), pp. 66–73 (2008). [Google Scholar]
  7. M. Suzuki, H. Saitou, Y. Udagawa, Light Water Reactor Fuel Analysis Code FEMAXI-7; Model and Structure, JAEA-Data/Code 2010-035, Japan Atomic Energy Agency (JAEA), Japan (2010). [Google Scholar]
  8. T. Okawa, I. Tatewaki, T. Ishizu, H. Endo, Y. Tsuboi, H. Saitou, “Fuel behavior analysis code FEMAXI-FBR development and validation for core disruptive accident”, Progress in Nuclear Energy, 82, pp 80-85 (2015). [Google Scholar]
  9. J. Charpenel, L. Francette, I. Sato, D. Struwe, W. Pfrang, “Fuel Pin Behavior under the Slow Power Ramp Transients in the CABRI-2 Experiments”, Nuclear Technology, 130, pp. 252–271 (2000). [Google Scholar]
  10. S. Perez-Martin, W. Pfrang, N. Girault, L. Cloarec, L. Laborde, M. Buck, V. Matuzas, A. Flores y Flores, P. Raison, A.L. Smith, N. Mozzani, F. Feria, L. Herranz, B. Farges, “Development and assessment of ASTEC-Na fuel pin thermo-mechanical models performed in the European JASMIN project”, Annals of Nuclear Energy, 119, pp. 454–473 (2018). [Google Scholar]
  11. M. Haessler, D. Struwe, A.T.D. Butland, N. Nonaka, I. Sato, J. Papin, “The CABRI 2 programme -overview and results”, Proceedings of the International Fast Reactor Safety Meeting, Snowbird, USA, August 12-16. Vol. II, pp. 209–221 (1990). [Google Scholar]
  12. J. Papin, Comprehensive Nuclear Materials, Ch. 2.24 pp. 609–634, Elsevier (2012). [Google Scholar]

Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.

Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.

Initial download of the metrics may take a while.