Innovative and safe supply of fuels for reactors

Stéphane Valance; Bruno Baumeister; Winfried Petry; Jan Höglund

doi:10.1051/epjn/2019013

All issues

Volume 6 (2020)

EPJ Nuclear Sci. Technol., 6 (2020) 40

References

Euratom Research and Training in 2019: challenges, achievements and future perspectives

Open Access

Issue		EPJ Nuclear Sci. Technol. Volume 6, 2020 Euratom Research and Training in 2019: challenges, achievements and future perspectives


Article Number		40
Number of page(s)		6
Section		Part 1: Safety research and training of reactor systems
DOI		https://doi.org/10.1051/epjn/2019013
Published online		05 May 2020

ESSANUF, ESSANUF homepage, [Online] Available from http://www.essanuf.eu [Google Scholar]
J. Höglund, S. Kristensson, in ESSANUF – European Supply of SAfe NUclear Fuel, 12 International conference on WWER fuel performance, modelling and experimental support, Bulgaria, 2017 [Google Scholar]
C. Gyori, P. Blair, M. Jonson, G. Robertson, P. van Uffelen, A. Schubert, B. Hatala, R. Meca, in International Conference Nuclear Energy for New Europe (NENE), Bled, Slovenia, 2017 [Google Scholar]
T. Strömgren, Y. Le Moigne, Prediction of critical heat flux in fuel bundles using CFD, in 12 International conference on WWER fuel performance, modelling and experimental support, Bulgaria, 2017 [Google Scholar]
HERACLES-CP, HERACLES-CP homepage, [Online] Available from https://heracles-consortium.eu/cp.php [Google Scholar]
S. Dubois, J. Noirot, J. Gatt, M. Ripert, P. Lemoine, P. Boulcourt, in Proceedings of the 11th International Meeting on Research Reactor Fuel Management (RRFM), Lyon, France, 2007 [Google Scholar]
F. Huet, J. Noirot, V. Marelle, S. Dubois, P. Boulcourt, P. Sacristan, S. Naury, P. Lemoine, in 9th International Meeting on Research Reactor Fuel Management (RRFM), Budapest, Hungary, 2005 [Google Scholar]
A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Verwerft, Post-irradiation examination of uranium–7 wt% molybdenum atomized dispersion fuel, J. Nucl. Mater. 335 , 39 (2004) [Google Scholar]
D. Burkes, T. Huber, A. Casella, A model to predict thermal conductivity of irradiated U–Mo dispersion fuel, J. Nucl. Mater. 473 , 309 (2016) [Google Scholar]
S. Van den Berghe, P. Lemoine, Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in Europe, Nucl. Eng. Technol. 46 , 125 (2014) [Google Scholar]
LEU-FOREvER, LEU-FOREvER homepage, [Online] Available from https://heracles-consortium.eu/forever.php [Google Scholar]
S. Valance, H. Palancher, F. Huet, B. Stepnik, H. Breitkreuz, S. Van den Berghe, M. Hrerhor, J. Gajewski, in International Meeting on Research Reactor Fuel Management (RRFM), München, Germany, 2018 [Google Scholar]
J. Matos, in International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Chicago, USA, 2003 [Google Scholar]
A. Leenaers, J. Van Eyken, S. Van den Berghe, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]
H. Breitkreuz, J. Hingerl, A. Heldmann, C. Steyer, T. Zweifel, R. Jungwirth, J. Shi, W. Petry, in International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Antwerp, Belgium, 2016 [Google Scholar]
B. Stepnik, M. Grasse, C. Jarousse, H. Breitkreutz, C. Steyer, W. Petry, in International Meeting on Research Reactor Fuel Management (RRFM), Berlin, Germany, 2016 [Google Scholar]
G. Zaz, Y. Calzavara, E. Le Clézio, G. Despaux, Adaptation of a high-frequency ultrasonic transducer to the measurement of water tempreature in a nuclear reactor, Phys. Procedia 70 , 195 (2015) [Google Scholar]
G. Zaz, A. Dekkious, P. Meignen, Y. Calzavara, E. Le Clézio, G. Despaux, High frequency transducer dedicated to the high-resolution in-situ measurement of the distance between two nuclear fuel plates, Phys. Procedia 70 , 191 (2015) [Google Scholar]
Nuclear Regulatory Commission, Washington, DC (USA) Office of Nuclear Reactor Regulation, Safety evaluation report related to the evaluation of low-enriched uranium silicide-aluminum dispersion fuel for use in non-power reactors (NUREG–1313), United States, 1988 [Google Scholar]
R. Duperray, L. Roux, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]
M. Boyard, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]
J. Koubbi, M. Boyard, F. Huet, V. Romanello, A. Dambrosio, M. Hrehor, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]
B. Stepnik, J. Allenou, C. Rontard, C. Schwartz, C. Steyer, B. Baumeister, W. Petry, S. Van den Berghe, A. Leenaers, S. Valance, H. Palancher, E. Hervieu, Y. Calzavara, H. Guyon, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]

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[1] ESSANUF, ESSANUF homepage, [Online] Available from http://www.essanuf.eu [Google Scholar]

[2] J. Höglund, S. Kristensson, in ESSANUF – European Supply of SAfe NUclear Fuel, 12 International conference on WWER fuel performance, modelling and experimental support, Bulgaria, 2017 [Google Scholar]

[3] C. Gyori, P. Blair, M. Jonson, G. Robertson, P. van Uffelen, A. Schubert, B. Hatala, R. Meca, in International Conference Nuclear Energy for New Europe (NENE), Bled, Slovenia, 2017 [Google Scholar]

[4] T. Strömgren, Y. Le Moigne, Prediction of critical heat flux in fuel bundles using CFD, in 12 International conference on WWER fuel performance, modelling and experimental support, Bulgaria, 2017 [Google Scholar]

[5] HERACLES-CP, HERACLES-CP homepage, [Online] Available from https://heracles-consortium.eu/cp.php [Google Scholar]

[6] S. Dubois, J. Noirot, J. Gatt, M. Ripert, P. Lemoine, P. Boulcourt, in Proceedings of the 11th International Meeting on Research Reactor Fuel Management (RRFM), Lyon, France, 2007 [Google Scholar]

[7] F. Huet, J. Noirot, V. Marelle, S. Dubois, P. Boulcourt, P. Sacristan, S. Naury, P. Lemoine, in 9th International Meeting on Research Reactor Fuel Management (RRFM), Budapest, Hungary, 2005 [Google Scholar]

[8] A. Leenaers, S. Van den Berghe, E. Koonen, C. Jarousse, F. Huet, M. Trotabas, M. Boyard, S. Guillot, L. Sannen, M. Verwerft, Post-irradiation examination of uranium–7 wt% molybdenum atomized dispersion fuel, J. Nucl. Mater. 335 , 39 (2004) [Google Scholar]

[9] D. Burkes, T. Huber, A. Casella, A model to predict thermal conductivity of irradiated U–Mo dispersion fuel, J. Nucl. Mater. 473 , 309 (2016) [Google Scholar]

[10] S. Van den Berghe, P. Lemoine, Review of 15 years of high-density low-enriched UMo dispersion fuel development for research reactors in Europe, Nucl. Eng. Technol. 46 , 125 (2014) [Google Scholar]

[11] LEU-FOREvER, LEU-FOREvER homepage, [Online] Available from https://heracles-consortium.eu/forever.php [Google Scholar]

[12] S. Valance, H. Palancher, F. Huet, B. Stepnik, H. Breitkreuz, S. Van den Berghe, M. Hrerhor, J. Gajewski, in International Meeting on Research Reactor Fuel Management (RRFM), München, Germany, 2018 [Google Scholar]

[13] J. Matos, in International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Chicago, USA, 2003 [Google Scholar]

[14] A. Leenaers, J. Van Eyken, S. Van den Berghe, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]

[15] H. Breitkreuz, J. Hingerl, A. Heldmann, C. Steyer, T. Zweifel, R. Jungwirth, J. Shi, W. Petry, in International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR), Antwerp, Belgium, 2016 [Google Scholar]

[16] B. Stepnik, M. Grasse, C. Jarousse, H. Breitkreutz, C. Steyer, W. Petry, in International Meeting on Research Reactor Fuel Management (RRFM), Berlin, Germany, 2016 [Google Scholar]

[17] G. Zaz, Y. Calzavara, E. Le Clézio, G. Despaux, Adaptation of a high-frequency ultrasonic transducer to the measurement of water tempreature in a nuclear reactor, Phys. Procedia 70 , 195 (2015) [Google Scholar]

[18] G. Zaz, A. Dekkious, P. Meignen, Y. Calzavara, E. Le Clézio, G. Despaux, High frequency transducer dedicated to the high-resolution in-situ measurement of the distance between two nuclear fuel plates, Phys. Procedia 70 , 191 (2015) [Google Scholar]

[19] Nuclear Regulatory Commission, Washington, DC (USA) Office of Nuclear Reactor Regulation, Safety evaluation report related to the evaluation of low-enriched uranium silicide-aluminum dispersion fuel for use in non-power reactors (NUREG–1313), United States, 1988 [Google Scholar]

[20] R. Duperray, L. Roux, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]

[21] M. Boyard, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]

[22] J. Koubbi, M. Boyard, F. Huet, V. Romanello, A. Dambrosio, M. Hrehor, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]

[23] B. Stepnik, J. Allenou, C. Rontard, C. Schwartz, C. Steyer, B. Baumeister, W. Petry, S. Van den Berghe, A. Leenaers, S. Valance, H. Palancher, E. Hervieu, Y. Calzavara, H. Guyon, in International Meeting on Research Reactor Fuel Management (RRFM), Swemieh, Jordan, 2019 [Google Scholar]