Coupling reactor design and scenario calculations: a promising method for scenario optimization

Kévin Tirel; Timothée Kooyman; Christine Coquelet-Pascal; Elsa Merle

doi:10.1051/epjn/2022002

All issues

Volume 8 (2022)

EPJ Nuclear Sci. Technol., 8 (2022) 7

References

Fuel Cycle Simulation TWoFCS 2021

Open Access

Issue		EPJ Nuclear Sci. Technol. Volume 8, 2022 Fuel Cycle Simulation TWoFCS 2021


Article Number		7
Number of page(s)		14
DOI		https://doi.org/10.1051/epjn/2022002
Published online		25 May 2022

Loi n°91-1381 du 30 décembre 1991 relative aux recherches sur la gestion des déchets radioactifs, 1991 [Google Scholar]
Loi n° 2006-739 du 28 juin2006 de programme relative à la gestion durable des matières et déchets radioactifs, 2006 [Google Scholar]
Ministère de la transition écologique et solidaire, Programmation Pluriannuelle de l'Energie, 2019 [Google Scholar]
P. Sciora, L. Buiron, G. Rimpault, F. Varaine, A break even oxide fuel core for an innovative SFR: CEA neutronic studies, in Proceedings of the Global 2009 conference, Paris, France (2009) [Google Scholar]
P. Sciora, D. Blanchet, L. Buiron, B. Fontaine, M. Vanier, F. Varaine, C. Venard, S. Massara, A.-C. Scholer, D. Verrier, Low void effect core design applied on 2400 MWth SFR reactor, in Proceedings of the ICAPP 2011 conference, Nice, France 5, 1 (2011) [Google Scholar]
A. Languille, J. Garnier, P. Lo Pinto, CAPRA core studies − The oxide Reference Option, in Proceedings of the Global 1995 conference, Versailles, France (1995) [Google Scholar]
A. Zaetta, B. Fontaine, P. Sciora, R. Lavastre, R. Jacqmin, V. Pascal, M. Pelletier, G. Mignot, A. Jankowiak, CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors, EPJ Nuclear Sci. Technol. 5, 1 (2019) [Google Scholar]
C. Coquelet-Pascal, M. Tiphine, G. Krivtchik, D. Freynet, C. Cany, R. Eschbach, C. Chabert, COS I6: a tool for nuclear transition scenario studies and application to SFR deployment scenarios with minor actinide transmutation, Nucl. Technol. 192, 91–110 (2015) [CrossRef] [Google Scholar]
T. Kooyman, P. Sciora, C. Coquelet-Pascal, Some considerations on the design of a small versatile fast reactor, in Proceedings of the ICAPP 2019 conference, Juan-les-pins, France (2019) [Google Scholar]
G. Krivtchik, Analysis of unvertainty propagation in nuclear fuel cycle scenarios, PhD thesis, Université de Grenoble, 2014 [Google Scholar]
D. Freynet, Développement d'une méthodologie pour l'optimisation multicritère de scénarios d'évolution du parc nucléaire, PhD thesis, Université de Grenoble, 2016 [Google Scholar]
K. Ammar, Conception multi-physique et multi-objectif des coeurs de RNR-Na hétérogènes: développement d'une méthode d'optimisation sous incertitudes, PhD thesis, Université Paris-Sud 11, 2014 [Google Scholar]
O. Fabbris, Optimisation multi-physique et multi-critère des coeurs de RNR-Na: application au concept CFV, PhD thesis, Université de Grenoble, 2014 [Google Scholar]
T. Kooyman, Amélioration des performances de transmutation des actinides mineurs dans les réacteurs de quatrième génération: aspects cycle et coeurs, PhD thesis, Université d'Aix-Marseille, 2017 [Google Scholar]
M. Ernoult, X. Doligez, N. Thiollière, A. Zakari-Issoufou, A. Bidaud, S. Bouneau, J. Clavel, F. Courtin, S. David, A. Somaini, Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations, Ann. Nucl. Energy 1128, 69–76 (2019) [CrossRef] [Google Scholar]
J.-B. Blanchard, G. Damblin, J.-M. Martinez, G. Arnaud, F. Gaudier, The URANIE platform: an open-source software for optimisation, meta-modelling and uncertainty analysis, EPJ Nuclear Sci. Technol. 5, 4 (2019) [Google Scholar]
J. Ruggieri, J. Tommasi, J. Lebrat, C. Suteau, D. Plisson-Rieunier, G. Rimpault, J. Sublet, ERANOS 2.1: International Code System for GEN IV Fast Reactor, in Proceedings of the ICAPP 2006 conference, Reno, Nevada, USA (2006) [Google Scholar]
A. Koning, R. Forrest, M. Kellett, R. Mills, H. Henriksson, Y. Rugama, The JEFF-3.1 Nuclear Data Library, 2006 [Google Scholar]
G. Martin, C. Coquelet-Pascal, Symbiotic equilibrium between sodium fast reactors and pressurized water reactors supplied with MOX fuel, Ann. Nucl. Energy 103, 356–362 (2017) [Google Scholar]
K. Tirel, T. Kooyman, C. Coquelet-Pascal, E. Merle, Possibility to stabilize plutonium inventory in a sodium-cooled small modular reactors − Pressurized water reactors fleet, Ann. Nucl. Energy 146, 107632 (2020) [CrossRef] [Google Scholar]
S. Aniel, J. Bergeron, A. Puill, Evaluation of the maximum content of a MOX-fueled pressurized water reactor versus isotopic composition with respect to the void coefficient, Article publié lors d'un comité technique, n° XA9744117, Newby Bridge, Royaume Uni, 1995 [Google Scholar]
P. Virtanen, R. Gommers, T.E. Oliphant, M. Haberland, T. Reddy, D. Cournapeau, E. Burovski, P. Peterson, W. Weckesser, J. Bright, S.J.v.d. Walt, M. Brett, J. Wilson, K.J. Millman, N. Mayorov, A.R.J. Nelson, E. Jones, R. Kern, E. Larson, C. Carey, I. Polat, Y. Feng, E.W. Moore, J. VanderPlas, D. Laxalde, J. Perktold, R. Cimrman, I. Henriksen, E. Quintero, C.R. Harris, A.M. Archibald, A.H. Ribeiro, F. Pedregosa, P. van Mulbregt, SciPy 1.0 Contributors, SciPy 1.0: fundamental algorithms for scientific computing in python, Nat. Methods 17, 261–272 (2020) [NASA ADS] [CrossRef] [Google Scholar]
N. Thiollière, J.-B. Clavel, F. Courtin, X. Doligez, M. Ernoult, Z. Issoufou, G. Krivtchik, B. Leniau, B. Mouginot, A. Bidaud, S. David, V. Lebrin, C. Perigois, Y. Richet, A. Somaini, A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a PWR fleet simulated with the CLASS tool, EPJ Nuclear Sci. Technol. 4, 113 (2018) [Google Scholar]
ANDRA, Inventaire national des matières et déchets radioactifs, Rapport de synthèse, 2018 [Google Scholar]
D. Gelles, Microstructural examination of commercial ferritic alloys at 200 dpa, J. Nucl. Mater. 1, 293–298 (1996) [CrossRef] [Google Scholar]
W. Zhou, Resilience analysis of nuclear fuel cycle scenarios, PhD thesis, Université de Grenoble, 2020 [Google Scholar]
J. Liang, M. Ernoult, X. Doligez, S. David, S. Bouneau, N. Thiollière, G. Krivtchik, F. Courtin, W. Zhou, S. Tillement, Assessment of strategy robustness under disruption of objective in dynamic fuel cycle studies, Ann. Nucl. Energy 154, 108131 (2021) [CrossRef] [Google Scholar]

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[1] Loi n°91-1381 du 30 décembre 1991 relative aux recherches sur la gestion des déchets radioactifs, 1991 [Google Scholar]

[2] Loi n° 2006-739 du 28 juin2006 de programme relative à la gestion durable des matières et déchets radioactifs, 2006 [Google Scholar]

[3] Ministère de la transition écologique et solidaire, Programmation Pluriannuelle de l'Energie, 2019 [Google Scholar]

[4] P. Sciora, L. Buiron, G. Rimpault, F. Varaine, A break even oxide fuel core for an innovative SFR: CEA neutronic studies, in Proceedings of the Global 2009 conference, Paris, France (2009) [Google Scholar]

[5] P. Sciora, D. Blanchet, L. Buiron, B. Fontaine, M. Vanier, F. Varaine, C. Venard, S. Massara, A.-C. Scholer, D. Verrier, Low void effect core design applied on 2400 MWth SFR reactor, in Proceedings of the ICAPP 2011 conference, Nice, France 5, 1 (2011) [Google Scholar]

[6] A. Languille, J. Garnier, P. Lo Pinto, CAPRA core studies − The oxide Reference Option, in Proceedings of the Global 1995 conference, Versailles, France (1995) [Google Scholar]

[7] A. Zaetta, B. Fontaine, P. Sciora, R. Lavastre, R. Jacqmin, V. Pascal, M. Pelletier, G. Mignot, A. Jankowiak, CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors, EPJ Nuclear Sci. Technol. 5, 1 (2019) [Google Scholar]

[8] C. Coquelet-Pascal, M. Tiphine, G. Krivtchik, D. Freynet, C. Cany, R. Eschbach, C. Chabert, COS I6: a tool for nuclear transition scenario studies and application to SFR deployment scenarios with minor actinide transmutation, Nucl. Technol. 192, 91–110 (2015) [CrossRef] [Google Scholar]

[9] T. Kooyman, P. Sciora, C. Coquelet-Pascal, Some considerations on the design of a small versatile fast reactor, in Proceedings of the ICAPP 2019 conference, Juan-les-pins, France (2019) [Google Scholar]

[10] G. Krivtchik, Analysis of unvertainty propagation in nuclear fuel cycle scenarios, PhD thesis, Université de Grenoble, 2014 [Google Scholar]

[11] D. Freynet, Développement d'une méthodologie pour l'optimisation multicritère de scénarios d'évolution du parc nucléaire, PhD thesis, Université de Grenoble, 2016 [Google Scholar]

[12] K. Ammar, Conception multi-physique et multi-objectif des coeurs de RNR-Na hétérogènes: développement d'une méthode d'optimisation sous incertitudes, PhD thesis, Université Paris-Sud 11, 2014 [Google Scholar]

[13] O. Fabbris, Optimisation multi-physique et multi-critère des coeurs de RNR-Na: application au concept CFV, PhD thesis, Université de Grenoble, 2014 [Google Scholar]

[14] T. Kooyman, Amélioration des performances de transmutation des actinides mineurs dans les réacteurs de quatrième génération: aspects cycle et coeurs, PhD thesis, Université d'Aix-Marseille, 2017 [Google Scholar]

[15] M. Ernoult, X. Doligez, N. Thiollière, A. Zakari-Issoufou, A. Bidaud, S. Bouneau, J. Clavel, F. Courtin, S. David, A. Somaini, Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations, Ann. Nucl. Energy 1128, 69–76 (2019) [CrossRef] [Google Scholar]

[16] J.-B. Blanchard, G. Damblin, J.-M. Martinez, G. Arnaud, F. Gaudier, The URANIE platform: an open-source software for optimisation, meta-modelling and uncertainty analysis, EPJ Nuclear Sci. Technol. 5, 4 (2019) [Google Scholar]

[17] J. Ruggieri, J. Tommasi, J. Lebrat, C. Suteau, D. Plisson-Rieunier, G. Rimpault, J. Sublet, ERANOS 2.1: International Code System for GEN IV Fast Reactor, in Proceedings of the ICAPP 2006 conference, Reno, Nevada, USA (2006) [Google Scholar]

[18] A. Koning, R. Forrest, M. Kellett, R. Mills, H. Henriksson, Y. Rugama, The JEFF-3.1 Nuclear Data Library, 2006 [Google Scholar]

[19] G. Martin, C. Coquelet-Pascal, Symbiotic equilibrium between sodium fast reactors and pressurized water reactors supplied with MOX fuel, Ann. Nucl. Energy 103, 356–362 (2017) [Google Scholar]

[20] K. Tirel, T. Kooyman, C. Coquelet-Pascal, E. Merle, Possibility to stabilize plutonium inventory in a sodium-cooled small modular reactors − Pressurized water reactors fleet, Ann. Nucl. Energy 146, 107632 (2020) [CrossRef] [Google Scholar]

[21] S. Aniel, J. Bergeron, A. Puill, Evaluation of the maximum content of a MOX-fueled pressurized water reactor versus isotopic composition with respect to the void coefficient, Article publié lors d'un comité technique, n° XA9744117, Newby Bridge, Royaume Uni, 1995 [Google Scholar]

[22] P. Virtanen, R. Gommers, T.E. Oliphant, M. Haberland, T. Reddy, D. Cournapeau, E. Burovski, P. Peterson, W. Weckesser, J. Bright, S.J.v.d. Walt, M. Brett, J. Wilson, K.J. Millman, N. Mayorov, A.R.J. Nelson, E. Jones, R. Kern, E. Larson, C. Carey, I. Polat, Y. Feng, E.W. Moore, J. VanderPlas, D. Laxalde, J. Perktold, R. Cimrman, I. Henriksen, E. Quintero, C.R. Harris, A.M. Archibald, A.H. Ribeiro, F. Pedregosa, P. van Mulbregt, SciPy 1.0 Contributors, SciPy 1.0: fundamental algorithms for scientific computing in python, Nat. Methods 17, 261–272 (2020) [NASA ADS] [CrossRef] [Google Scholar]

[23] N. Thiollière, J.-B. Clavel, F. Courtin, X. Doligez, M. Ernoult, Z. Issoufou, G. Krivtchik, B. Leniau, B. Mouginot, A. Bidaud, S. David, V. Lebrin, C. Perigois, Y. Richet, A. Somaini, A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a PWR fleet simulated with the CLASS tool, EPJ Nuclear Sci. Technol. 4, 113 (2018) [Google Scholar]

[24] ANDRA, Inventaire national des matières et déchets radioactifs, Rapport de synthèse, 2018 [Google Scholar]

[25] D. Gelles, Microstructural examination of commercial ferritic alloys at 200 dpa, J. Nucl. Mater. 1, 293–298 (1996) [CrossRef] [Google Scholar]

[26] W. Zhou, Resilience analysis of nuclear fuel cycle scenarios, PhD thesis, Université de Grenoble, 2020 [Google Scholar]

[27] J. Liang, M. Ernoult, X. Doligez, S. David, S. Bouneau, N. Thiollière, G. Krivtchik, F. Courtin, W. Zhou, S. Tillement, Assessment of strategy robustness under disruption of objective in dynamic fuel cycle studies, Ann. Nucl. Energy 154, 108131 (2021) [CrossRef] [Google Scholar]