References
- Xu Mi, Safety properties of China experimental fast reactor, Chin. J. Nucl. Eng. Sci. (2) (2011) 116-126.
- Xu Mi, Fast reactor technology R&D activities in China, Nucl. Eng. Technol. 39 (3) (2007) 187-192. https://doi.org/10.5516/NET.2007.39.3.187
- K. Clarno, A.A. Lorber, R.J. Pryor, W.F. Spotz, R.C. Schmidt, K. Belcourt, L. L. Humphries, Foundational Development of an Advanced Nuclear Reactor Integrated Safety Code (No. SAND2010-0878), Sandia National Laboratories (SNL), Albuquerque, NM, and Livermore, CA (United States), 2010.
- A.M. Tentner, D.P. Weber, G. Birgersson, SAS4A LMFBR Whole Core Accident Analysis Code (No. CONF-850410, 2, 1985.
- S. Kondo, Y. Tobita, K. Morita, N. Shirakawa, SIMMER-III: an advanced computer program for LMFBR severe accident analysis, in: ANP'92 International Conference on Design and Safety of Advanced Nuclear Power Plants, 1992.
- Y. Tobita, T. Fujita, T. Miura, M. Sugaya, Development of SAME-2: A Connection Code between SAS4A and SIMMER-3, 2002.
- G. Bandini, S. Ederli, S. Perez-Martin, M. Haselbauer, W. Pfrang, L.E. Herranz, C. Berna, V. Matuzas, A. Flores y Flores, N. Girault, L. Laborde, ASTEC-Na code: thermal-hydraulic model validation and benchmarking with other codes, Ann. Nucl. Energy 119 (2018) 427-439, https://doi.org/10.1016/j.anucene.2017.12.016.
- 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, Ann. Nucl. Energy 119 (2018) 454-473, https://doi.org/10.1016/j.anucene.2017.12.061.
- V. Matuzas, L. Ammirabile, L. Cloarec, D. Lemasson, S. Perez-Martin, A. Ponomarev, Extension of ASTEC-Na capabilities for simulating reactivity effects in sodium cooled fast reactor, Ann. Nucl. Energy 119 (2018) 440-453, https://doi.org/10.1016/j.anucene.2017.12.030.
- L.S. Lebel, N. Girault, New developments in modeling sodium spray fires with ASTEC-Na, Ann. Nucl. Energy 119 (2018) 23-35, https://doi.org/10.1016/j.anucene.2018.04.024.
- N.A. Mosunova, The EUCLID/V1 integrated code for safety assessment of liquid metal cooled fast reactors. Part 1: basic models, Therm. Eng. 65 (5) (2018) 304-316, https://doi.org/10.1134/s0040601518050063.
- V.M. Alipchenkov, A.V. Boldyrev, D.P. Veprev, Yu A. Zeigarnik, P.V. Kolobaeva, E. V. Moiseenko, N.A. Mosunova, E.F. Seleznev, V.F. Strizhov, E.V. Usov, S.L. Osipov, V.S. Gorbunov, D.A. Afremov, A.A. Semchenkov, The EUCLID/V1 integrated code for safety assessment of liquid metal cooled fast reactors. Part 2: validation and verification, Therm. Eng. 65 (9) (2018) 627-640, https://doi.org/10.1134/s004060151809001x.
- R. Hooper, M. Hopkins, R. Pawlowski, B. Carnes, H. Moffat, Final Report on LDRD Project: Coupling Strategies for Multi-Physics Applications, SAND2007-7146, Sandia National Laboratories, April 2007.
- P. Gao, B. Zhang, J. Li, J. Shan, Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment, Nucl. Eng. Technol. (2021), https://doi.org/10.1016/j.net.2021.07.029.
- S. Tang, B. Zhang, J. Shan, Research on the performance enhancement of accident tolerant fuel for eliminating core melting based on ISAA, Ann. Nucl. Energy 186 (2023) 109747, https://doi.org/10.1016/j.anucene.2023.109747.
- J.B. Ainscough, B.W. Oldfield, J.O. Ware, Isothermal grain growth kinetics in sintered UO2 pellets, J. Nucl. Mater. 49 (2) (1973) 117-128, https://doi.org/10.1016/0022-3115(73)90001-9.
- A. Magni, A. Del Nevo, L. Luzzi, D. Rozzia, M. Adorni, A. Schubert, P. Van Uffelen, The TRANSURANUS fuel performance code, in: Nuclear Power Plant Design and Analysis Codes, Woodhead Publishing, 2021, pp. 161-205.
- B. Michel, I. Rami'ere, I. Viallard, C. Introini, M. Lainet, N. Chauvin, S. Bernaud, Two fuel performance codes of the PLEIADES platform: ALCYONE and GERMINAL, in: Nuclear Power Plant Design and Analysis Codes, Woodhead Publishing, 2021, pp. 207-233.
- S.E. Lemehov, F. Jutier, Y. Parthoens, B. Vos, S. Van Den Berghe, M. Verwerft, N. Nakae, MACROS benchmark calculations and analysis of fission gas release in MOX with high content of plutonium, Prog. Nucl. Energy 57 (2012) 117-124, https://doi.org/10.1016/j.pnucene.2011.12.010.
- M.F. Marchbanks, R.A. Moen, J.E. Irvin, Nuclear Systems Materials Handbook, Hanford Engineering Development Lab, 1976 (No. HEDL-SA-871).
- R. Sher, Fission-energy Release for 16 Fissioning Nuclides. Final Report (No. EPRI-NP-1771), Stanford Univ., CA (USA), 1981. Dept. of Mechanical Engineering.
- T.H. Fanning, A.J. Brunett, T. Sumner, The SAS4A/SASSYS-1 Safety Analysis Code System, Argonne National Lab.(ANL), Argonne, IL (United States), 2017 version 5 (No. ANL/NE-16/19).
- M. Bober, G. Schumacher, Material transport in the temperature gradient of fast reactor fuels, in: Advances in Nuclear Science and Technology, Academic Press, 1973, pp. 121-179.
- C.F. Clement, The movement of lenticular pores in UO2 nuclear fuel elements, J. Nucl. Mater. 68 (1) (1977) 63-68. https://doi.org/10.1016/0022-3115(77)90217-3
- W.J. Lackey, F.J. Homan, A.R. Olsen, Porosity and actinide redistribution during irradiation of (U, Pu)O2, Nucl. Technol. 16 (1) (1972) 120-142, https://doi.org/10.13182/nt72-a31181.
- V.Z. Jankus, R.W. Weeks, LIFE-I: A FORTRAN-IV COMPUTER CODE FOR THE PREDICTION OF FAST-REACTOR FUEL-ELEMENT BEHAVIOR (No. ANL-7736), Argonne National Lab., Ill, 1970.
- J.F. Babelot, N. Chauvin, Joint CEA/JRC Synthesis Report of the Experiment SUPERFACT 1. Report JRC-ITU-TN-99/03, 1999.
- C. Prunier, F. Boussard, L. Koch, M. Coquerelle, Some Specific Aspects of Homogeneous Am and Np Based Fuels Transmutation through the Outcomes of the Superfact Experiment in PHENIX Fast Reactor (No. CEA-CONF-11506), CEA Centre d'Etudes de Cadarache, 1993.
- L. Luzzi, T. Barani, B. Boer, L. Cognini, A. Del Nevo, M. Lainet, S. Lemehov, A. Magni, V. Marelle, B. Michel, D. Pizzocri, A. Schubert, P. Van Uffelen, M. Bertolus, Assessment of three European fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, Nucl. Eng. Technol. 53 (10) (2021) 3367-3378, https://doi.org/10.1016/j.net.2021.04.010.
- L. Luzzi, T. Barani, B. Boer, A. Del Nevo, M. Lainet, S. Lemehov, A. Magni, V. Marelle, B. Michel, D. Pizzocri, A. Schubert, P. Van Uffelen, M. Bertolus, Assessment of INSPYRE-extended fuel performance codes against the SUPERFACT-1 fast reactor irradiation experiment, Nucl. Eng. Technol. 55 (3) (2023) 884-894, https://doi.org/10.1016/j.net.2022.10.038.
- A.H. Squillacote, J. Ahrens, C. Law, B. Geveci, K. Moreland, B. King, The Paraview Guide, 366, Kitware, Clifton Park, NY, 2007.
- K. Lassmann, A. Schubert, P. Van Uffelen, C. Gyori, J. Van De Laar, Transuranus Handbook, 1975. Document Number Version, 1.
- A. Gallais-During, F. Delage, S. Bejaoui, 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, J. Nucl. Mater. 512 (2018) 214-226, https://doi.org/10.1016/j.jnucmat.2018.10.016.
- M. Lainet, B. Michel, J.-C. Dumas, M. Pelletier, I. Rami'ere, GERMINAL, a fuel performance code of the PLEIADES platform to simulate the in-pile behaviour of mixed oxide fuel pins for sodium-cooled fast reactors, J. Nucl. Mater. 516 (2019) 30-53, https://doi.org/10.1016/j.jnucmat.2018.12.030.
- G. Pastore, L. Luzzi, V. Di Marcello, P. Van Uffelen, Physics-based modelling of fission gas swelling and release in UO2 applied to integral fuel rod analysis, Nucl. Eng. Des. 256 (2013) 75-86, https://doi.org/10.1016/j.nucengdes.2012.12.002.
- G. Kussmaul, W. Vaeth, J. Wolff, J. Dadillon, M. Haessler, F. Sabathier, The CABRI project-overall status and achievements, in: Science and Technology of Fast Reactor Safety, Thomas Telford Publishing, 1987, pp. 1-103.