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Analysis of sodium boiling initiated by unprotected loss of flow in European sodium fast reactor core with different subassembly designs
Bodi, J., Ponomarev, A., & Mikityuk, K. (2022). Analysis of sodium boiling initiated by unprotected loss of flow in European sodium fast reactor core with different subassembly designs. Nuclear Engineering and Design, 399, 112014 (12 pp.). https://doi.org/10.1016/j.nucengdes.2022.112014
Analysis of hypothetical unprotected loss of flow in superphénix start-up core: sensitivity to modeling details
Ponomarev, A., & Mikityuk, K. (2019). Analysis of hypothetical unprotected loss of flow in superphénix start-up core: sensitivity to modeling details. In The proceedings of the international conference on nuclear engineering (ICONE): Vol. 2019.27. Proceedings of ICONE-27. 27th international conference on nuclear engineering (pp. ICONE27-2050 (6 pp.). https://doi.org/10.1299/jsmeicone.2019.27.2050
Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels
Zhang, Y., & Mikityuk, K. (2016). Static and transient analysis of a medium-sized sodium cooled fast reactor loaded with oxide, nitride, carbide and metallic fuels. Annals of Nuclear Energy, 87, 761-771. https://doi.org/10.1016/j.anucene.2015.03.025
Coupled 3D-neutronics / thermal-hydraulics analysis of an unprotected loss-of-flow accident for a 3600 MWth SFR core
Sun, K., Chenu, A., Mikityuk, K., Krepel, J., & Chawla, R. (2012). Coupled 3D-neutronics / thermal-hydraulics analysis of an unprotected loss-of-flow accident for a 3600 MWth SFR core. In Vol. 4. PHYSOR 2012: advances in reactor physics (pp. 3231-3245).