An ultra-long-life small safe fast reactor core concept having heterogeneous driver-blanket fuel assemblies

Kuperman, 2018 Tucek, 2006, Comparison of sodium and lead-cooled fast reactors regarding reactor physics aspects, severe safety and economical issues, Nucl. Eng. Des., 236, 1589, 10.1016/j.nucengdes.2006.04.019 Yang, 2012, Fast reactor physics and computational methods, Nucl. Eng. Technol., 44, 177, 10.5516/NET.01.2012.504 Kim, 2010 You, 2016, A core physics study of advanced sodium-cooled TRU burners with thorium- and uranium-based metallic fuels, Nucl. Technol., 194, 217, 10.13182/NT15-85 2013 Taiwo, 2006, Nucl. Technol., 155, 34, 10.13182/NT06-A3744 Sekimoto, 2001, CANDLE: the new burnup strategy, Nucl. Sci. Eng., 130, 306, 10.13182/NSE01-01 Sekimoto, 2010, Performance optimization of the CANDLE reactor for nuclear energy sustainability, Energy Convers. Manag., 51, 1788, 10.1016/j.enconman.2009.12.045 Ahlfeld, 2011, Conceptual design of a 500MWe travelling wave demonstration reactor plant Gilleland, 2016, The traveling wave reactor: design and development, Engineering, 2, 88, 10.1016/J.ENG.2016.01.024 Greenspan, 2012, A phased development of breed-and-burn reactors for enhanced nuclear energy sustainability, Sustainability, 4, 2745, 10.3390/su4102745 Hong, 2017, Core design options of an ultra-long-cycle sodium cooled reactor with effective use of PWR spent fuel for sustainable energy supply, Int. J. Energy Res., 41, 854, 10.1002/er.3677 Hong, 2015, A neutronic design study of lead-bismuth-cooled small and safe ultra-long-life cores, Ann. Nucl. Energy, 85, 58, 10.1016/j.anucene.2015.04.032 Hartanto, 2016, An optimization study on the excess reactivity in a linear breed-and-burn fast reactor (B&BR), Ann. Nucl. Energy, 94, 62, 10.1016/j.anucene.2016.02.017 Driscoll, 1979 Hejzlar, 2013, LLC Traveling wave reactor development overview, Nucl. Eng. Technol., 45, 731, 10.5516/NET.02.2013.520 Choi, 2018, A neutronic design study of small ultra-long-life SFR core using serpent heterogeneous Monte Carlo calculation Jung, 2016, A preliminary design study of ultra-long-life SFR cores having heterogeneous fuel assemblies Jung, 2018, Alternative design options for small ultra-long-life sodium cooled fast reactor core using heterogeneous assemblies Pelowitz, 2013 Leppanen, 2015, The serpent Monte Carlo code : status, development and applications in 2013, Ann. Nucl. Energy, 82, 142, 10.1016/j.anucene.2014.08.024 Wade, 1997, The design nationale of the IFR, Prog. Nucl. Engergy, 31, 13, 10.1016/0149-1970(96)00002-9 Sun, 2013, A neutronics study for improving the safety and performance parameters of a 3600 MWth sodium-cooled fast reactor, Ann. Nucl. Energy, 53, 464, 10.1016/j.anucene.2012.10.004 Hong, 2005, The encapsulated nuclear heat source (ENHS) reactor core design, Nucl. Technol., 149, 22, 10.13182/NT05-A3577 Tak, 2015, Feasibility study on ultra-long cycle operation and material performance for compact liquid metal-cooled fast reactors : a review work, Int. J. Energy Res., 39, 1859, 10.1002/er.3384 Stauff, 2013, Application of an annular metallic fuel with lower gas plenum for sodium-cooled fast reactor, Trans. Am. Nucl. Soc., 108, 747 Chenaud, 2013, Status of the ASTRID core at the end of the pre-conceptual design phase 1, Nucl. Eng. Technol., 45, 721, 10.5516/NET.02.2013.519 Sciora, 2011, Low void effect core design applied on 2400 MWth SFR reactor