6/27/2023 0 Comments Mcfr quicklinksEnergy 65, 78–90 (2014).Together with our partners, Vanderbilt is advancing sustainable materials to build your home, power your business, and strengthen your community. Antonio et al., Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: analytical, deterministic and Monte Carlo approaches. Pope et al., Sustained Recycle in Light Water and Sodium-Cooled Reactors. Jordanov et al., Conversion of high enriched uranium in thorium-232-based oxide fuel for light and heavy water reactors: MOX-T fuel. Huff, Fuel cycle performance of fast spectrum molten salt reactor designs. ![]() Cai et al., Minor actinide incineration and Th–U breeding in a small FLiNaK molten salt fast reactor. Xia et al., Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium. Brun et al., Fast thorium molten salt reactors started with plutonium. Li et al., Transition toward thorium fuel cycle in a molten salt reactor by using plutonium. University of Chinese Academy of Sciences (2019)ĭ.Y. Xia, Research on the High-precision Burnup Calculation Methods and Thorium–Uranium Fuel Breeding For The Liquid-Fueled Molten Salt Reactors. Xia et al., Effect of 37Cl enrichment on neutrons in a molten chloride salt fast reactor. Gauld, Origen-s: Depletion Module to Calculate Neutron Activation, Actinide Transmutation, Fission Product Generation, and Radiation Source Terms (Oak Ridge National Laboratory, Oak Ridge, 2011) Wu et al., Development of a Molten Salt Reactor specifific depletion code MODEC. ![]() Bowman, Scale 6: comprehensive nuclear safety analysis code system. Cui et al., Analysis of burnup performance for a molten chloride salt fast reactor based on thorium fuel. Yu et al., Influences of 7Li enrichment on Th–U fuel breeding for an improved molten salt fast reactor (IMSFR). Yu et al., Model optimization and analysis of Th–U breeding based on MSFR. Billebaud et al., Potential of thorium molten salt reactors detailed calculations and concept evolution with a view to large scale energy production. Bokov, Potentialities of the fast spectrum molten salt reactor concept: REBUS-3700. Design optimization and burnup analysis for molten chloride fast reactor. Weißbach et al., The dual fluid reactor-a novel concept for a fast nuclear reactor of high efficiency. Proceedings of the International Thorium Energy Conference: Gateway to Thorium Energy (2015)Ī. Abram, Stable salt reactor design concept. Simmons, An assessment of a 2500 MWe molten chloride salt fast reactor (United Kingdom Energy Authority Reactor Group, Winfrith, 1974) Yan et al., Th–U and U–Pu cycling performances of molten chloride salt fast reactor under LEU start-up mode. Holl et al., Reactor design and feasibility study: fused salt fast breeder (Oak Ridge School of Reactor Technology, Oak Ridge, 1956) GIF (Generation IV International Forum) Annual Report 2008(2008), pp. The thorium molten salt reactor: Launching the thorium fuel cycle with the molten salt fast reactor. Ivan et al., Progress in development of Li, Be, Na/F molten salt actinide recycler & transmutation concept. Aufiero et al., Modelling and analysis of the MSFR transient behavior. Cammi et al., Investigation of the MSFR core physics and fuel cycle characteristics. Allibert et al., Towards the thorium fuel cycle with molten salt fast reactors. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation.ĭ. Moreover, the breeding capability of an MCFR was better than that of an MFFR at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR) to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. The recent development of molten salt fast reactors has generated a renewed interest in them.
0 Comments
Leave a Reply. |