Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Illustration of heterogeneity for two salt shares

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Scheme of the EQL0D procedure. The upper-right step (green) is performed by the cell code and the rest of the steps (orange) by the MATLAB-based script

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Infinite neutron multiplication factor at the beginning of equilibrium cycle for several configurations

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Uranium-233 weight percentage among actinides in the equilibrium composition

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Reproduction of the U233 weight percentage at equilibrium using the inverse of the capture rate according to Eq. (2) and normalized to the maximum of the actual value for comparison with Fig. 4

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Excess reactivity per weight percentage of Uranium-233 at equilibrium as a function of the graphite length between channels

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Graphite slowing-down length computed according to Eq. (3)

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Neutron spectra of channels of 1, 10, 50 cm radius and salt share of 30%

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Neutron spectra of channels of 5 cm and salt shares of 10%, 40%, and 80%

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Spatial distribution of thermal (above) and fast (below) fission rates (in arbitrary units) in the 30 cm and 40% case

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Thermal-to-total fission rate ratio according to Eq. (4) as function of the distance between channels

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Uranium-234-to-Uranium-233 ratio as function of the distance between channels

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Protactinium-233 capture contribution to the Uranium-234-to-Uranium-233 ratio as function of the distance between channels

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Uranium-233 capture contribution to the Uranium-234-to-Uranium-233 ratio as function of the distance between channels

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Calculated bare cylinder critical radius given by Eq. (6) as function of the interchannel distance

Date of download: 10/11/2017 Copyright © ASME. All rights reserved. From: Parametric Lattice Study of a Graphite-Moderated Molten Salt Reactor ASME J of Nuclear Rad Sci. 2015;1(1):011009-011009-8. doi:10.1115/1.4026401 Figure Legend: Calculated migration area given by Eq. (7) as function of the interchannel distance