Date of download: 11/12/2016 Copyright © ASME. All rights reserved. From: Fission Product Release Under Supercritical Water-Cooled Reactor Conditions ASME J of Nuclear Rad Sci. 2016;2(2): doi: / Noble gas and iodine release versus decay constant (λ) from EVESR superheat fuel rod KB-40 (Adapted from Ref. [8]). Y-axis is release rate divided by the yield (y) and the decay constant. Data from April 2, 1966: reactor power 13 MW(t) and outlet steam temperature 847°F. The peak cladding temperature at the time of failure was estimated to be 777°C Figure Legend:

Date of download: 11/12/2016 Copyright © ASME. All rights reserved. From: Fission Product Release Under Supercritical Water-Cooled Reactor Conditions ASME J of Nuclear Rad Sci. 2016;2(2): doi: / Weight change for the SIMFUEL samples tested at 400°C and 25 MPa at different exposure times. Samples 1, 2, and 3 were exposed for 1 day, samples 4, 5, and 6 for 3 days, and samples 7, 8, and 9 for 7 days Figure Legend:

Date of download: 11/12/2016 Copyright © ASME. All rights reserved. From: Fission Product Release Under Supercritical Water-Cooled Reactor Conditions ASME J of Nuclear Rad Sci. 2016;2(2): doi: / Concentrations of autoclave corrosion products in the test solution as a function of exposure time at 400°C and 25 MPa Figure Legend:

Date of download: 11/12/2016 Copyright © ASME. All rights reserved. From: Fission Product Release Under Supercritical Water-Cooled Reactor Conditions ASME J of Nuclear Rad Sci. 2016;2(2): doi: / Concentrations of Sr and Ba in the test solution as a function of exposure time at 400°C and 500°C, 25 MPa Figure Legend:

Date of download: 11/12/2016 Copyright © ASME. All rights reserved. From: Fission Product Release Under Supercritical Water-Cooled Reactor Conditions ASME J of Nuclear Rad Sci. 2016;2(2): doi: / Solubility of UO2(c) at 500°C as a function of pH using a Ni-NiO buffer. Adapted from Red’kin et al. [27] Figure Legend:

Date of download: 11/12/2016 Copyright © ASME. All rights reserved. From: Fission Product Release Under Supercritical Water-Cooled Reactor Conditions ASME J of Nuclear Rad Sci. 2016;2(2): doi: / Thermodynamically calculated solubility of ThO2 at 25°C as a function of pH Figure Legend: