The hydrogen terminal solubilities for dissolution (TSSD) and precipitation (TSSP) in non-irradiated sponge-based E110opt alloy and electrolytic zirconium E635 alloy are presented. TSS measurements for these alloys were made for the first time. Samples were examined using the methods of differential scanning calorimetry (DSC) and hot vacuum extraction spectrometry. Terminal solid solubilities (TSSD and TSSP) in E110opt and E635 alloys are shown to be coincident with each other within the experimental uncertainty interval. This means that there is no distinguishable difference between TSS in sponge-based and electrolytic zirconium alloys. Resulting TSSD values for E110opt and E635 alloys were compared with those for zirconium alloys Zircaloy-2, Zircaloy-4, Zr-1%Nb, M5, Zirlo and shown to be identical within the errors. Approximation dependencies of TSSD and TSSP solvi in E110opt and E635 alloys were derived. These dependencies will be used in nuclear fuel performance codes to calculate behavior of the zirconium reactor core components in different regimes of operation.
机构:
Atom Energy Canada Ltd, Chalk River Nucl Labs, Stn 82, Chalk River, ON K0J 1J0, CanadaAtom Energy Canada Ltd, Chalk River Nucl Labs, Stn 82, Chalk River, ON K0J 1J0, Canada
机构:
Atom Energy Canada Ltd, Chalk River Nucl Labs, Stn 82, Chalk River, ON K0J 1J0, CanadaAtom Energy Canada Ltd, Chalk River Nucl Labs, Stn 82, Chalk River, ON K0J 1J0, Canada