Explanation of the UO2/Zircaloy-4 Reaction layer sequence in terms of the total interfacial energy of the system

Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C

“…It has been shown in many out-of-pile and in-pile experiments that UO 2 fuel can be reduced by Zry-4 cladding at high temperatures under good solid state contact conditions to form oxygenstabilized -Zr(O) and metallic U [17][18][19]. Similar to the interaction between UO 2 and Zry-4 system, the solid state interaction between U 3 Si 2 and Zry-4 could lead to the formation of Zr-Si compounds and U.…”

First principles phase diagram calculations for the octahedral-interstitial system αTiOX, 0≤X≤1/2

“…Zircalloy is used as nuclear fuel-rod cladding in light water reactors, but it is metastable with respect to oxidation by the UO 2 fuel. [1][2][3][4] Oxidation of zircalloy transforms it from the high-temperature (high-T), oxygen-poor, bcc solution (βZr X ) into the low-T, oxygen-rich, hcp-based solution (αZrO X ). At temperatures between about 1173K and 573K various ordered phases have been reported.…”

Effects of interaction between molten zircaloy and irradiated MOX fuel on the fission product release behavior

“…When the temperature was raised above the melting point of Zry cladding (2033 K), the liquefaction of Zry occurred. The fractional release, however, continued to follow the diffusion rule because the molten Zry wet the fuel poorly [10,40,41]. After sufficient wettability was established, the fuel dissolution occurred, resulting in the increase of the fractional release of Cs which was held in the crystalline solid fuel.…”