An analytical model has been developed to describe the release kinetic
s of nonvolatile fission products (e.g., molybdenum, cerium, ruthenium
, and barium) from uranium dioxide fuel under severe reactor accident
conditions. This treatment considers the rate-controlling process of r
elease in accordance with diffusional transport in the fuel matrix and
fission product vaporization from the fuel surface into the surroundi
ng gas atmosphere. The effect of the oxygen potential in the gas atmos
phere on the chemical form and volatility of the fission product is co
nsidered. A correlation is also developed to account for the trapping
effects of antimony and tellurium in the Zircaloy cladding. This model
interprets the release behavior of fission products observed in Commi
ssariat a l'Engerie Atomique experiments conducted in the HEVA/VERCORS
facility at high temperature in a hydrogen and steam atmosphere.