Abstract: In a nuclear reactor, an array of fuel rods containing stacked uranium dioxide pellets clad with zircalloy is the heat source for a thermodynamic cycle of energy conversion from heat to electricity. After fuel is used in a nuclear reactor, the assemblies are stored underwater in a spent nuclear fuel pool at the nuclear power plant while heat generation and radioactive decay rates decrease before it is placed in packages for dry storage or transportation. A computational model of a Boiling Water Reactor spent fuel assembly is modeled using FLUENT, the computational fluid dynamics package. Heat transfer simulations were performed on the two-dimensional 9x9 spent fuel assembly to predict the maximum cladding temperature for different input to the FLUENT model. Uncertainty quantification is used to predict the heat transfer and the maximum temperature profile inside the assembly.
Abstract: Electrolytic dissolution characteristics of UO2 and
SIMFUEL electrodes were studied at several potentials in carbonate
solutions of a high concentration at several pHs. The electrolytic
uranium dissolution was much affected by a corrosion product of
UO2CO3 generated at the electrode during the dissolution in carbonate
solution. The corrosion product distorted the voltammogram at UO2
and SIMFUEL electrodes in the potential region of oxygen evolution
and increased the overpotential of oxygen evolution at the electrode.
The effective dissolution in a carbonate solution could be obtained at
an applied potential such as +4 V (vs SSE) or more which had an
overpotential of oxygen evolution high enough to rupture the
corrosion product on the electrode surface.