Experiments performed by others measured the temperature of an 8x8 array of horizontal heated rods in air within a constant temperature enclosure. That apparatus was a scaled-down model of a spent boiling water reactor fuel assembly in a transport package. In the current work, threedimensional computational fluid dynamics simulations of natural convection and radiation heat transfer within this...

Abstract Electrochemical corrosion of lower-activity spent fuel simulants, SIMFUELs, has been investigated in support on-going analogous studies a real AGR nuclear electrode. Two electrode coupling methods have investigated, to study the sample 25 GWd/tU SIMFUEL pellet 20/25/Nb cladding replicate setup. Method-1 involves individual standalone electrodes, while Method-2 and within same For both ...

In this study, a multi-physics modeling method was developed to analyze nuclear fuel rod's thermo-mechanical behavior especially for high temperature anisotropic creep deformation during ballooning and burst occurring in Loss of Coolant Accident (LOCA). Based on transient heat transfer nonlinear mechanical analysis, the present work newly incorporated special characteristics which include gap t...

The safety report of the TRIGAMark II reactor in Vienna includes three accident scenarios and their deterministic dose consequences to the environment. The destruction of the cladding of the most activated fuel element, the destruction of all fuel elements and a plane crash were considered scenarios in that report. The calculations were made in 1978 with the software program named STRISK. In th...

Cladding or cladding used for nuclear fuel elements requires special requirements such as good mechanical properties, radiation resistance, corrosion adequate physical and chemical low thermal neutron absorption. Materials that are widely structural materials reactors beryllium, magnesium, aluminum, zirconium their alloys. Alloy 9Cr-316-1Mo Nuclear material. material has been made. The was chos...

Among the factors influencing degradation of spent nuclear fuel cladding in interim dry storage, irradiation history and average burnup at discharge must be considered. In fact, due to pellet-cladding contact particularly affecting high fuels, inner surface becomes increasingly exposed damage caused by alpha decaying actinides present rim pellet. Moreover, low temperature conditions characteris...

The United States produces a large amount of cladding material from used nuclear fuel, expected to approach 1,000 MT/year for the next 50 year. This requires a technical route to manage this cladding material. Three approaches (mechanical, thermo-mechanical, chemical) were proposed to manage the radioactive cladding. In the mechanical approach, the cladding is compacted and stored with a cement...