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 ...

The Code O-SUKI-N 3D is an upgraded version of the 2D O-SUKI (Comput. Phys. Commun. 240, 83 (2019)). integrated 3-dimensional (3D) simulation program system for fuel implosion, ignition and burning a direct-drive nuclear-fusion pellet in heavy ion beam (HIB) inertial confinement fusion (HIF).The consists three programs Lagrangian fluid implosion program, data conversion Euler program. can also ...

The propagation of uncertainties in a PWR fuel rod under steady-state irradiation is analyzed by computational means. A hypothetical steady-state scenario of the Three Mile Island 1 reactor fuel rod is modeled with the fuel performance FRAPCON, using realistic input uncertainties for the fabrication and model parameters, boundary conditions and material properties. The uncertainty and sensitivi...

On the Madison Symmetric Torus magnetic fusion plasma experiment, frozen pellet injection is an established method of depositing deuterium fuel into the core of the plasma. To freeze deuterium gas into pellets, the injector is cooled to 10 K with a cryogenic helium refrigerator. To exhaust residual frozen deuterium following injection of each pellet, the injector is warmed by resistive heating ...

During a Reactivity Initiated Accident (RIA), nuclear fuel cladding experiences multiaxial loading state in which the Pellet-Cladding Mechanical Interaction (PCMI) produces strain biaxiality ratio (εzz/εθθ) of between 0 and 1. This study examines effect on fracture Zircaloy-4 cladding. A new mechanical test has been developed order to apply several levels biaxiality. Digital Image Correlation (...