In this study an optimization method for the design of combined solar and pellet heating systems is presented and evaluated. The paper describes the steps of the method by applying it for an example of system. The objective of the optimization was to find the design parameters that give the lowest auxiliary energy (pellet fuel + auxiliary electricity) and carbon monoxide (CO) emissions for a sy...

Fuel rods operating for several years in a LWR can experience fuel-cladding gap closure as result of the phenomena due to temperature and irradiation. Local power increase induces circumferential stresses cladding different expansion pellet. In presence corrosive fission products (i.e. Iodine) beyond specific stress threshold level burnup, cracks may grow-up from internal external surface, caus...

Transient fuel behavior in a Light Water-cooled Reactor core depends on nuclear properties (Doppler broadening, moderation ratio, and, sometimes, neutron gas temperature etc.) and variations of thermal-physics parameters (temperature distributions, elongation moderator density). Usually, rough reactor analysis one ignores the very details distributions largely staying frame so-called adiabatic ...

Abstract With the emergence of various novel fuel elements, traditional X-ray test technologies refer to national standards that have gradually been unable meet non-destructive testing (NDT) requirements for these elements. As a new NDT technology, industrial computed tomography (CT) has great potential nuclear In this paper, through personalized transformation self-developed equipment, we carr...

One of the main methods to obtain energy from controlled thermonuclear fusion is inertial confinement fusion (ICF), a process where nuclear fusion reactions are initiated by heating and compressing a fuel target, typically in the form of a pellet that contains deuterium and tritium, relying on the inertia of the fuel mass to provide confinement. In inertial confinement fusion experiments, it is...

The Advanced Fuels Campaign performed a series of irradiation tests minor actinide-bearing mixed oxide fuel (MA-MOX), the so-called AFC-2C&D experiments, to investigate transmutation long-lived transuranic actinide isotopes contained in spent nuclear via fast reactor technology at burnups exceeding 10 % fission initial metallic atoms. This manuscript reports test results derived from one five M...

Pellet-Cladding Interaction (PCI) in a Light Water Reactor is one of the major concerns to guarantee clad integrity while attempting at increasing flexibility PWR nuclear reactor operations follow power grid demand. In order forbid leading failure, modeling capability simulate mechanism has improved through years. Code development needs detailed and precise experimental data. Those data result ...