The accident-tolerant fuel concept involves replacing the conventional cladding system (zirconium) with a new material or coating that has specific thermomechanical properties. aim of this study is to evaluate neutronics performance chromium and design solutions. A Zircaloy–uranium (Zr–U) currently used as standard in pressurized water reactors around world. This investigation presents benefits...

In-depth understanding of nuclear fuel behaviour under operation is critical to anticipate and prevent severe accidents. Loss-of-cooling events can lead core meltdown, formation U–Zr–O liquids (the basic components corium lavas), formed molten cladding. To improve the knowledge on those liquid mixtures, we evaluate ability existing interatomic potentials (CRG Yakub) for solid-phase (U, Zr)O2 ac...

SiC/SiC composites are resistant to high temperatures making them excellent candidates for aeronautical or nuclear applications. The robustness of the mechanical behavior CVI-SiC/SiC tubes fuel cladding was examined in this paper. loading direction parallel tube axis, and fibers were oriented ±45° with respect axis. tensile analyzed considering as a unidirectional composite. exhibits convention...

The nuclear industry uses fuel performance codes to demonstrate integrity preservation of rods. These include a complex system models with empirical constants that one needs calibrate for best estimates and uncertainties. However, deriving the appropriate level uncertainty is often challenging due model inadequacies. This paper presents method address inadequacies by adapting mean covariance pa...

The oxide dispersion strengthened (ODS) ferritic steels are one of the most important in fuel cladding materials for 4th Generation nuclear reactors because their excellent mechanical properties such as irradiation resistance, swelling and elevated temperature tensile/compressive strength. Mechanical alloying (MA) is promising routes developing nanocrystalline ODS steel materials. For productio...

Indonesia possesses numerous potential sites for nuclear power plant development. A fast and comprehensive radiological consequences analysis is required to conduct a preliminary of radionuclide release into the atmosphere, including source terms estimation. One simplified method such estimation use Relative Volatility approach by Kess Booth, published in IAEA TECDOC 1127. The objective this st...

Micromechanics techniques, such as nano-indentation and micro-pillar compression, can be applied to study hydrogen-charged zirconium alloys at elevated temperatures, which is highly relevant for the nuclear industry. Such experiments are often conducted inside a scanning electron microscope (SEM) under high-vacuum conditions (10−5 mbar). The combination of high-temperature environment causes so...

The problems of reprocessing and long-term storage spent nuclear fuel (SNF) at power plants with RBMK reactors have not been fully resolved so far. For this reason, are forced to search for new options the disposal fuel, which can provide least temporary SNF storage. One possible solutions problem is switch compacted in reactor pools (SFPs). As number assemblies (SFAs) SFPs increases, a greater...