In this article, a criticality and depletion analysis of the European Lead-Cooled Training Reactor (ELECTRA), low-power, compact, fast lead-cooled reactor, was performed. The active core model simulations were made by using MCNPX code. First, is compared with reference influence reflector radius on system analyzed. Secondly, it simulated fuel combustion after 30 years continuous operation ELECT...

Abstract Operating conditions in the liquid metal fast reactor, like higher power density, temperature gradient, and burnup, are more severe to fuel rod comparing light water reactor. The integrity safety of is very essential reactor safety. In this study, designed for M 2 LFR-1000, which a typical pool type lead cooled evaluated using performance analysis code named KMC-Fueltra. Irradiation be...

An SPND (Self-powered Neutron Detector) is commonly used for neutron detection in NPP (Nuclear Power Plant) by virtue of un-reactivity for gamma-rays. But it has a drawback, which is that it cannot detect neutrons in real time due to beta emissions (about > 48 s) after reactions between neutrons and Rh in an SPND. And Generation IV reactors such as MSR (Molten-salt reactor), SFR (Sodium-cooled ...

NEPTUNE_CFD is a code based on a 3D transient Eulerian two-fluid model. One of the main application targets is the two-phase Pressurized Thermal Shock (PTS), which is related to PWR Reactor Pressure Vessel (RPV) lifetime safety studies, when sub-cooled water from Emergency Core Cooling (ECC) system is injected into the possibly uncovered cold leg and penetrates into the RPV downcomer. Five expe...

The chemicals used for the NPs synthesis are TetraEthylOrthoSilicate (TEOS), l-Arginine, chloride acid 0.1M and ethanol. They were supplied by Aldrich and used as received. High-purity deionized water (18.2 M.cm) was produced using Millipore Milli-Q Gradient system. The synthesis follows the same protocol as in our previous work [1]. It is performed in a 2000 ml reactor thermostated with hot wa...

Initiating event analysis is an essential prerequisite of conducting probabilistic safety assessment for nuclear reactors, which plays important role in improving the core design, identifying fault, and guiding operation. In order to determine initiating list SIMONS (Small Innovative helium-xenon cooled Mobile Nuclear power System), preliminary researches on initial were carried out using MLD (...