THE SECOND SAUDI INTERNATIONAL CONFERENCE ON NUCLEAR POWER ENGINEERING (SCOPE-2)

This work presents a preliminary neutronic analysis of the SMART (System-integrated Modular Advanced Reactor), a small modular integral PWR developed by KAERI. The study, conducted at the Nuclear Engineering Department of the Federal University of Minas Gerais (DEN-UFMG), aims to support the future integration of thermal-hydraulic and neutronic simulations for accident-tolerant fuel (ATF)...

This research presents the first application of Sparse Identification of Nonlinear Dynamics (SINDy) to nuclear reactor model identification, specifically targeting Pressurized Water Reactor systems. The identified models provide a foundation for advanced control systems, predictive diagnostics, and operational optimization while maintaining the interpretability required for nuclear safety...

A paper that presents the learning process of using the HCP, parameterized through benchmarking against several existing pebble bed reactor designs such as HTR-10 and HTR-PM. Subsequently, an analysis was conducted on several parameters, including excess reactivity, radionuclide content, and pebble fuel consumption, for each variation of reactor geometry design in order to determine the most...

An Automatic Soluble Boron Scenario Based on a Sliding Mode Observer During Daily Load Follow Operation in APR1400

Optimizing the reload pattern of a nuclear reactor core, such as that of the APR-1400, is a complex and computationally intensive task due to the high dimensionality and non-linearity of the search space. These problems are characterized by numerous local minima, making it challenging to locate the global optimum using conventional deterministic methods. Metaheuristic algorithms like Simulated...

Isotope 232Th is the only isotope of thorium naturally occurring in the nature and it is a fertile material. As a result of neutron capture by 232Th and two consequent beta decays appears fissile isotope 233U being a good nuclear fuel. Furthermore, the use of thorium may result in an extension of the fuel campaign.
There are numerous research papers available on the use of thorium in nuclear...

Following the Fukushima accident, the nuclear industry has accelerated the development of Accident Tolerant Fuel (ATF) technologies aimed at enhancing fuel safety and performance. This includes exploring advanced cladding materials such as chromium-coated Zircaloy, silicon carbide (SiC), and iron-based alloys like FeCrAl and stainless steel (SS), which offer improved resistance to...

Abstract
Controlling reactivity is still a major problem that is typically solved with burnable poisons (BPs). Gadolinium is one example of a single BP that can cause power peaking and uneven depletion. The use of hybrid burnable poisons (HBPs), which balance residual reactivity with neutron absorption, presents a possible substitute. Hybrid BP combinations in VVER-1200 cores have received...

This research presents a parametric extension of Dynamic Mode Decomposition (pDMD) applied to Molten Salt Fast Reactor dynamics analysis. The work addresses the computational limitations of Full-Order Models in nuclear reactor system evaluation, where discretized partial differential equations provide high accuracy at significant computational cost.This work contributes to the broader...

This two-page abstract presents a benchmarking study of the OpenMC Monte Carlo code using the University of Florida Training Reactor (UFTR) as a graphite-moderated test case. It outlines the development of a high-fidelity OpenMC model, the simulation setup, and comparison with experimental reactivity data. The abstract demonstrates OpenMC’s accuracy in modeling graphite-moderated systems and...