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

Boiling curves, which relate heat flux density to surface superheating, are traditionally derived under stationary conditions and widely used for modeling heat exchange in power equipment. However, real-world scenarios often involve rapid increases in heat flux, such as in reactor power surges or superconducting systems. This study experimentally investigates the differences between boiling...

Boiling flows play a pivotal role in a wide array of industrial processes, particularly in energy systems such as nuclear reactors, where efficient thermal management is essential to ensure system performance and safety. These flows exhibit complex behaviour due to the interaction of multiple phases, and they are characterized by a variety of flow regimes that depend on the local phase...

This research presents the application of Data-Driven Reduced Order Modelling (DDROM) to the DYNASTY experimental facility, addressing computational limitations of high-fidelity nuclear reactor models. The work demonstrates practical validation of theoretical ROM methods using real experimental data from a natural circulation loop.

This paper aims to investigate the compact crossflow heat exchangers (HXs) and their implementation in the lead fast reactors (LFRs). Two different analyses have been performed, following the same geometrical parameters in terms of tube diameter and pitch-to-diameter ratios, as reported in the research work conducted by Ciurluini et al. [1], which addresses the same reactor concept proposed by...

This paper presents an extension of the Incompressible Schrödinger Flow (ISF) method for computational analysis of inviscid fluid flows. The ISF method represents an alternative computational approach to traditional Computational Fluid Dynamics (CFD) and spectral methods for inviscid fluid analysis. The fundamental concept exploits the mathematical analogy between hydrodynamics and quantum...

The current work aims to provide a complete and explicit physics-based model, within the uncertainty of the experimental data, for Vertical upward annular two-phase flow. The model will only require data that is known before-hand without any restriction on its range.

The Kingdom of Saudi Arabia has joined the distinguished group of nations benefiting from nuclear reactor technology. Given the unique environmental conditions of the region, the most effective strategy for nuclear reactor deployment is the development of low-power micro-nuclear plants that can be rapidly installed in remote locations [1]. The key considerations in nuclear reactor...

This paper focuses on thermal-hydraulic analyses to investigate safety-related aspects of the Reference LFR system, a conceptual Small Modular Reactor cooled by molten lead, using the RELAP5/Mod3.3 code in its version modified by the University of Pisa to account for heavy liquid metals as working fluid. The primary aim of this work is to develop a physically accurate model of the Reference...

Hideo Nakamura
Japan Atomic Energy Agency (JAEA)
Tokai, Japan
nakamura.hideo@jaea.go.jp

Ahmed Bentaib
Autorité de sûreté nucléaire et de radioprotection (ASNR)
Fontenay Aux Roses, France
ahmed.bentaib@asnr.fr

Martina Adorni
OECD Nuclear Energy Agency (NEA)
46, quai Alphonse Le Gallo, 92100 Boulogne-Billancourt, France
martina.adorni@oecd-nea.org

Abstract
The Working Group...