Saudi International Conference On Nuclear Power Engineering (SCOPE)

Severe accident management (SAM) measures play a significant role in mitigating severe accidents in
nuclear power plants (NPPs). Their proper design requires a thorough understanding of processes
leading to severe accidents and the related phenomena. As SAM measures are being increasingly
considered in regulation of NPPs operation, it is of utmost importance that suitable database is...

The Chernobyl and Fukushima nuclear accidents have significantly impacted the public's perception of nuclear energy and its potential benefits. To fully harness nuclear technology's potential for contributing to the Sustainable Development Goals (SDGs), as highlighted by the IAEA bulletin of September 2016, we must restore public confidence in this energy source. Emergency preparedness and...

Nuclear reactors and associated structural facilities are designed to withstand various types of loadings including thermal, vibrational and fatigue etc. Despite meticulous design incorporations, these structures can be damaged during operation due to unforeseen scenarios and can cause imminent danger in retrospect of nuclear radiation leakages, loss of critical infrastructure and life. To...

Source term evaluation constitutes an important feature and element for Severe Accident Management (SAM) strategy. For assessment of SAM efficiency it is crucial to identify phenomena and parameters that present major contributions to the uncertainty in the magnitude and timing of the releases, assess their sensitivity, and quantify the uncertainty. In this work source term evaluation and...

Severe Accidents (SA) are the most complex, extreme, and unlikely accident scenarios that might occur in a Nuclear Power Plant (NPP). However, no matter how unlikely they are, the five accidents that already occurred in commercial NPPs (TMI-2 [1], Chernobyl-4 [2] and Fukushima Daiichi (Units 1 through 3) [3]), highlight that “improbable” does not mean “impossible” and, given their potential...

Determination of a source term is an essential part in the chain of nuclear safety analyses and serves as a cornerstone to following analyses of radiological consequences. Aside the design basis accidents like large break LOCA, events where primary coolant bypasses the containment may be of high importance. Such accidents are steam generator tube ruptures, where a flow of activities from...

This work aimed to validate a MELCOR model of the Reactor Cavity Cooling System (RCCS) by conducting Computational Fluid Dynamics (CFD) simulations. The development of a passive heat removal system design falls under the category of safety systems, which require guaranteed functionality and verification during the licensing process for the construction and operation of nuclear reactors, both...