Saudi International Conference On Nuclear Power Engineering (SCOPE)

The OECD Nuclear Energy Agency (NEA) Working Group on Analysis and Management of Accidents (WGAMA) addresses activities in the three technical fields of thermal-hydraulics (T/Hs), computational fluid dynamics (CFD) and severe accidents (SAs) related to safety aspects of potential accidental situations in nuclear power plants (NPPs). WGAMA covers existing nuclear reactors and related...

This study evaluates the reactor degradation progression in VVER-1000 due to loss of coolant accident (LOCA) and total station blackout (SBO). The simulation evaluation was carried out using the adaptive SYStem Thermal-hydraulics (ASYST) program. The low-pressure scenario was simulated by modelling 80 mm small break LOCA (SBLOCA) in the cold pressurizer leg in during SBO. This double ended...

In the coupled neutronics and thermal-hydraulics analysis, the void fraction plays a significant role in determining various reactor parameters such as reactor coolant mixture density, neutron moderation, local power distribution, two-phase pressure drop, two-phase flow regimes, and heat transfer coefficient. Consequently, accurate prediction of the void fraction is crucial for nuclear reactor...

In the complex field of nuclear reactor design and analysis, there is a continuous need for sophisticated computational models that can accurately capture the diverse and challenging thermal hydraulic phenomena during steady state and transient conditions. This research sets the stage for the development of a comprehensive system analysis code for nuclear reactor thermal hydraulic design,...

The quality of TRISO coated nuclear fuel particles is crucial to the successful operation and safety of Very-High-Temperature Nuclear Reactors (VHTR). For this reason, the TRISO particles should be free of defects and uniform in size and shape, as well as have a uniform coating. In this respect, the gas-solid spouted bed coating technology of TRISO particles is important. Coating layers around...

Demonstrations of the capabilities of nuclear system analysis codes are required to obtain a license for their use in various applications of nuclear power plants. The Safety and Performance Analysis CodE (SPACE) has been developed and approved to be used for licensing applications of Pressurized Water Reactors (PWRs). However, since new innovative designs such as SMART100, a 100 MWe...

Abstract:
Nuclear power is identified as a reliable solution to generate electricity and desalinate water for the base load without intermittence and non-controlled variations. The recourse to nuclear power in Gulf countries started a few years ago. Few plants have already been constructed, in particular in UAE. One of the numerous aspects to be addressed of nuclear power performance is the...