Nuclear Meltdown Relocation and Core Catcher Analysis

• Autor(a) principal: Bregu, Evald
• Data de Publicação: 2023
• Outros Autores: Ajah, Stephen Aroh, Gomes, Jefferson
• Tipo de documento: Artigo
• Idioma: eng
• Título da fonte: Vetor (Online)
• Texto Completo: https://periodicos.furg.br/vetor/article/view/15158
• topic: Nuclear reactor core; Meltdown relocation; Core Catcher; Lower plenum; Computational Fluid Dynamic; Nuclear Engineering; Volume of Fluid; Level Set; Heat transfer; Núcleo do reator nuclear; Realocação do Núcleo depois do Derretimento; Unidade de Contenção de Núcleo; Plenum inferior

Nuclear meltdown with the potential human and environmental harm is one of the major accident hazard (MAH) faced by nuclear power plants. Limiting (or entirely avoiding) criticality events are the main design strategies for reactors of generations 3½ and 4 (Gen3½ and Gen4). These include ensuring negative void and negative temperature coefficients (for both moderator and fuel) regardless of operational conditions, which provide a self-regulating mechanism that helps preventing accidents occurrence (i.e., to address safety and reliability aspects of Gen4’s goals). However, in severe accident scenarios (e.g. during loss-of-coolant, LOCA, events) where failure to extract heat from the reactor may lead to core degradation, strategies to mitigate reactor meltdown and relocation are critical in the design of safety protocols. This work aims to numerically investigate core relocation as an integrated multi-fluid and heat dynamics problem in which flow of melted materials (UO2, Zircaloy and graphite) are modelled through interface capturing/tracking methods. Two interface tracking/capturing methods were compared, the level-set volume of fluid method (VOF) in Ansys Fluent, and the compressive advection method (CAM) in Fluidity/ICFERST. Both methods are in good agreement for the core relocation simulation. An in-vessel core catcher (IVCC) of tungsten alloy was also proposed to demonstrate core degradation control strategy through cooling of the melted multi-materials. The IVCC was simulated with a multifluid model in Ansys Fluent, in a specified applied heat flux model. The thickness of the IVCC is 0.20 m and the heat flux used is 600 kW m-2. The tungsten material used was able to withstand both thermal and mechanical loads on the lower plenum by extracting decay heat from the corium.