Abstract
A cooling system design for the processing of radioactive waste drums is investigated in this work, with the objective of providing insights for the determination of the air flow rate required to ensure an acceptable slag temperature (323 K or below) after 5 days. A methodology based on both 3D and 2D axisymmetric Computational Fluid Dynamics (CFD) modelling is developed. Transient temperature distributions within the drums in time and space determined by the heat transfer characteristics are studied in detail. A sensitivity analysis is also carried out assuming different physical properties of the radioactive slag. It was found out that for all variations analyzed, the maximum temperature of slag at the end of five days cooling is below 323 K, where the maximum outlet air temperature for a minimum air inlet velocity of 1 m/s is between 320 K and 323 K depending on the radioactive slag properties. When glass-like radioactive slag properties are assumed, the internal heat conduction within the slag is limiting the overall heat transfer, therefore requiring significantly longer cooling times.
Highlights
Heat transfer is one of the fundamental aspects to consider for nuclear waste processing and storage, and it has been the objective of many research studies
Fluid Dynamics (CFD) is commonly used for the design and research of the heat transfer processes associated to nuclear power generation, such as reactor cooling, nuclear material rods cooling, and safety issues
Weng et al [1] carried out a Computational Fluid Dynamics (CFD) investigation of the performance of a special direct vessel injection (DVI) structure for the core cooling system in a
Summary
Heat transfer is one of the fundamental aspects to consider for nuclear waste processing and storage, and it has been the objective of many research studies. Fluid Dynamics (CFD) is commonly used for the design and research of the heat transfer processes associated to nuclear power generation, such as reactor cooling, nuclear material rods cooling, and safety issues. Weng et al [1] carried out a CFD investigation of the performance of a special direct vessel injection (DVI) structure for the core cooling system in a. Flow mixing and heat transfer capability in the reactor vessel was analysed under different injection conditions. CFD thermal hydraulic simulations of the moderator tank in a pressure vessel PHWR were carried out by Corzo et al [4], considering the heat source by neutron thermalization. Park et al [5] carried out an experimental study on a novel liquid metal fin concept for the prevention of boiling critical heat flux, and their CFD simulations confirmed that heat transfer
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