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Develop and improve modelling capabilities of reactor vessel internals using ansys

Dafedar, Sajeed (2020) Develop and improve modelling capabilities of reactor vessel internals using ansys.

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Abstract:Nuclear reactors present a unique challenge to researchers interested in building new ones or even just making existing reactors more efficient. By their very nature, it is challenging to observe what is happening in an operating reactor directly. Modelling and simulation provide the ability for scientists and engineers to understand what is happening in the reactor. This thesis deals with developing and improving the modelling capabilities for simulations of the reactor vessel core. It was done in collaboration with Nuclear Research and Consultancy Group (NRG). First, the thesis deals with improving the modelling capabilities of Pressurized Water Reactor (PWR) by considering transient thermal simulations. Transient analysis is an essential tool when designing nuclear reactors since they predict the behaviour of a reactor during changing conditions, such as a control-rod movement, induced by an operator, or an accident scenario. In this thesis, the transient analysis was simulated in ANSYS based on the start-up loading conditions of the pressurized water reactor. The verification of these transient thermal simulations was done based on the thermal heat capacity of the reactor. Later, the modelling capabilities of the SALIENT experiments, which is one of the supporting experiments of the “Dutch Molten-Salt Program” was to be improved. The current model of the SALIENT experiment was unable to find an accurate and stable solution in recent version of APDL due to highly distorted elements. Hence, specific hypotheses were carried out to improve the modelling capabilities for it to converge in latest APDL versions.
Item Type:Essay (Master)
Faculty:ET: Engineering Technology
Subject:52 mechanical engineering
Programme:Mechanical Engineering MSc (60439)
Link to this item:http://purl.utwente.nl/essays/85405
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