Abstract
High fidelity modelling for nuclear power plant analysis is becoming more common due to advances in modelling software and the availability of high-performance computers. However, to design, develop and regulate new light water nuclear reactors there are, up until now, limited requirements for high fidelity methods due to the already well-established computational methods already being widely accepted. This article explores the additional detail which can be obtained when using high fidelity methods through Monte Carlo/Sub-channel analysis compared to industrial methods of cross-section/nodal analysis using the Advanced Boiling Water Reactor as a case study. This case study was chosen due to the challenges in modelling two phase flow and the high levels of heterogeneity within the fuel assembly design. The article investigates how to implement such an approach, from a bottom-up procedure, by analysing each stage of the modelling process.
Highlights
Modelling and simulation in the topic of nuclear reactor cores has made very strong progress over the last few decades, mainly sponsored through large international programmes like NURESIM [1] or through national efforts like Consortium for AdvancedSimulation of Light Water Reactors (CASL) [2]
Single Assembly 2D Levels Results. This investigation aimed to understand the differences within the softwares solvers, and the master cross‐section used by taking 2D cross‐sections for each level of each fuel and the master cross-section used by taking 2D cross-sections for each level of each fuel assembly, these were burnt up to 60 GWd/TU using a constant fuel temperature of assembly, these were burnt up to 60 GWd/TU using a constant fuel temperature
This study has identified that the pure neutronic assumptions within DYN3D and Serpent cause large variances of the speeds at which the power profiles move in boiling water reactor (BWR)’s due to the high levels of axial heterogeneity within the design which are not considered within current high-fidelity methods for pressurized water reactor (PWR)
Summary
Modelling and simulation in the topic of nuclear reactor cores has made very strong progress over the last few decades, mainly sponsored through large international programmes like NURESIM [1] or through national efforts like Consortium for AdvancedSimulation of Light Water Reactors (CASL) [2]. Modelling and simulation in the topic of nuclear reactor cores has made very strong progress over the last few decades, mainly sponsored through large international programmes like NURESIM [1] or through national efforts like Consortium for Advanced. Not all of the new efforts seem to be suitable for near term industrial application; the UK has recently delivered their own industrial nuclear reactor core simulation [3] approach. We intend in this publication to have a deeper look into the application of high-fidelity methods for boiling water reactor (BWR) core modelling to determine the requirements which will be used to help improve future industrial BWR simulation technology. The relevant key safety parameters and their evaluation in industrial application in nuclear reactors have not significantly changed over the past thirty years, despite significant advancements in computation power within this time frame. There is no motivation to change the current methodology from an industrial perspective as regulatory bodies are satisfied with the detail being provided because the designs being commissioned are often well understood
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