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MCSIMus: Monte Carlo Simulation with Inline Multiphysics

Lead Research Organisation: University of Cambridge
Department Name: Engineering

Abstract

Nuclear reactors in various forms are increasingly prominent in the context of net zero. However, stringent safety standards and advanced reactor designs necessitate ever-greater certainty and understanding in reactor physics and operation. As physical experimentation becomes more expensive, nuclear engineering relies increasingly on high-fidelity simulation of reactors.

Traditionally, resolving different physical phenomena in a reactor (such as neutron transport or thermal-hydraulics) proceeded by assuming only a weak dependence upon other phenomena due to limits on computational power. Such approximations were allowable when additional conservatisms were included in reactor designs. However, more economical or sophisticated reactor designs render such approximations invalid, and reactor designers must be able to resolve the interplay between each physical phenomenon. This poses a challenge to reactor physicists due to vastly increased computational costs of multi-physics calculations, as well as the risks of numerical instabilities - these are essentially non-physical behaviours which are purely an artefact of simulation.

This proposal aims to provide the basis of new computational approaches in nuclear engineering which are both substantially cheaper and more stable than present multi-physics approaches. Traditional methods tend to have one tool fully resolve one phenomenon, pass the information to another tool which resolves a second phenomenon, and then pass this updated information back to the first tool and repeat until (hopefully) the results converge. This proposal hopes to explore a slightly simpler approach, where information is exchanged between different solvers before each has fully resolved its own physics, extending this to many of the phenomena of interest to a reactor designer. Preliminary analysis suggests that this approach should be vastly more stable and computationally efficient than previous methods. The investigations will be carried out using home-grown numerical tools developed at the University of Cambridge which are designed for rapid prototyping of new ideas and algorithms. The final result is anticipated to transform the nuclear industry's approach to multi-physics calculations and greatly accelerate our ability to explore and design more advanced nuclear reactors.
 
Title Linear sources in the random ray method 
Description This algorithm allows meshes used in neutron transport to be significantly coarsened, reducing memory and runtime. The innovation is taking a previous model and extending it to the random ray method. This algorithm holds significant promise in radiation shielding applications. It is described in detail in https://www.tandfonline.com/doi/full/10.1080/00295639.2024.2394729 
Type Of Material Computer model/algorithm 
Year Produced 2024 
Provided To Others? Yes  
Impact This algorithm has been implemented in the widely used Monte Carlo code OpenMC. This will be applied to radiation shielding challenges in fusion simulations. 
URL https://www.tandfonline.com/doi/full/10.1080/00295639.2025.2458958?src=exp-la
 
Title Memory efficient deterministic neutron noise algorithm 
Description A new algorithm was proposed to reduce the memory burden of deterministic neutron noise calculations. This can make these calculations more tractable, allowing their use as diagnostic tools in nuclear reactors. 
Type Of Material Computer model/algorithm 
Year Produced 2024 
Provided To Others? Yes  
Impact No impacts yet, but it is anticipated that this becomes a common algorithm in neutron noise applications. 
URL https://www.sciencedirect.com/science/article/pii/S0306454924001130
 
Description Random ray work with Argonne 
Organisation Argonne National Laboratory
Country United States 
Sector Public 
PI Contribution We worked together on several papers with ANL members
Collaborator Contribution Intellectual contributions and discussions to creating papers.
Impact Several of the papers published so far are directly attributable to this collaboration.
Start Year 2023
 
Description Random ray work with Michigan 
Organisation University of Michigan
Country United States 
Sector Academic/University 
PI Contribution One of my PhD students will start working with University of Michigan to investigate the random ray method applied to multiphysics reactor problems.
Collaborator Contribution The partner provided supervision and desk space to the student, as well as intellectual contributions.
Impact The collaboration has not fully begun yet.
Start Year 2025
 
Title SCONE 
Description Open-source modifiable neutron transport code. 
Type Of Technology Software 
Year Produced 2017 
Open Source License? Yes  
Impact Research progress for methods in particle transport. 
URL https://github.com/CambridgeNuclear/SCONE