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.
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.
Organisations
- University of Cambridge (Lead Research Organisation)
- Argonne National Laboratory (Collaboration)
- University of Michigan (Collaboration)
- EDF Energy R&D UK Centre Limited (Project Partner)
- Georgia Institute of Technology (Project Partner)
- United Kingdom Atomic Energy Authority (Project Partner)
- Jacobs UK Limited (Project Partner)
- University of Liverpool (Project Partner)
- Imperial College London (Project Partner)
- AWE plc (Project Partner)
People |
ORCID iD |
| Paul Cosgrove (Principal Investigator / Fellow) |
Publications
Cosgrove P
(2024)
A memory-efficient neutron noise algorithm for reactor physics
in Annals of Nuclear Energy
Cosgrove P
(2023)
The Random Ray Method Versus Multigroup Monte Carlo: The Method of Characteristics in OpenMC and SCONE
in Nuclear Science and Engineering
Cosgrove P
(2025)
On the practicalities of producing a nuclear weapon using high-assay low-enriched uranium
in Annals of Nuclear Energy
P. Cosgrove
(2024)
The random ray method applied to fixed source transport problems
R. Neame
(2024)
Linear Source Approximation in The Random Ray Method
Raffuzzi V
(2025)
Application of the Random Ray Method to Variance Reduction in Radiation Shielding Problems
in Nuclear Science and Engineering
Skretteberg M
(2025)
A non-parametric bootstrap method for Monte Carlo neutron transport
in Annals of Nuclear Energy
| 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 |