Development of a spatial domain decomposition scheme for Monte Carlo neutron transport

Manuel García, Diego Ferraro, Victor Hugo Sanchez-Espinoza, Luigi Mercatali, Jaakko Leppänen, Ville Valtavirta

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

    Abstract

    The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform large-scale neutron transport simulations, such as full-core burnup or high-fidelity multiphysics. In practice however, software limitations in the majority of the available Monte Carlo codes result in a low efficiency when running in High Performance Computing (HPC) environments, the main issues being inadequate memory utilization and poor scalability. The traditional parallel processing scheme based of splitting particle histories among processes requires domain replication across nodes, and therefore the memory demand for each computing node does not scale, and a memory bottleneck appears for large-scale problems. The scalability of this approach usually limits the resources that can be used efficiently to a small number of nodes/processors. Consequently, massively parallel execution is not viable with particle-based parallelism, at least not by itself. In this work we propose a Spatial Domain Decomposition (SDD) approach to develop an efficient and scalable Monte Carlo neutron transport algorithm. Breaking down the geometry into subdomains, a distributed memory scheme can be used to reduce the in-node memory demand, allowing the simulation of large-scale memory-intensive problems. Additionally, with an efficient neutron tracking algorithm the overall speedup can be significantly improved.

    Original languageEnglish
    Title of host publication26th International Conference on Nuclear Engineering
    Subtitle of host publicationNuclear Fuel and Material, Reactor Physics, and Transport Theory
    PublisherAmerican Society of Mechanical Engineers ASME
    Number of pages7
    Volume3
    ISBN (Print)978-0-7918-5145-6
    DOIs
    Publication statusPublished - Nov 2018
    MoE publication typeNot Eligible
    Event26th International Conference on Nuclear Engineering, ICONE 2018 - London, United Kingdom
    Duration: 22 Jul 201826 Jul 2018
    Conference number: 26

    Conference

    Conference26th International Conference on Nuclear Engineering, ICONE 2018
    Abbreviated titleICONE 2018
    CountryUnited Kingdom
    CityLondon
    Period22/07/1826/07/18

    Fingerprint

    Neutrons
    Decomposition
    Data storage equipment
    Scalability
    Geometry
    Processing

    Cite this

    García, M., Ferraro, D., Sanchez-Espinoza, V. H., Mercatali, L., Leppänen, J., & Valtavirta, V. (2018). Development of a spatial domain decomposition scheme for Monte Carlo neutron transport. In 26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory (Vol. 3). [ICONE26-82144] American Society of Mechanical Engineers ASME. https://doi.org/10.1115/ICONE26-82144
    García, Manuel ; Ferraro, Diego ; Sanchez-Espinoza, Victor Hugo ; Mercatali, Luigi ; Leppänen, Jaakko ; Valtavirta, Ville. / Development of a spatial domain decomposition scheme for Monte Carlo neutron transport. 26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. Vol. 3 American Society of Mechanical Engineers ASME, 2018.
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    abstract = "The computing power available nowadays to the average Monte-Carlo-code user is sufficient to perform large-scale neutron transport simulations, such as full-core burnup or high-fidelity multiphysics. In practice however, software limitations in the majority of the available Monte Carlo codes result in a low efficiency when running in High Performance Computing (HPC) environments, the main issues being inadequate memory utilization and poor scalability. The traditional parallel processing scheme based of splitting particle histories among processes requires domain replication across nodes, and therefore the memory demand for each computing node does not scale, and a memory bottleneck appears for large-scale problems. The scalability of this approach usually limits the resources that can be used efficiently to a small number of nodes/processors. Consequently, massively parallel execution is not viable with particle-based parallelism, at least not by itself. In this work we propose a Spatial Domain Decomposition (SDD) approach to develop an efficient and scalable Monte Carlo neutron transport algorithm. Breaking down the geometry into subdomains, a distributed memory scheme can be used to reduce the in-node memory demand, allowing the simulation of large-scale memory-intensive problems. Additionally, with an efficient neutron tracking algorithm the overall speedup can be significantly improved.",
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    García, M, Ferraro, D, Sanchez-Espinoza, VH, Mercatali, L, Leppänen, J & Valtavirta, V 2018, Development of a spatial domain decomposition scheme for Monte Carlo neutron transport. in 26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. vol. 3, ICONE26-82144, American Society of Mechanical Engineers ASME, 26th International Conference on Nuclear Engineering, ICONE 2018, London, United Kingdom, 22/07/18. https://doi.org/10.1115/ICONE26-82144

    Development of a spatial domain decomposition scheme for Monte Carlo neutron transport. / García, Manuel; Ferraro, Diego; Sanchez-Espinoza, Victor Hugo; Mercatali, Luigi; Leppänen, Jaakko; Valtavirta, Ville.

    26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. Vol. 3 American Society of Mechanical Engineers ASME, 2018. ICONE26-82144.

    Research output: Chapter in Book/Report/Conference proceedingConference article in proceedingsScientificpeer-review

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    García M, Ferraro D, Sanchez-Espinoza VH, Mercatali L, Leppänen J, Valtavirta V. Development of a spatial domain decomposition scheme for Monte Carlo neutron transport. In 26th International Conference on Nuclear Engineering: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. Vol. 3. American Society of Mechanical Engineers ASME. 2018. ICONE26-82144 https://doi.org/10.1115/ICONE26-82144