A new assembly-level Monte Carlo neutron transport code for reactor physics calculations

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

    Abstract

    This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended for diffusion code group-constant generation and other reactor physics calculations. The code is being developed at the Technical Research Centre of Finland (VTT), under the working title “Probabilistic Scattering Game”, or PSG. The PSG code uses a method known as Woodcock tracking to simulate neutron histories. The advantages of the method include fast simulation in complex geometries and relatively simple handling of complicated geometrical objects. The main drawback is the inability to calculate reaction rates in optically thin volumes. This narrows the field of application to calculations involving parameters integrated over large volumes. The main features of the PSG code and the Woodcock tracking method are introduced. The code is applied in three example cases, involving infinite lattices of two-dimensional LWR fuel assemblies. Comparison calculations are carried out using MCNP4C and CASMO-4E. The results reveal that the code performs quite well in the calculation cases of this study, especially when compared to MCNP. The PSG code is still under extensive development and there are both flaws in the simulation of the interaction physics and programming errors in the source code. The results presented here, however, seem very encouraging, especially considering the early development stage of the code.
    Original languageEnglish
    Title of host publicationMathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005
    PublisherAmerican Nuclear Society ANS
    Number of pages12
    Editioncd-rom
    Publication statusPublished - 2005
    MoE publication typeA4 Article in a conference publication

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    reactor physics
    assembly
    neutrons
    Finland
    games
    programming
    assemblies
    reaction kinetics
    simulation

    Cite this

    Leppänen, J. (2005). A new assembly-level Monte Carlo neutron transport code for reactor physics calculations. In Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005 (cd-rom ed.). American Nuclear Society ANS.
    Leppänen, Jaakko. / A new assembly-level Monte Carlo neutron transport code for reactor physics calculations. Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005. cd-rom. ed. American Nuclear Society ANS, 2005.
    @inproceedings{54f451304dd347b69d5e12cbe714da61,
    title = "A new assembly-level Monte Carlo neutron transport code for reactor physics calculations",
    abstract = "This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended for diffusion code group-constant generation and other reactor physics calculations. The code is being developed at the Technical Research Centre of Finland (VTT), under the working title “Probabilistic Scattering Game”, or PSG. The PSG code uses a method known as Woodcock tracking to simulate neutron histories. The advantages of the method include fast simulation in complex geometries and relatively simple handling of complicated geometrical objects. The main drawback is the inability to calculate reaction rates in optically thin volumes. This narrows the field of application to calculations involving parameters integrated over large volumes. The main features of the PSG code and the Woodcock tracking method are introduced. The code is applied in three example cases, involving infinite lattices of two-dimensional LWR fuel assemblies. Comparison calculations are carried out using MCNP4C and CASMO-4E. The results reveal that the code performs quite well in the calculation cases of this study, especially when compared to MCNP. The PSG code is still under extensive development and there are both flaws in the simulation of the interaction physics and programming errors in the source code. The results presented here, however, seem very encouraging, especially considering the early development stage of the code.",
    author = "Jaakko Lepp{\"a}nen",
    year = "2005",
    language = "English",
    booktitle = "Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005",
    publisher = "American Nuclear Society ANS",
    address = "United States",
    edition = "cd-rom",

    }

    Leppänen, J 2005, A new assembly-level Monte Carlo neutron transport code for reactor physics calculations. in Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005. cd-rom edn, American Nuclear Society ANS.

    A new assembly-level Monte Carlo neutron transport code for reactor physics calculations. / Leppänen, Jaakko.

    Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005. cd-rom. ed. American Nuclear Society ANS, 2005.

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

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    AU - Leppänen, Jaakko

    PY - 2005

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    N2 - This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended for diffusion code group-constant generation and other reactor physics calculations. The code is being developed at the Technical Research Centre of Finland (VTT), under the working title “Probabilistic Scattering Game”, or PSG. The PSG code uses a method known as Woodcock tracking to simulate neutron histories. The advantages of the method include fast simulation in complex geometries and relatively simple handling of complicated geometrical objects. The main drawback is the inability to calculate reaction rates in optically thin volumes. This narrows the field of application to calculations involving parameters integrated over large volumes. The main features of the PSG code and the Woodcock tracking method are introduced. The code is applied in three example cases, involving infinite lattices of two-dimensional LWR fuel assemblies. Comparison calculations are carried out using MCNP4C and CASMO-4E. The results reveal that the code performs quite well in the calculation cases of this study, especially when compared to MCNP. The PSG code is still under extensive development and there are both flaws in the simulation of the interaction physics and programming errors in the source code. The results presented here, however, seem very encouraging, especially considering the early development stage of the code.

    AB - This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended for diffusion code group-constant generation and other reactor physics calculations. The code is being developed at the Technical Research Centre of Finland (VTT), under the working title “Probabilistic Scattering Game”, or PSG. The PSG code uses a method known as Woodcock tracking to simulate neutron histories. The advantages of the method include fast simulation in complex geometries and relatively simple handling of complicated geometrical objects. The main drawback is the inability to calculate reaction rates in optically thin volumes. This narrows the field of application to calculations involving parameters integrated over large volumes. The main features of the PSG code and the Woodcock tracking method are introduced. The code is applied in three example cases, involving infinite lattices of two-dimensional LWR fuel assemblies. Comparison calculations are carried out using MCNP4C and CASMO-4E. The results reveal that the code performs quite well in the calculation cases of this study, especially when compared to MCNP. The PSG code is still under extensive development and there are both flaws in the simulation of the interaction physics and programming errors in the source code. The results presented here, however, seem very encouraging, especially considering the early development stage of the code.

    M3 - Conference article in proceedings

    BT - Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005

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    Leppänen J. A new assembly-level Monte Carlo neutron transport code for reactor physics calculations. In Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications Meeting 2005. cd-rom ed. American Nuclear Society ANS. 2005