Current Status of the PSG Monte Carlo Neutron Transport Code

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

    4 Citations (Scopus)

    Abstract

    PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark.
    Original languageEnglish
    Title of host publicationPHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics
    Subtitle of host publicationAdvances in Nuclear Analysis and Simulation
    PublisherAmerican Nuclear Society ANS
    Number of pages10
    ISBN (Electronic)978-0-89448-697-5
    ISBN (Print)0-89448-697-7
    Publication statusPublished - 2006
    MoE publication typeA4 Article in a conference publication
    EventAmerican Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006 - Vancouver, Canada
    Duration: 10 Sep 200614 Sep 2006

    Conference

    ConferenceAmerican Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006
    CountryCanada
    CityVancouver
    Period10/09/0614/09/06

    Fingerprint

    neutrons
    reactor physics
    reactors
    Finland
    simulators
    dosimeters
    assembly
    geometry

    Cite this

    Leppänen, J. (2006). Current Status of the PSG Monte Carlo Neutron Transport Code. In PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation American Nuclear Society ANS.
    Leppänen, Jaakko. / Current Status of the PSG Monte Carlo Neutron Transport Code. PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS, 2006.
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    title = "Current Status of the PSG Monte Carlo Neutron Transport Code",
    abstract = "PSG is a new Monte Carlo neutron transport code, developed at the Technical Research Centre of Finland (VTT). The code is mainly intended for fuel assembly-level reactor physics calculations, such as group constant generation for deterministic reactor simulator codes. This paper presents the current status of the project and the essential capabilities of the code. Although the main application of PSG is in lattice calculations, the geometry is not restricted in two dimensions. This paper presents the validation of PSG against the experimental results of the three-dimensional MOX fuelled VENUS-2 reactor dosimetry benchmark.",
    author = "Jaakko Lepp{\"a}nen",
    year = "2006",
    language = "English",
    isbn = "0-89448-697-7",
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    publisher = "American Nuclear Society ANS",
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    Leppänen, J 2006, Current Status of the PSG Monte Carlo Neutron Transport Code. in PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS, American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation, PHYSOR-2006, Vancouver, Canada, 10/09/06.

    Current Status of the PSG Monte Carlo Neutron Transport Code. / Leppänen, Jaakko.

    PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS, 2006.

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

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    Leppänen J. Current Status of the PSG Monte Carlo Neutron Transport Code. In PHYSOR 2006: American Nuclear Society's Topical Meeting on Reactor Physics: Advances in Nuclear Analysis and Simulation. American Nuclear Society ANS. 2006