The universal fuel performance code interface in serpent 2

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

    4 Citations (Scopus)

    Abstract

    The increasing interest in high fidelity modeling of power and test reactors drives the development of new tools for multi-physics modeling as well as the coupling capabilities of the current, well established, codes. The simultaneous modeling of fuel performance and core neutronics enables solving the coupled problem between fission power, fuel temperature and mechanical behavior of fuel elements at different parts of the system. To make such considerations easier, an universal fuel performance code interface has been implemented in the Monte Carlo reactor physics code Serpent 2. The interface allows to take in account the temperature and strain distributions, calculated by fuel performance codes, in the neutron transport simulations. Information is transmitted to Serpent 2 via a separate file containing 2D axisymmetric temperature and strain distributions in the fuel elements. The output in the coupled calculation mode includes 2D axisymmetric power distributions and axial fast fluence distributions in different lattice positions. Results from an initial test problem involving the depletion of a short 3D VVER assembly are presented and compared to a similar calculation without the thermal and mechanical feedback
    Original languageEnglish
    Title of host publicationProceedings of LWR Fuel Performance Meeting TopFuel 2013
    PublisherAmerican Nuclear Society ANS
    Pages195-202
    ISBN (Print)978-0-89448-701-9
    Publication statusPublished - 2013
    MoE publication typeA4 Article in a conference publication
    EventLWR Fuel Performance Meeting, Top Fuel 2013 - Charlotte, NC, United States
    Duration: 15 Sep 201319 Sep 2013

    Conference

    ConferenceLWR Fuel Performance Meeting, Top Fuel 2013
    CountryUnited States
    CityCharlotte, NC
    Period15/09/1319/09/13

    Fingerprint

    Physics
    Temperature
    Neutrons
    Feedback
    Hot Temperature

    Cite this

    Valtavirta, V., Tulkki, V., Leppänen, J., & Viitanen, T. (2013). The universal fuel performance code interface in serpent 2. In Proceedings of LWR Fuel Performance Meeting TopFuel 2013 (pp. 195-202). American Nuclear Society ANS.
    Valtavirta, Ville ; Tulkki, Ville ; Leppänen, Jaakko ; Viitanen, Tuomas. / The universal fuel performance code interface in serpent 2. Proceedings of LWR Fuel Performance Meeting TopFuel 2013. American Nuclear Society ANS, 2013. pp. 195-202
    @inproceedings{239e1b44deea43be809af36594aefec4,
    title = "The universal fuel performance code interface in serpent 2",
    abstract = "The increasing interest in high fidelity modeling of power and test reactors drives the development of new tools for multi-physics modeling as well as the coupling capabilities of the current, well established, codes. The simultaneous modeling of fuel performance and core neutronics enables solving the coupled problem between fission power, fuel temperature and mechanical behavior of fuel elements at different parts of the system. To make such considerations easier, an universal fuel performance code interface has been implemented in the Monte Carlo reactor physics code Serpent 2. The interface allows to take in account the temperature and strain distributions, calculated by fuel performance codes, in the neutron transport simulations. Information is transmitted to Serpent 2 via a separate file containing 2D axisymmetric temperature and strain distributions in the fuel elements. The output in the coupled calculation mode includes 2D axisymmetric power distributions and axial fast fluence distributions in different lattice positions. Results from an initial test problem involving the depletion of a short 3D VVER assembly are presented and compared to a similar calculation without the thermal and mechanical feedback",
    author = "Ville Valtavirta and Ville Tulkki and Jaakko Lepp{\"a}nen and Tuomas Viitanen",
    year = "2013",
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    Valtavirta, V, Tulkki, V, Leppänen, J & Viitanen, T 2013, The universal fuel performance code interface in serpent 2. in Proceedings of LWR Fuel Performance Meeting TopFuel 2013. American Nuclear Society ANS, pp. 195-202, LWR Fuel Performance Meeting, Top Fuel 2013, Charlotte, NC, United States, 15/09/13.

    The universal fuel performance code interface in serpent 2. / Valtavirta, Ville; Tulkki, Ville; Leppänen, Jaakko; Viitanen, Tuomas.

    Proceedings of LWR Fuel Performance Meeting TopFuel 2013. American Nuclear Society ANS, 2013. p. 195-202.

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

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    N2 - The increasing interest in high fidelity modeling of power and test reactors drives the development of new tools for multi-physics modeling as well as the coupling capabilities of the current, well established, codes. The simultaneous modeling of fuel performance and core neutronics enables solving the coupled problem between fission power, fuel temperature and mechanical behavior of fuel elements at different parts of the system. To make such considerations easier, an universal fuel performance code interface has been implemented in the Monte Carlo reactor physics code Serpent 2. The interface allows to take in account the temperature and strain distributions, calculated by fuel performance codes, in the neutron transport simulations. Information is transmitted to Serpent 2 via a separate file containing 2D axisymmetric temperature and strain distributions in the fuel elements. The output in the coupled calculation mode includes 2D axisymmetric power distributions and axial fast fluence distributions in different lattice positions. Results from an initial test problem involving the depletion of a short 3D VVER assembly are presented and compared to a similar calculation without the thermal and mechanical feedback

    AB - The increasing interest in high fidelity modeling of power and test reactors drives the development of new tools for multi-physics modeling as well as the coupling capabilities of the current, well established, codes. The simultaneous modeling of fuel performance and core neutronics enables solving the coupled problem between fission power, fuel temperature and mechanical behavior of fuel elements at different parts of the system. To make such considerations easier, an universal fuel performance code interface has been implemented in the Monte Carlo reactor physics code Serpent 2. The interface allows to take in account the temperature and strain distributions, calculated by fuel performance codes, in the neutron transport simulations. Information is transmitted to Serpent 2 via a separate file containing 2D axisymmetric temperature and strain distributions in the fuel elements. The output in the coupled calculation mode includes 2D axisymmetric power distributions and axial fast fluence distributions in different lattice positions. Results from an initial test problem involving the depletion of a short 3D VVER assembly are presented and compared to a similar calculation without the thermal and mechanical feedback

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    Valtavirta V, Tulkki V, Leppänen J, Viitanen T. The universal fuel performance code interface in serpent 2. In Proceedings of LWR Fuel Performance Meeting TopFuel 2013. American Nuclear Society ANS. 2013. p. 195-202