Development of a dynamic simulation mode in serpent 2 Monte Carlo code

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

    25 Citations (Scopus)

    Abstract

    This paper presents a dynamic neutron transport mode, currently being implemented in the Serpent 2 Monte Carlo code for the purpose of simulating short reactivity transients with temperature feedback. The transport routine is introduced and validated by comparison to MCNP5 calculations. The method is also tested in combination with an internal temperature feedback module, which forms the inner part of a multi-physics coupling scheme in Serpent 2. The demo case for the coupled calculation is a reactivity-initiated accident (RIA) in PWR fuel.
    Original languageEnglish
    Title of host publicationInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013
    PublisherAmerican Nuclear Society (ANS)
    Pages117-127
    ISBN (Print)978-0-89448-700-2
    Publication statusPublished - 2013
    MoE publication typeA4 Article in a conference publication
    EventInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013 - Sun Valley, ID, United States
    Duration: 5 May 20139 May 2013

    Conference

    ConferenceInternational Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M&C 2013
    Abbreviated titleM&C 2013
    Country/TerritoryUnited States
    CitySun Valley, ID
    Period5/05/139/05/13

    Keywords

    • dynamic Monte Carlo
    • multi-physics
    • RIA
    • serpent
    • temperature feedback

    Fingerprint

    Dive into the research topics of 'Development of a dynamic simulation mode in serpent 2 Monte Carlo code'. Together they form a unique fingerprint.

    Cite this